Publications authored/co-authored by staff of the Nuclear Data Section

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    Uncertainty propagation in activation cross section measurements
    [Abstract]
    N. Otuka, B. Lalremruata, M.U. Khandaker, A.R. Usman, L.R.M. Punte, Radiat. Phys. Chem.140 (2017) pp. 502-510.
    doi:10.1016/j.radphyschem.2017.01.013
    Abstract
    The IAEA Nuclear Data Section (IAEA NDS) has emphasized the importance of archiving experimental nuclear data with detailed description of the uncertainties to provide reasonable evaluated (recommended) data sets with their uncertainties to end-usersof nuclear data. In order to achieve this goal, the IAEA NDS is transferring relevant knowledge to experimentalists by instructing uncertainty propagation for their specific experiments. This article discusses uncertainty propagation based on detailed description of uncertainties in neutron- and charged-particle-induced activation cross sections measured in our studies.
    Inter-comparison of Hauser-Feshbach model codes toward better actinide evaluations R. Capote, S. Hilaire, O. Iwamoto, T. Kawano and M. Sin, Proc. ND2016, EPJ Web of Conferences 146 (2017) 12034.
    doi:10.1051/epjconf/201714612034
    Optical model with multiple band couplings using soft rotator structure D. Martyanov, E. Soukhovitskii, R. Capote, J.M. Quesada and S. Chiba , Proc. ND2016, EPJ Web of Conferences 146 (2017) 12031.
    doi:10.1051/epjconf/201714612031
    A tool for calculation of 7Li(p,n)7Be neutron source spectra below the three-body break-up reaction threshold
    [Abstract]
    R. Pachuau, B. Lalremruata, N. Otuka, L.R. Hlondo, L.R.M. Punte and H.H. Thanga, Proc. ND2016, EPJ Web of Conferences 146 (2017) 12016.
    doi:10.1051/epjconf/201714612016
    Abstract
    We developed a new deterministic neutron source spectrum code EPEN - Energy of Proton Energy of Neutron - for a given lithium target thickness, sample angular coverage and proton energy from the reaction threshold to the three-body break-up threshold. The angular differential cross sections of the 7Li(p,n0)7Be and 7Li(p,n1)7Be reactions evaluated by Liskien and Paulsen were adopted above 1.95 MeV while the functional form suggested by Macklin and Gibbons was adopted for the 7Li(p,n0)7Be reaction cross section near threshold. The spectra obtained by EPEN are validated by the experimental spectra and also compared with the spectra predicted by two Monte Carlo codes, SimLiT and PINO. The results of comparison are discussed in detail.
    Saturation of coupling of collective levels in optical model calculations of even-even actinides J.M. Quesada, D. Martyanov, E. Soukhovitskiĩ, R. Capote and S. Chiba, Proc. ND2016, EPJ Web of Conferences 146 (2017) 12013.
    doi:10.1051/epjconf/201714612013
    Description of nucleon scattering on 208Pb by a fully Lane-consistent dispersive spherical optical model potential W.L. Sun, J. Wang, E.Sh. Soukhovitskii, R. Capote and J.M. Quesada, Proc. ND2016, EPJ Web of Conferences 146 (2017) 12010.
    doi:10.1051/epjconf/201714612010
    A theoretical study of deuteron-induced surrogate reactions B.V. Carlson, R. Capote and M. Sin, Proc. ND2016, EPJ Web of Conferences 146 (2017) 12001.
    doi:10.1051/epjconf/201714612001
    Investigation of the 27Al(d,x)24Na nuclear reaction for deuteron beam monitoring purpose
    [Abstract]
    M.U. Khandaker, H. Haba, N. Otuka and H.A. Kassim, Proc. ND2016, EPJ Web of Conferences 146 (2017) 11029.
    doi:10.1051/epjconf/201714611029
    Abstract
    Activation cross-sections for the 27Al(d,x)24Na nuclear reaction was measured by using a stacked-foil activation technique combined with high purity germanium (HPGe) γ-ray spectrometry over deuteron energy range of 2–24 MeV. Measured data were critically compared with the available literature data and also with the theoretical data extracted from the TENDL data base. Accuracy of the 27Al(d,x)24Na cross-sections were confirmed by the simultaneous measurements of the natTi(d,x)48V monitor reaction cross-sections. Present results reproduced well the IAEA recommended natTi(d,x)48V reaction cross-sections, but provide slight deviation with the IAEA recommended 27Al(d,x)24Na cross-sections. It may be concluded that the use of 27Al(d,x)24Na in deuteron beam monitoring should not be a perfect choice if one has the option to use the natTi(d,x)48V reaction.
    Measurement of (n, xnγ) reaction cross sections in W isotopes G. Henning, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 11016.
    doi:10.1051/epjconf/201714611016
    (n,xnγ) cross sections on actinides versus reaction code calculations M. Kerveno, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 11012.
    doi:10.1051/epjconf/201714611012
    Fission yield covariances for JEFF: A Bayesian Monte Carlo method O. Leray, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 09023.
    doi:10.1051/epjconf/201714609023
    Nuclear data for ion beam analysis applications P. Dimitriou, V. Semkova and V. Zerkin , Proc. ND2016, EPJ Web of Conferences 146 (2017) 09014.
    doi:10.1051/epjconf/201714609014
    Nuclear data for fusion technology – the European approach U. Fischer, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 09003.
    doi:10.1051/epjconf/201714609003
    IAEA coordinated research project on nuclear data for charged-particle monitor reactions and medical isotope production R. Capote, Aet al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 08007.
    doi:10.1051/epjconf/201714608007
    Experiments in the EXFOR library for evaluation of thermal neutron constants
    [Abstract]
    N. Otuka, R. Capote, V. Semkova, T. Kawai and G. Noguere, Proc. ND2016, EPJ Web of Conferences 146 (2017) 07005.
    doi:10.1051/epjconf/201714607005
    Abstract
    E.J. Axton’s experimental database adopted in evaluation of thermal neutron constants by himself and also by a recent project to update the IAEA Neutron Standard was checked against the experimental literature and EXFOR library. We discovered that many data are found neither in the EXFOR library nor in the articles quoted by Axton due to various reasons. This paper summarizes the status of the experimental data cited by Axton in the experimental literature as well as in the EXFOR library.
    EXFOR – a global experimental nuclear reaction data repository: Status and new developments
    [Abstract]
    V. Semkova, N. Otuka, M. Mikhailiukova, B. Pritychenko and O. Cabellos, Proc. ND2016, EPJ Web of Conferences 146 (2017) 07003.
    doi:10.1051/epjconf/201714607003
    Abstract
    Members of the International Network of Nuclear Reaction Data Centres (NRDC) have collaborated since the 1960s on the worldwide collection, compilation and dissemination of experimental nuclear reaction data. New publications are systematically complied, and all agreed data assembled and incorporated within the EXFOR database. Recent upgrades to achieve greater completeness of the contents are described, along with reviews and adjustments of the compilation rules for specific types of data.
    Dissemination of data measured at the CERN n_TOF facility
    [Abstract]
    E. Dupont, N. Otuka, O. Cabellos et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02045.
    doi:10.1051/epjconf/201714607002
    Abstract
    The n_TOF neutron time-of-flight facility at CERN is used for high quality nuclear data measurements from thermal energy up to hundreds of MeV. In line with the CERN open data policy, the n_TOF Collaboration takes actions to preserve its unique data, facilitate access to them in standardised format, and allow their re-use by a wide community in the fields of nuclear physics, nuclear astrophysics and various nuclear technologies. The present contribution briefly describes the n_TOF outcomes, as well as the status of dissemination and preservation of n_TOF final data in the international EXFOR library.
    TANGRA – an experimental setup for basic and applied nuclear research by means of 14.1 MeV neutrons I. Ruskov, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 03024.
    doi:10.1051/epjconf/201714603024
    Improving activation cross section data with TALYS N. Dzysiuk and A. Koning, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02047.
    doi:10.1051/epjconf/201714602047
    New fit of thermal neutron constants (TNC) for 233,235U, 239,241Pu and 252Cf(sf): Microscopic vs. Maxwellian data V.G. Pronyaev, R. Capote, A. Trkov, G. Noguere and A. Wallner, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02045.
    doi:10.1051/epjconf/201714602045
    Nuclear structure and decay data evaluation in Europe A. Negret, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02042.
    doi:10.1051/epjconf/201714602042
    On the use of the generalized SPRT method in the equivalent hard sphere approximation for nuclear data evaluation G. Noguere, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02036.
    doi:10.1051/epjconf/201714602036
    Propagation of nuclear data uncertainties for fusion power measurements H. Sjostrand, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02034.
    doi:10.1051/epjconf/201714602034
    TALYS/TENDL verification and validation processes: Outcomes and recommendations M. Fleming, J.-C. Sublet, M.R. Gilbert, A. Koning and D. Rochman, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02033.
    doi:10.1051/epjconf/201714602033
    Evaluation of the neutron induced reactions on 235U from 2.25 keV up to 30 MeV A. Trkov, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02029.
    doi:10.1051/epjconf/201714602029
    A new evaluation of the neutron data standards A.D. Carlson, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02025.
    doi:10.1051/epjconf/201714602025
    Covariances for the 56Fe radiation damage cross sections S.P. Simakov, A. Koning and A.Yu. Konobeyev, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02012.
    doi:10.1051/epjconf/201714602012
    n+235U resonance parameters and neutron multiplicities in the energy region below 100 eV M.T. Pigni, R. Capote, A. Trkov and V.G. Pronyaev, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02011.
    doi:10.1051/epjconf/201714602011
    Implementation of a new energy-angular distribution of particles emitted by deuteron induced nuclear reaction in transport simulations P. Sauvan, A. Koning, F. Ogando and J. Sanz, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02010.
    doi:10.1051/epjconf/201714602010
    Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics P. Griffin, D. Rochman and A. Koning, Proc. ND2016, EPJ Web of Conferences 146 (2017) 02008.
    doi:https://doi.org/10.1051/epjconf/201714602008
    The CIELO collaboration: Progress in international evaluations of neutron reactions on Oxygen, Iron, Uranium and Plutonium M.B. Chadwick, et al., Proc. ND2016, EPJ Web of Conferences 146 (2017) 02001
    doi:https://doi.org/10.1051/epjconf/201714612034
    Study of deuteron-induced nuclear reactions on natural tungsten for the production of theranostic 186Re via AVF cyclotron up to 38 MeV
    [Abstract]
    M.U. Khandaker, K. Nagatsu, K. Minegishi, T. Wakui, M.R. Zhang, N. Otuka, Nucl. Instrum. Meth. B 403 (2017) pp. 51-68.
    doi:10.1016/j.nimb.2017.04.087
    Abstract
    Activation cross-sections for the natW(d,x)181,182 m,182 g,183,184m,184g,184g(cum),186gRe, 187W and 182g+m+nTa nuclear reactions were measured from the respective thresholds up to 38 MeV by using a stacked-foil activation technique combined with HPGe γ-ray spectrometry. The results are compared with the available literature data and theoretical data extracted from the TENDL-2015 library, and found only a partial agreement among them. Independent cross-sections for the natW(d,x)182g+m+nTa reactions are reported here for the first time. Physical thick target yields for the investigated reaction products were deduced from the measured cross-sections and compared with the directly measured yields found in the literature. The deduced yield curves indicate that a typical irradiation of an enriched 186W target with 100 μA current from a low energy (<18 MeV) deuteron cyclotron is suitable to obtain more than a hundred GBq activity of 186gRe in no carrier added form.
    Thick and thin target 7Li(p,n)7Be neutron spectra below the three-body breakup reaction threshold
    [Abstract]
    R. Pachuau, B. Lalremruata, N. Otuka, L.R. Hlondo, L.R.M. Punte, H.H. Thanga, Nucl. Sci. Eng. 187 (2017) pp. 70-80.
    doi:10.1080/00295639.2017.1291053
    Abstract
    Recently, we measured the 70Zn(n,γ)71Znm activation cross sections using the 7Li(p,n)7Be neutron source for 2.0 MeV < Ep < 3.7 MeV. Since the time-of-flight and multiple foil activation techniques cannot be applied due to the continuous beam structure and weak neutron flux at the facility, we have to rely on calculated neutron energy spectra for data reduction procedure. There are existing Monte Carlo–based codes such as Protons In Neutrons Out (PINO) and SimLiT for calculation of 7Li(p,n)7Be neutron source spectra at these energies. However, these two codes predicted different neutron spectra at these energy regions. We therefore decided to study the thick and thin target 7Li(p,n)7Be neutron spectra from the reaction threshold to the three-body breakup threshold by deterministic calculation. The predicted neutron spectra near threshold were validated by experimental neutron spectra. Our neutron spectra were compared with those predicted by PINO and SimLiT. Our neutron spectra at Ep = 2.8 and 3.5 MeV agree perfectly with those predicted by SimLiT but not with those predicted by PINO.
    Measurements of neutron capture cross sections on 70Zn at 0.96 and 1.69 MeV
    [Abstract]
    L.R.M. Punte, B. Lalremruata, N. Otuka, S.V. Suryanarayana, Y. Iwamoto, R. Pachuau, B. Satheesh, H.H. Thanga, L.S. Danu, V.V. Desai, L.R. Hlondo, S. Kailas, S. Ganesan, B.K. Nayak, A. Saxena, Phys. Rev. C 95 (2017) p.024619.
    doi:10.1103/PhysRevC.95.024619
    Abstract
    The cross sections of the 70Zn(n,γ)71Znm(T1/2=3.96 ±0.05-h) reaction have been measured relative to the 197Au(n,γ)198Au cross sections at 0.96 and 1.69 MeV using a 7 Li(p,n)7Be neutron source and activation technique. The cross section of this reaction has been measured for the first time in the MeV region. The new experimental cross sections have been compared with the theoretical prediction by talys-1.6 with various level-density models and γ-ray strength functions as well as the tendl-2015 library. The talys-1.6 calculation with the generalized superfluid level-density model and Kopecky-Uhl generalized Lorentzian γ-ray strength function predicted the new experimental cross sections at both incident energies. The 70Zn(n,γ)71Zn>g+m total capture cross sections have also been derived by applying the evaluated isomeric ratios in the tendl-2015 library to the measured partial capture cross sections. The spectrum averaged total capture cross sections derived in the present paper agree well with the jendl-4.0 library at 0.96 MeV, whereas it lies between the tendl-2015 and the jendl-4.0 libraries at 1.69 MeV.
    The TENDL library: Hope, reality and future D. Rochman, et al., Proc. ND 2016, EPJ Web of Conferences 146 (2017) 02006.
    doi:https://doi.org/10.1051/epjconf/201714602006
    Update of the α - n Yields for Reactor Fuel Materials for the Interest of Nuclear Safeguards
    [Abstract]
    S.P. Simakov, Q.Y. van den Berg Nucl. Data Sheets 139 (2017) pp. 190-203.
    doi:10.1016/j.nds.2017.01.005
    Abstract
    The neutron yields caused by spontaneous α-decay of actinides and subsequent (α ,xn) reactions were re-evaluated for the reactor fuel materials UO2, UF6, PuO2 and PuF4. For this purpose, the most recent reference data for decay parameters, α-particle stopping powers and (α,xn) cross sections were collected, analysed and used in calculations. The input data and elaborated code were validated against available thick target neutron yields in pure and compound materials measured at accelerators or with radioactive sources. This paper provides the specific neutron yields and their uncertainties resultant from α -decay of actinides 241Am, 249Bk, 252Cf, 242,244Cm, 237Np, 238−242Pu, 232Th and 232−236,238U in oxide and fluoride compounds. The obtained results are an update of previous reference tables issued by the Los Alamos National Laboratory in 1991 which were used for the safeguarding of radioactive materials by passive non-destructive techniques. The comparison of the updated values with previous ones shows an agreement within one estimated uncertainty (≈10%≈10%) for oxides, and deviations of up to 50% for fluorides.
    Production cross-sections of radionuclides from α-induced reactions on natural copper up to 50 MeV
    [Abstract]
    A.R. Usman, M.U. Khandaker, H. Haba, N. Otuka, M. Murakami, Y. Komori, Appl. Radiat. Isot. 114 (2016) pp. 104-113.
    doi:10.1016/j.apradiso.2016.04.027
    Abstract
    The excitation functions were measured for the natCu(α,x)66,67Ga,65Zn,57,58,60Co reactions in the energy range of 16.5 − 50 MeV. A conventional stacked-foil activation technique combined with HPGe γ-ray spectrometry was employed to determine cross-sections. The measured cross-sections were critically compared with relevant previous experimental data and also with the evaluated data in the TENDL-2014 library. Present results confirmed some of the previous experimental data, whereas only a partial agreement was found with the evaluated data. The measured data are useful for reducing the existing discrepancies in the literature, to improve the nuclear reaction model codes, and to enrich the experimental database towards various applications.
    Neutron-induced fission cross section of237Np in the keV to MeV range at the CERN n TOF facility
    [Abstract]
    M. Diakaki, P. Dimitriou, R. Capote, et al. (n_TOF Collaboration) Phys. Rev. C 93 (2016) 034614.
    doi:10.1103/PhysRevC.93.034614
    Abstract
    The neutron-induced fission cross section of 237Np was experimentally determined at the high-resolution and high-intensity facility n TOF, at CERN, in the energy range 100 keV to 9 MeV, using the 235U(n,f) and 238U(n,f ) cross section standards below and above 2 MeV, respectively. A fast ionization chamber was used in order to detect the fission fragments from the reactions and the targets were characterized as far as their mass and homogeneity are concerned by means of α spectroscopy and Rutherford backscattering spectroscopy respectively. Theoretical calculations within the Hauser-Feshbach formalism have been performed, employing the EMPIRE code, and the model parameters were tuned in order to successfully reproduce the experimental fission cross-sectional data and simultaneously all the competing reaction channels.
    Effects of Fission Yield Data in the Calculation of Antineutrino Spectra for 235U(n,fission) at Thermal and Fast Neutron Energies
    [Abstract]
    A.A. Sonzogni, E.A. McCutchan, T.D. Johnson and P. Dimitriou, Phys. Rev. Lett. 116 (2016) 132502.
    doi:10.1103/PhysRevLett.116.132502
    Abstract
    Fission yields form an integral part of the prediction of antineutrino spectra generated by nuclear reactors, but little attention has been paid to the quality and reliability of the data used in current calculations. Following a critical review of the thermal and fast ENDF/B-VII.1 235U fission yields, deficiencies are identified and improved yields are obtained, based on corrections of erroneous yields, consistency between decay and fission yield data, and updated isomeric ratios. These corrected yields are used to calculate antineutrino spectra using the summation method. An anomalous value for the thermal fission yield of 86Ge generates an excess of antineutrinos at 5–7 MeV, a feature which is no longer present when the corrected yields are used. Thermal spectra calculated with two distinct fission yield libraries (corrected ENDF/B and JEFF) differ by up to 6% in the 0–7 MeV energy window, allowing for a basic estimate of the uncertainty involved in the fission yield component of summation calculations. Finally, the fast neutron antineutrino spectrum is calculated, which at the moment can only be obtained with the summation method and may be relevant for short baseline reactor experiments using highly enriched uranium fuel.
    Generalized Collisional Radiative Model Using Screened Hydrogenic Levels H.-K. Chung, S. H. Hansen, H. A. Scott, Modern Methods in Collisional-Radiative Modeling of Plasmas, pp. 51-79, Ralchenko, Yuri(Ed.), Springer (2016)
    doi:10.1007/978-3-319-27514-7_3
    Nanoscale femtosecond imaging of transient hot solid density plasmas with elemental and charge state sensitivity using resonant coherent diffraction T. Kluge, M. Bussmann, H.-K. Chung, C. Gutt, L. G. Huang, M. Zacharias, U. Schramm and T. E. Cowan, >Phys. Plasmas 23, 033103 (2016)
    doi:10.1063/1.4942786
    Detailed model for hot-dense aluminum plasmas generated by an x-ray free electron laser O. Ciricosta, S. M. Vinko, H.-K. Chung, C. Jackson, R. W. Lee, T. R. Preston, D. S. Rackstraw and J. S. Wark Phys. Plasmas 23, 022707 (2016)
    doi:10.1063/1.4942540
    The virtual atomic and molecular data centre (VAMDC) consortium M. L. Dubernet, B K Antony, Y A Ba, Yu L Babikov, K Bartschat, V Boudon, B J Braams, H-K Chung et al. J. Phys. B: At. Mol. Opt. Phys. 49 074003 (2016)
    Simulations of the time and space-resolved x-ray transmission of a free-electron-laser-heated aluminium plasma D S Rackstraw, S M Vinko, O Ciricosta, H-K Chung, R W Lee and J S Wark, J. Phys. B: At. Mol. Opt. Phys. 49 035603 (2016)
    Free-Electron X-Ray Laser Measurements of Collisional-Damped Plasmons in Isochorically Heated Warm Dense Matter P. Sperling, E. J. Gamboa, H. J. Lee, H. K. Chung, E. Galtier, Y. Omarbakiyeva, H. Reinholz, G. Röpke, U. Zastrau, J. Hastings, L. B. Fletcher, and S. H. Glenzer, Phys. Rev. Lett. 115, 115001 (2015)
    doi:10.1103/PhysRevLett.115.115001
    Benchmark experiment for the cross section of the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions
    [Abstract]
    S. Takács, F. Ditrói, M. Aikawa, H. Haba, N. Otuka, Nucl. Instrum. Meth. B 375 (2016) pp. 60-66.
    doi:10.1016/j.nimb.2016.03.040
    Abstract
    As nuclear medicine community has shown an increasing interest in accelerator produced 99mTc radionuclide, the possible alternative direct production routes for producing 99mTc were investigated intensively. One of these accelerator production routes is based on the 100Mo(p,2n)99mTc reaction. The cross section of this nuclear reaction was studied by several laboratories earlier but the available data-sets are not in good agreement. For large scale accelerator production of 99mTc based on the 100Mo(p,2n)99mTc reaction, a well-defined excitation function is required to optimise the production process effectively. One of our recent publications pointed out that most of the available experimental excitation functions for the 100Mo(p,2n)99mTc reaction have the same general shape while their amplitudes are different. To confirm the proper amplitude of the excitation function, results of three independent experiments were presented (Takács et al., 2015). In this work we present results of a thick target count rate measurement of the Eγ = 140.5 keV gamma-line from molybdenum irradiated by Ep = 17.9 MeV proton beam, as an integral benchmark experiment, to prove the cross section data reported for the 100Mo(p,2n)99mTc and 100Mo(p,pn)99Mo reactions in Takács et al. (2015).
    Development of a Reference Database for Particle-Induced Gamma-ray Emission spectroscopy
    [Abstract]
    P. Dimitriou, H.-W. Becker, I. Bogdanović-Radović, M. Chiari, A. Goncharov, A.P. Jesus, O. Kakuee, A.Z. Kiss, A. Lagoyannis, J. Räisänen, D. Strivay, A. Zucchiatti, Nucl. Instrum. Meth. B 371(2016) pp. 33-36.
    doi:10.1016/j.nimb.2015.09.052
    Abstract
    Particle-Induced Gamma-ray Emission (PIGE) is a powerful analytical technique that exploits the interactions of rapid charged particles with nuclei located near a sample surface to determine the composition and structure of the surface regions of solids by measurement of characteristic prompt γ rays. The potential for depth profiling of this technique has long been recognized, however, the implementation has been limited owing to insufficient knowledge of the physical data and lack of suitable user-friendly computer codes for the applications. Although a considerable body of published data exists in the nuclear physics literature for nuclear reaction cross sections with γ rays in the exit channel, there is no up-to-date, comprehensive compilation specifically dedicated to IBA applications. A number of PIGE cross-section data had already been uploaded to the Ion Beam Analysis Nuclear Data Library (IBANDL) (http://www-nds.iaea.org/ibandl) by members of the IBA community by 2011, however a preliminary survey of this body of unevaluated experimental data has revealed numerous discrepancies beyond the uncertainty limits reported by the authors. Using the resources and coordination provided by the IAEA, a concerted effort to improve the situation was made within the Coordinated Research Project on the Development of a Reference Database for PIGE spectroscopy, from 2011 to 2015. The aim of the CRP was to create a data library for Ion Beam Analysis that contains reliable and usable data on charged particle γ-ray emission cross sections that would be made freely available to the user community. As the CRP has reached its completion, we shall present its main achievements, including the results of nuclear cross-section evaluations and the development of a computer code that will become available to the public allowing for the implementation of a standardless PIGE technique.
    Validation of IRDFF in 252Cf Standard and IRDF-2002 Reference Neutron Fields
    [Abstract]
    Stanislav Simakov, Roberto Capote, Lawrence Greenwood, Patrick Griffin, Albert Kahler, Vladimir Pronyaev, Andrej Trkov and Konstantin Zolotarev, EPJ Web of Conferences 106 (2016) 04011.
    doi:10.1051/epjconf/201610604011
    Abstract
    The results of validation of the latest release of International Reactor Dosimetry and Fusion File, IRDFF-1.03, in the standard 252Cf(s.f.) and reference 235U(nth,f) neutron benchmark fields are presented. The spectrum-averaged cross sections were shown to confirm IRDFF-1.03 in the 252Cf standard spontaneous fission spectrum; that was not the case for the current recommended spectra for 235U(nth,f). IRDFF was also validated in the spectra of the research reactor facilities ISNF, Sigma-Sigma and YAYOI, which are available in the IRDF-2002 collection. The ISNF facility was re-simulated to remove unphysical oscillations in the spectrum. IRDFF-1.03 was shown to reproduce reasonably well the spectrum-averaged data measured in these fields except for the case of YAYOI.
    Toward a New Evaluation of Neutron Standards
    [Abstract]
    A.D. Carlson, V.G. Pronyaev, R. Capote, G.M. Hale, F.-J. Hambsch, T. Kawano, S. Kunieda, W. Mannhart, R.O. Nelson, D. Neudecker, P. Schillebeeckx, S. Simakov, D.L. Smith, P. Talou, X. Tao, A. Wallner and W. Wang, EPJ Web of Conferences 106 (2016) 04002.
    doi:10.1051/epjconf/201610604002
    Abstract
    Measurements related to neutron cross section standards and certain prompt neutron fission spectra are being evaluated. In addition to the standard cross sections, investigations of reference data that are not as well known as the standards are being considered. Procedures and codes for performing this work are discussed. A number of libraries will use the results of this standards evaluation for new versions of their libraries. Most of these data have applications in neutron dosimetry.
    Systematic study of proton capture reactions in medium-mass nuclei relevant to the p process: The case of 103Rh and 113,115In
    [Abstract]
    S. Harissopulos, A. Spyrou, V. Foteinou, M. Axiotis, G. Provatas, P. Demetriou, Phys. Rev. C 93 (2016) 025804.
    doi:10.1103/PhysRevC.93.025804
    Abstract
    The cross sections of the 103Rh(p,γ ) 104Pd and the 113,115In(p,γ ) 114,116Sn reactions have been determined from γ angular distribution measurements carried out at beam energies from 2 to 3.5 MeV. An array of four highly efficient HPGe detectors all shielded with BGO crystals for Compton background suppression was used. Astrophysical S factors and reaction rates were deduced from the measured cross sections. Statistical model calculations were performed using the Hauser-Feshbach (HF) code TALYS and were compared with the new data. A good agreement between theory and experiment was found. In addition, the effect of different combinations of the nuclear input parameters entering the HF calculations on the ground-state reaction rates was investigated. It was found that these rates differ by a factor 3 at the most, being thus within the average discrepancies observed between calculated p-nuclei abundances and observations, if certain combinations of optical model potentials, nuclear level densities, and γ -ray strength functions are used.
    Updated Photonuclear Data Library and Database for Photon Strength Functions
    [Abstract]
    P. Dimitriou, R.B. Firestone, S. Siem, F. Becvar, M. Krticka, V.V. Varlamov, M. Wiedeking, EPJ Web of Conferences 93 (2015) 06004.
    doi:10.1051/epjconf/20159306004
    Abstract
    Photonuclear cross sections and gamma-ray data used to extract Photon Strength Functions are important for a large range of applications including basic sciences. The recommendations of an IAEA Consultant’s Meeting to update the IAEA Photonuclear Data Library and create a Reference Database for Photon Strength Functions are presented.
    Nuclear Data Sheets for A = 227 B. Singh, F. Kondev, E. McCutchan, J. Tuli, et al. Nucl. Data Sheets 132 (2016) 257.
    Measurements of deuteron-induced reaction cross-sections on natural nickel up to 24 MeV
    [Abstract]
    A.R. Usman, M.U. Khandaker, H. Haba, M. Murakami, N. Otuka, Nucl. Instrum. Meth. B 368 (2016) pp. 112-119.
    doi:10.1016/j.nimb.2015.10.077
    Abstract
    Deuteron-induced cross-sections of the natNi(d,x)55–58,60Co, 57Ni, 52g,54Mn and 61Cu reactions were measured from the respective threshold energies to 24 MeV by using a stacked-foil activation technique combined with HPGe γ-ray spectrometry. The results were compared with the available experimental data and also with the evaluated data in the TENDL-2014 library. Present results show a reasonable agreement with the recently reported experimental data while a partial agreement is found with the evaluated data. The results are expected to further enrich the experimental database and to understand the discrepancies among the previous measurements. The natNi(d,x)61Cu cross-sections recommended by the IAEA overestimate recent experimental ones, and their upgrade has been proposed.
    Excitation functions of deuteron-induced nuclear reactions on natural platinum up to 24 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, M. Murakami, N. Otuka, H.A. Kassim, Nucl. Instrum. Meth. B 362 (2015) pp. 151-162.
    doi:10.1016/j.nimb.2015.09.045
    Abstract
    Excitation functions of the natPt(d,x)192,193,194,195,196m2,196,198m,198,199Au, 195m,197Pt and 190(g+m1+0.086m2),192(g+m1),194mIr nuclear reactions were measured from the respective threshold up to 24 MeV deuteron energy by using the stacked foil activation technique combined with HPGe gamma-ray spectrometry. Measured data were critically compared with the available literature data and theoretical data extracted from the TENDL-2013 library, and only partial agreement among them was found. Physical thick target yields for the investigated reaction products were also deduced and compared with the directly measured ones in the literature. The deduced yield curves indicate that a low energy cyclotron (<15 MeV) and a highly enriched 198Pt target could be used to obtain 198,199Au in no carrier added form. All cross-sections for 190(g+m1+0.086m2),194mIr and those for 193,194,196m2,196,199Au, and 195m,197Pt in the lower energy region are reported for the first time.
    Investigation of femtosecond collisional ionization rates in a solid-density aluminium plasma
    [Abstract]
    S. M. Vinko, O. Ciricosta, T. R. Preston, D. S. Rackstraw, C.R.D. Brown, T. Burian, J. Chalupský, B. I. Cho, H.-K. Chung, K. Engelhorn, R. W. Falcone, R. Fiokovinini, V. Hájková, P. A. Heimann, L. Juha, H. J. Lee, R. W. Lee, M. Messerschmidt, B. Nagler, W. Schlotter et al. Nature Communications 6. (2015) pp. 6397
    doi:10.1038/ncomms7397
    Abstract
    The rate at which atoms and ions within a plasma are further ionized by collisions with the free electrons is a fundamental parameter that dictates the dynamics of plasma systems at intermediate and high densities. While collision rates are well known experimentally in a few dilute systems, similar measurements for nonideal plasmas at densities approaching or exceeding those of solids remain elusive. Here we describe a spectroscopic method to study collision rates in solid-density aluminium plasmas created and diagnosed using the Linac Coherent light Source free-electron X-ray laser, tuned to specific interaction pathways around the absorption edges of ionic charge states. We estimate the rate of collisional ionization in solid-density aluminium plasmas at temperatures B30 eV to be several times higher than that predicted by standard semiempirical models.
    Prompt fission neutron spectra in fast-neutron-induced fission of 238U
    [Abstract]
    V.V. Desai, B.K. Nayak, A. Saxena, S.V. Suryanarayana, R. Capote, Phys. Rev. C 92 014609
    doi:10.1103/PhysRevC.92.014609
    Abstract
    Prompt fission neutron spectrum (PFNS) measurements for the neutron-induced fission of 238U are carried out at incident neutron energies of 2.0, 2.5, and 3.0 MeV, respectively. The time-of-flight technique is employed to determine the energy of fission neutrons. The prompt fission neutron energy spectra so obtained are analysed using Watt parametrization to derive the neutron multiplicity and average prompt fission neutron energy. The present experimental PFNS data are compared with the evaluated spectra taken from the ENDF/B-VII.1 library and the predictive calculations carried out using the EMPIRE-3.2 (Malta) code with built-in Los Alamos (LA) and Kornilov PFNS models. The sensitivity of the EMPIRE-3.2 LA model–calculated PFNS to the nuclear level density parameter of the average fission fragment and to the total kinetic energy is investigated. EMPIRE-3.2 LA model PFNS calculations that use Madland 2006–recommended values [D. G. Madland, Nucl. Phys. A 772, 113 (2006)] of the total kinetic energy and the level density parameter a = A/(10 ± 0.5) compare very well to measured data at all incident neutron incident energies.
    High-accuracy determination of the 238U/ 235U fission cross section ratio up to ≈ 1 GeV at n_TOF at CERN
    [Abstract]
    C. Paradela, M. Calviani, D. Tarrıo, E. Leal-Cidoncha, L. S. Leong, L. Tassan-Got, C. Le Naour, I. Duran, N. Colonna, L. Audouin, M. Mastromarco, S. Lo Meo, A. Ventura, G. Aerts, S. Altstadt, H. Alvarez, F. Alvarez-Velarde, S. Andriamonje, J. Andrzejewski, G. Badurek, M. Barbagallo, P. Baumann, V. Be´cares, F. Becvar, F. Belloni, B. Berthier, E. Berthoumieux, J. Billowes, V. Boccone, D. Bosnar, M. Brugger, F. Calvino, D. Cano-Ott, R. Capote,, et al. (n_TOF Collaboration), Phys. Rev. C 91 024602
    doi:10.1103/PhysRevC.91.024602
    Abstract
    The 238U to 235U fission cross section ratio has been determined at n_TOF up to ≈1 GeV, with two different detection systems, in different geometrical configurations. A total of four datasets has been collected and compared. They are all consistent to each other within the relative systematic uncertainty of 3–4%. The data collected at n_TOF have been suitably combined to yield a unique fission cross section ratio as a function of neutron energy. The result confirms current evaluations up to 200 MeV. Good agreement is also observed with theoretical calculations based on the INCL++/Gemini++ combination up to the highest measured energy. The n_TOF results may help solve a long-standing discrepancy between the two most important experimental datasets available so far above 20 MeV, while extending the neutron energy range for the first time up to ≈1 GeV.
    TANGRA-Setup for the Investigation of Nuclear Fission induced by 14.1 MeV neutrons
    [Abstract]
    I.N. Ruskov, Yu.N. Kopatch, V.M. Bystritsky, V.R. Skoy, V.N. Shvetsov, F.-J. Hambsch, S. Oberstedt, R. Capote Noy, P.V. Sedyshev, D.N. Grozdanov, I.Zh. Ivanov, V.Yu. Aleksakhin, E.P. Bogolubov, Yu.N. Barmakov, S.V. Khabarov, A.V. Krasnoperov, A.R. Krylov, J. Obhodaš, L.B. Pikelner, V.L. Rapatskiy, A.V. Rogachev, Yu.N. Rogov, V.I. Ryzhkov, A.B. Sadovsky, R.A. Salmin, M.G. Sapozhnikov, V.M. Slepnev, D. Sudac, O.G. Tarasov, V. Valkovic, D.I. Yurkov, N.I. Zamyatin, Sh.S. Zeynalov, A.O. Zontikov, E.V. Zubarev, Physics Procedia 64 (2015) pp. 163-170.
    doi:10.1016/j.phpro.2015.04.022
    Abstract
    The new experimental setup TANGRA (Tagged Neutrons & Gamma Rays), for the investigation of neutron induced nuclear reactions, e.g. (n,xn'), (n,xn'γ), (n,γ), (n,f), on a number of important isotopes for nuclear science and engineering (235,238U, 237Np, 239Pu, 244,245,248Cm) is under construction and being tested at the Frank Laboratory of Neutron Physics (FLNP) of the Joint Institute for Nuclear Research (JINR) in Dubna.
    Evaluation of the Prompt Fission Neutron Spectrum of Thermal-neutron Induced Fission in U-235
    [Abstract]
    A. Trkov, R. Capote, Physics Procedia 64 (2015) pp. 48-54.
    doi:10.1016/j.phpro.2015.04.007
    Abstract
    A new evaluation of the prompt fission neutron spectra (PFNS) for the neutron-induced fission of the U-235 nucleus is presented. By using differential data as ”shape data” good consistency was achieved between selected sets of differential data. A fit of differential PFNS data with the generalised least-squares method using the GANDR code allowed the estimation of the uncertainties and correlations. All experimental data were consistently fitted in a model independent way giving a PFNS average energy of 2.000 MeV with an estimated 9 keV uncertainty.
    Impact of the Normalization Condition and Model Information on Evaluated Prompt Fission Neutron Spectra and Associated Uncertainties
    [Abstract]
    D. Neudecker, R. Capote, D.L. Smith, T. Burr, P. Talou, Nucl. Scie. Engineering 179 (2015) pp. 381-397.
    doi:http://dx.doi.org/10.13182/NSE14-6
    Abstract
    Low evaluated uncertainties compared to experimental information and a strong model impact were observed in some prompt fission neutron spectrum (PFNS) evaluations that include mean values and covariances stemming from a rigid model. Here, we show by studying the 239Pu PFNS ENDF/B-VII.1 evaluation via generalized least-squares analyses that strong model correlations in combination with the normalization condition on the estimated PFNS and its covariances result in surprisingly low evaluated uncertainties. Furthermore, the model changes the evaluated results by w1s of combined experimental uncertainties near the average outgoing neutron energy (*2 MeV). We show both analytically and by means of representative numerical examples that the normalization condition on the spectrum and its covariances naturally leads to uncertainties reduced by a fully positively correlated scaling uncertainty.
    Evaluation of the 239Pu prompt fission neutron spectrum induced by neutrons of 500 keV and associated covariances
    [Abstract]
    D. Neudecker, P. Talou , T. Kawanoa, D.L. Smith, R. Capote, M.E. Rising, A.C. Kahler, Nucl. Instrum. Meth. A 791 (2015) pp. 80-92.
    doi:http://dx.doi.org/10.1016/j.nima.2015.04.044
    Abstract
    We present evaluations of the prompt fission neutron spectrum (PFNS) of 239Pu induced by 500 keV neutrons, and associated covariances. In a previous evaluation by Talou et al.(2010), surprisingly low evaluated uncertainties were obtained, partly due to simplifying assumptions in the quantification of uncertainties from experiment and model. Therefore, special emphasis is placed here on a thorough uncertainty quantification of experimental data and of the Los Alamos model predicted values entering the evaluation. In addition, the Los Alamos model was extended and an evaluation technique was employed that takes into account the qualitative differences between normalized model predicted values and experimental shape data. These improvements lead to changes in the evaluated PFNS and overall larger evaluated uncertainties than in the previous work. However, these evaluated uncertainties are still smaller than those obtained in a statistical analysis using experimental information only, due to strong model correlations. Hence, suggestions to estimate model defect uncertainties are presented, which lead to more reasonable evaluated uncertainties. The calculated keff of selected criticality benchmarks obtained with these new evaluations agree with each other within their uncertainties despite the different approaches to estimate model defect uncertainties.The keff one standard deviations overlap with some of those obtained using ENDF/B-VII.1, albeit their mean values are further away from unity. Spectral indexes for the Jezebel critical assembly calculated with the newly evaluated PFNS agree with the experimental data for selected(n,γ) and (n,f) reactions, and show improvements for high- energy threshold (n,2n)reactions compared to ENDF/B-VII.1.
    Random Sampling of Correlated Parameters - a Consistent Solution for Unfavourable Conditions
    [Abstract]
    G. Zerovnik, A. Trkov, I.A. Kodeli, R. Capote, D.L. Smith, Nucl. Data Sheets 123 (2015) pp. 185-190.
    doi:http://dx.doi.org/10.1016/j.nds.2014.12.032
    Abstract
    Two methods for random sampling according to a multivariate lognormal distribution – the correlated sampling method and the method of transformation of correlation coefficients – are briefly presented. The methods are mathematically exact and enable consistent sampling of correlated inherently positive parameters with given information on the first two distribution moments. Furthermore, a weighted sampling method to accelerate the convergence of parameters with extremely large relative uncertainties is described. However, the method is efficient only for a limited number of correlated parameters.
    Preliminary Evaluation and Uncertainty Quantification of the Prompt Fission Neutron Spectrum of 239Pu
    [Abstract]
    D. Neudecker, P. Talou, T.N. Taddeucci, R.C. Haight, T. Kawano, H.Y. Lee, D.L. Smith, R. Capote, M.E. Rising, and M.C. White, Nucl. Data Sheets 123 (2015) pp. 146-152.
    doi:http://dx.doi.org/10.1016/j.nds.2014.12.026
    Abstract
    Low evaluated uncertainties were obtained in a previous evaluation of the 239Pu prompt fission neutron spectrum and associated covariances for incident neutrons of 0.5 MeV, which were enlarged a-posteriori before being incorporated into ENDF/B-VII.1. These low evaluated uncertainties triggered an in-depth study and improved estimate of experimental as well as model uncertainties. Here, we will summarize these efforts and show that the improved estimate of experimental and model uncertainties leads to corresponding evaluated uncertainties in good agreement with uncertainties obtained in a statistical analysis based primarily on experimental information.
    Current Issues in Nuclear Data Evaluation Methodology: 235U Prompt Fission Neutron Spectra and Multiplicity for Thermal Neutrons
    [Abstract]
    A. Trkov, R. Capote, V.G. Pronyaev, Nucl. Data Sheets 123 (2015) pp. 8-15.
    doi:http://dx.doi.org/10.1016/j.nds.2014.12.003
    Abstract
    Issues in evaluation methodology of the prompt fission neutron spectra (PFNS) and neutron multiplicity for the thermal-neutron-induced fission of the 235U are discussed. The inconsistency between the experimental differential and integral data is addressed. By using differential data as ”shape data” good consistency was achieved between available sets of differential data. Integral dosimetry data have been used to define the PFNS slope at high outgoing neutron energies, where the quality of the differential data is poor. The inclusion into the fit of measured integral (spectrumaveraged) cross sections had a very small impact in the region where differential PFNS data are abundant and accurate, but removed the discrepancy with integral data at higher neutron emission energies. All experimental data are consistently fitted giving a PFNS average energy of 2.008 MeV. The impact on criticality prediction of the newly evaluated PFNS was tested. The highly enriched 235U solution assemblies with high leakage HEU-SOL-THERM-001 and HEU-SOL-THERM-009 benchmarks are the most sensitive to the PFNS. Criticality calculations for those solutions show a significant increase in reactivity if the average neutron energy of the fission neutrons is reduced from the ENDF/B-VI.5 value of 2.03 MeV. The proposed reduction of the PFNS average energy by 1.1% can be compensated by reducing the average number of neutrons per fission ν at the thermal energy to the Gwin et al. measured value. The simple least-squares PFNS fit was confirmed by a more sophisticated combined fit of differential PFNS data for 233,235U, 239Pu and 252Cf nuclides with the generalised least-squares method using the GMA and GANDR codes.
    Production cross-sections of long-lived radionuclides in deuteron-induced reactions on natural zinc up to 23 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, M. Murakami, N. Otuka, Nucl. Instrum. Meth. B 346 (2015) pp. 8-16.
    doi:10.1016/j.nimb.2015.01.011
    Abstract
    Production cross-sections of long-lived radionuclides 66,67Ga, 64,67Cu, 65,69mZn, and 58m+gCo via a deuteron irradiation on a natural zinc target were measured up to 23 MeV using a stacked-foil activation technique combined with HPGe γ-ray spectrometry. The present results showed partial agreements with the earlier experimental cross-sections and also with the theoretical data extracted from the TENDL-2013 library. Physical thick target yields of the investigated radionuclides were deduced using the measured cross-sections, and they found agreements with the directly measured ones in the literatures except for those reported by Dmitriev et al. for 65Zn. Optimal production pathways of the medically important 67Ga radionuclide using a low energy cyclotron are discussed.
    Saturable Absorption of an X-Ray Free-Electron-Laser Heated Solid-Density Aluminum Plasma
    [Abstract]
    D. S. Rackstraw, O. Ciricosta, S. M. Vinko, B. Barbrel, T. Burian, J. Chalupský B. I. Cho, H.-K. Chung, G. L. Dakovski, K. Engelhorn, V. Hájková, P. Heimann, M. Holmes, L. Juha, J. Krzywinski, R.W. Lee, S. Toleikis, J. J. Turner U. Zastrau and J. S. Wark, Phys. Rev. Lett. 114, 015003 (2015)
    doi:10.1103/PhysRevLett.114.015003
    Abstract
    High-intensity x-ray pulses from an x-ray free-electron laser are used to heat and probe a solid-density aluminum sample. The photon-energy-dependent transmission of the heating beam is studied through the use of a photodiode. Saturable absorption is observed, with the resulting transmission differing significantly from the cold case, in good agreement with atomic-kinetics simulations.
    Definitions of radioisotope thick target yields
    [Abstract]
    N. Otuka and S. Takács, Radiochim. Acta 103 (2015) pp. 1-6.
    doi:10.1515/ract-2013-2234
    Abstract
    Definitions of thick target yields are reviewed in relation to their documentation for the experimental nuclear reaction data library (database). Researchers reporting experimental thick target yields are urged to define their yields clearly with an appropriate unit in order to compile them in the experimental data library (EXFOR) in a consistent manner, and also to properly utilise them for omparison with other experimental and evaluated yields.
    Recent Work Leading Towards a New Evaluation of the Neutron Standards
    [Abstract]
    A.D. Carlson, V.G. Pronyaev, R. Capote, G.M. Hale, F.-J. Hambsch, T. Kawano, S. Kunieda, W. Mannhart, R.O. Nelson, D. Neudecker, P. Schillebeeckx, S. Simakov, D.L. Smith, P. Talou, X. Tao, A. Wallner, W. Wang Nucl. Data Sheets 123 (2015) pp. 27–35
    doi:doi:10.1016/j.nds.2014.12.006
    Abstract
    A new version of the ENDF/B library has been planned. The first step in producing this new library is evaluating the neutron standards. An evaluation is now underway with support from a Data Development Project of the IAEA. In addition to the neutron cross section standards, new evaluations are being done for prompt fission neutron spectra and a number of reference data. Efforts have been made to handle uncertainties in a proper way in these evaluations.
    Opacity effects in a solid-density aluminium plasma created by photo-excitation with an X-ray laser
    [Abstract]
    D. S., Rackstraw, S. M. Vinko, O. Ciricosta, B. I. Cho, K. Engelhorn, H.-K. Chung, ... & J. Wark, High Energy Density Physics, 11, pp. 59-69 (2014)
    doi:10.1016/j.hedp.2014.02.003
    Abstract
    The intensities within the focal spots of the output of recently developed X-ray sources based on free electron- laser (FEL) technology are so great that atoms within the focal region can potentially absorb several photons during the few tens of femtosecond X-ray pulse. Furthermore, the duration of the FEL Xray pulse is comparable to the Auger decay times of inner-shell holes created by the X-rays themselves. We report here how such a scenario can lead to opacity broadening of the fluorescence radiation emitted by the hot, dense plasma, which is created as a result of the X-radiation focussed onto a solid target, and in particular present calculations of the broadening of the Ka emission in a solid-density aluminium target, produced when the FEL photon energy is tuned below the Al K-edge, but is resonant with the Ka transition.
    Measurement and analysis of the 243Am neutron capture cross section at the n_TOF facility at CERN
    [Abstract]
    E. Mendoza, R. Capote, et al., (n_TOF Collaboration) Phys. Rev. C 90 (2014) 034608
    doi:10.1103/PhysRevC.90.034608
    Abstract
    Background: The design of new nuclear reactors and transmutation devices requires to reduce the present neutron cross section uncertainties of minor actinides. Purpose: Improvement of the 243Am(n,γ) cross section uncertainty. Method: The 243Am(n,γ) cross section has been measured at the n_TOF facility at CERN with a BaF2 total absorption calorimeter, in the energy range between 0.7 eV and 2.5 keV. Results: The 243Am(n,γ) cross section has been successfully measured in the mentioned energy range. The resolved resonance region has been extended from 250 eV up to 400 eV. In the unresolved resonance region our results are compatible with one of the two incompatible capture data sets available below 2.5 keV. The data available in EXFOR and in the literature have been used to perform a simple analysis above 2.5 keV. Conclusions: The results of this measurement contribute to reduce the 243Am(n,γ) cross section uncertainty and suggest that this cross section is underestimated up to 25% in the neutron energy range between 50 eV and a few keV in the present evaluated data libraries.
    Uncertainties of mass extrapolations in Hartree-Fock-Bogoliubov mass models
    [Abstract]
    S. Goriely, R. Capote, Phys. Rev. C 89 (2014) 054318
    doi:10.1103/PhysRevC.89.054318
    Abstract
    Some 27 Hartree-Fock-Bogoliubov (HFB) mass models have been developed by the Brussels-Montreal collaboration. Each of these models has been obtained with different model prescriptions or corresponds to a significantly differentminimum in the parameter space. The corresponding uncertainties in the mass extrapolation are discussed. In addition, for each of these models, uncertainties associated with local variations of the model parameters exist. Those are estimated for the HFB-24 mass model using a variant of the backward-forwardMonte Carlo method to propagate the uncertainties on the masses of exotic nuclei far away from the experimentally known regions. The resulting uncertainties are found to be significantly lower than those arising from the 27 HFB mass models. In addition, the derived correlations between the calculated masses and between model parameters are analyzed.
    Neutron-induced fission cross section of 234U measured at the CERN n_TOF facility
    [Abstract]
    R. Sarmento, P. Demetriou, R. Capote, et al., (n_TOF Collaboration), Phys. Rev. C 89 (2014) 044606
    doi:10.1103/PhysRevC.89.044606
    Abstract
    The neutron-induced fission cross section of 234U has been measured at the CERN n_TOF facility relative to the standard fission cross section of 235U from 20 keV to 1.4 MeV and of 238U from 1.4 to 200 MeV. A fast ionization chamber (FIC) was used as a fission fragment detector with a detection efficiency of no less than 97%. The high instantaneous flux and the low background characterizing the n_TOF facility resulted in wide-energy-range data (0.02 to 200 MeV), with high energy resolution, high statistics, and systematic uncertainties bellow 3%. Previous investigations around the energy of the fission threshold revealed structures attributed to β-vibrational levels, which have been confirmed by the present measurements. Theoretical calculations have been performed, employing the TALYS code with model parameters tuned to fairly reproduce the experimental data.
    Evaluation of neutron-induced reactions on 238U nucleus
    [Abstract]
    R. Capote, M. Sin, A. Trkov, M.W. Herman, D. Bernard, G. Noguère, A. Daskalakis, Y. Danon, Procs. Workshop "Nuclear Measurements, Evaluations and Applications (NEMEA-7) Collaborative International Evaluated Library Organisation (CIELO)", 5-8 November 2013, Geel, Belgium, NEA/NSC/DOC(2014)13, OECD 2014, pp. 113-118
    Abstract
    Advanced modelling of neutron-induced reactions on 238U nucleus using the EMPIRE system is aimed at improving our knowledge of the neutron scattering leading to better nuclear data for nuclear power applications. Capture and fission channels in n + 238U reaction are well constrained by available experimental data and IAEA neutron standard evaluations allowing to focus on the impact of elastic and inelastic scattering in evaluated cross-sections. The reaction model includes: i) a new rotational-vibrational dispersive optical model that couples the low-lying collective bands of vibrational character observed in even-even actinides; ii) the Engelbrecht-Weidenmüller transformation allowing inclusion of compound-direct interference effects enhanced by a dispersive treatment of the optical model potential; iii) a multi-humped fission barrier with absorption in the secondary well described within the optical model for fission. Impact of the advanced modelling on inelastic scattering cross-section and corresponding uncertainties is being assessed both by comparison with selected microscopic experimental data and integral criticality benchmarks including measured reaction rates (e.g. FLATTOP, JEMIMA, BIGTEN, MASURCA, PROFIL and PROFIL-2). Additionally, neutron scattering yields on 238U measured accurately at RPI by the time-of-flight technique at 29°, 60°, 112° and 153° have been used as a further constraint on the incident energy dependence of elastic and inelastic scattering of neutrons. Benchmark calculations provided feedback to improve the reaction modelling. The improvement of scattering cross-sections in existing libraries is discussed.
    Neutron-induced reactions on U and Th – A new approach via AMS
    [Abstract]
    A. Wallner, R. Capote, M. Christl, L.K. Fifield, M. Hotchkis, A. Krasa, J. Lachner, J. Lippold, A. Plompen, V. Semkova, M. Srncik, P. Steier, S. Tims, S. Winkler, Procs. Workshop "Nuclear Measurements, Evaluations and Applications (NEMEA-7) Collaborative International Evaluated Library Organisation (CIELO)", 5-8 November 2013, Geel, Belgium, NEA/NSC/DOC(2014)13, OECD 2014, pp. 159-167
    Abstract
    Recent studies exhibit discrepancies at keV and MeV energies between major nuclear data libraries for 238U(n,γ), 232Th(n,γ) and also for (n,xn) reactions. We have extended our initial (n,γ) measurements on 235,238U to higher neutron energies and to additional reaction channels. Neutron-induced reactions on 232Th and 238U were measured by a combination of the activation technique and atom counting of the reaction products using accelerator mass spectrometry (AMS). Natural thorium and uranium samples were activated with quasi-monoenergetic neutrons at IRMM. Neutron capture data were produced for neutron energies between 0.5 and 5 MeV. Fast neutron-induced reactions were studied in the energy range from 17 to 22 MeV. Preliminary data indicate a fair agreement with data libraries; however at the lower band of existing data. This approach represents a complementary method to on-line particle detection techniques and also to conventional decay counting.
    Nuclear data for medical applications – Recent developments and future requirements
    [Abstract]
    A.L. Nichols, R. Capote, Nucl. Data Sheets 120 (2014) pp. 239–241
    doi:10.1016/j.nds.2014.07.056
    Abstract
    Cancer treatment represents a major economic and medical issue because of the extensive incidence of the disease worldwide, with a particularly large rate of increase to be found in developing countries. Over the previous twenty years, the International Atomic Energy Agency (IAEA) has dedicated a series of investigations towards identifying and quantifying the production routes and decay characteristics of radioisotopes judged to be of existing and emerging importance in nuclear medicine and radiotherapy. Both the recommendations formulated during the course of these technical debates and the results of recently completed and on-going IAEA coordinated research projects are focused towards the successful evolution of improvements in nuclear data for medical applications throughout the early 21st century.
    Measurement of the MACS of 159Tb(n,γ) at kT = 30 keV by activation
    [Abstract]
    J. Praena, P.F. Mastinu, M. Pignatari, J.M. Quesada, R. Capote, Y. Morilla, Nucl. Data Sheets 120 (2014) pp. 205–207
    doi:10.1016/j.nds.2014.07.047
    Abstract
    The measurement of the Maxwellian-Averaged Cross-Section (MACS) of the 159Tb(n,γ) reaction at kT = 30 keV by the activation technique is presented. An innovative method for the generation of Maxwellian neutron spectra at kT = 30 keV is used. An experimental value of 2166±181 mb agrees well with the MACS value derived from the ENDF/B-VII.1 evaluation, but is higher than KADoNiS recommended value of 1580±150 mb. Astrophysical implications are studied.
    EMPIRE: A reaction model code for nuclear astrophysics
    [Abstract]
    A. Palumbo, M. Herman, R. Capote, Nucl. Data Sheets 120 (2014) pp. 180–183
    doi:10.1016/j.nds.2014.07.040
    Abstract
    The correct modeling of abundances requires knowledge of nuclear cross sections for a variety of neutron, charged particle and γ induced reactions. These involve targets far from stability and are therefore difficult (or currently impossible) to measure. Nuclear reaction theory provides the only way to estimate values of such cross sections. In this paper we present application of the EMPIRE reaction code to nuclear astrophysics. Recent measurements are compared to the calculated cross sections showing consistent agreement for n-, p- and α- induced reactions of astrophysical relevance.
    Evaluation of neutron resonance cross section data at GELINA
    [Abstract]
    P. Schillebeeckx, B. Becker, R. Capote, F. Emiliani, K. Guber, J. Heyse, K. Kauwenberghs, S. Kopecky, C. Lampoudis, C. Massimi, W. Mondelaers, M. Moxon, G. Noguere, A.J.M. Plompen, V. Pronyaev, P. Siegler, I. Sirakov, A. Trkov, K. Volev, G. Zerovnik, Nucl. Data Sheets 119 (2014) pp. 94–97
    doi:10.1016/j.nds.2014.08.027
    Abstract
    Over the last decade, the EC–JRC–IRMM, in collaboration with other institutes such as INRNE Sofia (BG), INFN Bologna (IT), ORNL (USA), CEA Cadarache (FR) and CEA Saclay (FR), has made an intense effort to improve the quality of neutron-induced cross section data in the resonance region. These improvements relate to both the infrastructure of the facility and the measurement setup, and the data reduction and analysis procedures. As a result total and reaction cross section data in the resonance region with uncertainties better than 0.5 % and 2 %, respectively, can be produced together with evaluated data files for both the resolved and unresolved resonance region. The methodology to produce full ENDF compatible files, including covariances, is illustrated by the production of resolved resonance parameter files for 241Am, Cd and W and an evaluation for 197Au in the unresolved resonance region.
    Study of 234U(n,f) resonances measured at the CERN n_TOF facility
    [Abstract]
    E. Leal-Cidoncha, R. Capote, et al., Nucl. Data Sheets 119 (2014) pp. 42–44
    doi:10.1016/j.nds.2014.08.013
    Abstract
    We present the analysis of the resolved resonance region for the 234U(n,f) cross section data measured at the CERN n_TOF facility. The resonance parameters in the energy range from 1 eV to 1500 eV have been obtained with the SAMMY code by using as initial parameters for the fit the resonance parameters of the JENDL-3.3 evaluation. In addition, the statistical analysis has been accomplished, partly with the SAMDIST code, in order to study the level spacing and the Mehta-Dyson correlation.
    Evaluation of the covariance matrix of estimated resonance parameters
    [Abstract]
    B. Becker, R. Capote, S. Kopecky, C. Massimi, P. Schillebeeckx, I. Sirakov, K. Volev, Nucl. Data Sheets 118 (2014) pp. 381–383
    doi:10.1016/j.nds.2014.04.086
    Abstract
    In the resonance region nuclear resonance parameters are mostly obtained by a least square adjustment of a model to experimental data. Derived parameters can be mutually correlated through the adjustment procedure as well as through common experimental or model uncertainties. In this contribution we investigate four different methods to propagate the additional covariance caused by experimental or model uncertainties into the evaluation of the covariance matrix of the estimated parameters: (1) including the additional covariance into the experimental covariance matrix based on calculated or theoretical estimates of the data; (2) including the uncertainty affected parameter in the adjustment procedure; (3) evaluation of the full covariance matrix by Monte Carlo sampling of the common parameter; and (4) retroactively including the additional covariance by using the marginalization procedure of Habert et al.
    Exclusive multiple emission cross sections in the hybrid Monte Carlo pre-equilibrium model and in EMPIRE-3.1
    [Abstract]
    B.V. Carlson, L. Brito, D.F. Mega, R. Capote, M. Herman, M.E. Rego, Nucl. Data Sheets 118 (2014) pp. 276–279
    doi:10.1016/j.nds.2014.04.057
    Abstract
    We discuss the general concept of exclusive emission cross sections and spectra and the exclusive spectra of the ENDF library. We briefly review the exclusive hybrid Monte Carlo simulation model and show how its exclusive cross sections can be integrated into the reaction code EMPIRE-3.1. We close by discussing several examples.
    Rotational-vibrational description of nucleon scattering on actinide nuclei using a dispersive coupled-channel optical model
    [Abstract]
    J.M. Quesada, R. Capote, E.Sh. Soukhovitskiĩ, S. Chiba, Nucl. Data Sheets 118 (2014) pp. 270-272
    doi:10.1016/j.nds.2014.04.055
    Abstract
    Tamura’s coupling formalism has been extended to consider low-lying rotational bands built on vibrational (single-particle) band heads in well-deformed even-even (odd) actinides. These additional excitations are introduced as a perturbation to the underlying rigid rotor structure that is known to describe well the ground state rotational band of major actinides. Coupling matrix elements needed in extended Tamura’s formalism are derived for both even-even and odd actinides. Employed dispersive optical model (DCCOMP) replaces the incident proton energy Ep (for proton induced reactions) by the equivalent Coulomb subtracted energy in all potential terms including both the imaginary and real potentials with the corresponding dispersive corrections. Therefore, the optical potential becomes fully symmetric for protons and neutrons. This potential is used to fit simultaneously all the available optical experimental databases (including neutron strength functions) for nucleon scattering on 238U and 232Th (even even) nuclei. Quasi-elastic (p,n) scattering data to the isobaric analogue states of the target nuclei are also used to constrain the isovector part of the optical potential. Derived Lane-consistent DCCOMP is based on coupling of almost all levels below 1 MeV of excitation energy. The ground state, octupole, beta, gamma and non-axial rotational bands are considered for even nuclei, and rotational bands built on single-particle levels – for odd nuclei. Application of derived potential to odd targets based on a new coupling scheme is foreseen.
    Fitting prompt fission neutron spectra using Kalman filter integrated with Empire code
    [Abstract]
    G.P.A. Nobre, M. Herman, S. Hoblit, A. Palumbo, R. Capote, A. Trkov, Nucl. Data Sheets 118 (2014) pp. 224-226
    doi:10.1016/j.nds.2014.04.042
    Abstract
    Prompt fission neutron spectra (PFNS) have proven to have a significant effect on criticality of selected benchmarks, in some cases as important as cross-sections. Therefore, a precise determination of uncertainties in PFNS is desired. Existing PFNS evaluations in nuclear data libraries relied so far almost exclusively on the Los Alamos model. However, deviations of evaluated data from available experiments have been noticed at both low and high neutron emission energies. New experimental measurements of PFNS have been recently published, thus demanding new evaluations. The present work describes the effort of integrating Kalman and EMPIRE codes in such a way to allow for parameter fitting of PFNS models. The first results are shown for the major actinides for two different PFNS models (Kornilov and Los Alamos). This represents the first step towards reevaluation of both cross-section and fission spectra data considering both microscopic and integral experimental data for major actinides.
    A fully Lane-consistent dispersive optical model potential for even Fe isotopes based on a soft-rotator model
    [Abstract]
    W. Sun, R. Li, E.Sh. Soukhovitskiĩ, J.M. Quesada, R. Capote, Nucl. Data Sheets 118 (2014) pp. 191-194
    doi:10.1016/j.nds.2014.04.034
    Abstract
    A fully Lane-consistent dispersive coupled-channel optical model (DCCOM) potential is derived that describes nucleon induced reactions on even iron isotopes. Low-lying structure of excited levels in iron even-even isotopes is described by a soft-rotator model that allows for dynamical deformation around the spherical shape. Soft-rotator Hamiltonian parameters are adjusted to reproduce the experimental energies of the low-lying collective levels of these isotopes. The comprehensive experimental database used in the fitting process included all scattering data for neutron and proton scattering up to 200 MeV. Employed Lane-consistent formalism allows deriving a potential fully symmetric for neutrons and protons. Lane consistency of the derived potential was validated by describing the quasi-elastic (p,n) scattering with excitation of IAS states. An exact approach for calculation of inelastic analyzing powers is derived. Calculated elastic and inelastic analyzing powers both for neutron and proton induced reactions were shown to be in good agreement with experimental data demonstrating the reliability of dispersive spin-orbit potential.
    Fluctuations above the resonance range in evaluated data of 55Mn
    [Abstract]
    A. Trkov, R. Capote, L.C. Leal, D.W. Muir, E.Sh. Soukhovitskiĩ, Nucl. Data Sheets 118 (2014) pp. 161-164
    doi:10.1016/j.nds.2014.04.026
    Abstract
    The evaluation procedures for 55Mn are elaborated, focusing on the issues related to the fluctuations in the cross sections above the resolved resonance range. Smooth cross sections are defined in the unresolved resonance range, based on the resolution-broadened total cross section measurements, where relevant. Above this energy fluctuations in the measured total cross section are introduced by scaling all reaction cross sections, but preserving the resolution-broadened total cross section. Special procedures are designed to match the observed structure in the average cosine of scattering by adjusting the ratio of the shape-elastic and compound-elastic contributions to the elastic scattering cross sections. The evaluated data file is being assembled and subjected to rigorous testing, verification and validation.
    Zirconium evaluations for ENDF/B-VII.2 for the fast region
    [Abstract]
    D.A. Brown, R. Arcilla, R. Capote, S.F. Mughabghab, M.W. Herman, A. Trkov, H.I. Kim, Nucl. Data Sheets 118 (2014) pp. 144–146
    doi:10.1016/j.nds.2014.04.021
    Abstract
    We have performed a new combined set of evaluations for 90−96Zr, including new resolved resonance parameterizations from Said Mughabghab for 90,91,92,94,96Zr and fast region calculations made with EMPIRE-3.1. Because 90Zr is a magic nucleus, stable Zr isotopes are nearly spherical. A new soft-rotor optical model potential is used allowing calculations of the inelastic scattering on low-lying coupled levels of vibrational nature. A soft rotor model describes dynamical deformations of the nucleus around the spherical shape and is implemented in EMPIRE/OPTMAN code. The same potential is used with rigid rotor couplings for odd-A nuclei. This then led to improved elastic angular distributions, helping to resolve improper leakage in the older ENDF/B-VII.1β evaluation in KAPL proprietary, ZPR and TRIGA benchmarks. Another consequence of 90Zr being a magic nucleus is that the level densities in both 90Zr and 91Zr are unusually low causing the (n,el) and (n,tot) cross sections to exhibit large fluctuations above the resolved resonance region. To accommodate these fluctuations, we performed a simultaneous constrained generalized least-square fit to (n,tot) for all isotopic and elemental Zr data in EXFOR, using EMPIRE’s TOTRED scaling factor. TOTRED rescales total cross sections so that the optical model calculations are unaltered by the rescaling and the correct competition between channels is maintained. In this fit, all (n,tot) data in EXFOR was used for Ein > 100 keV, provided the target isotopic makeup could be correctly understood, including spectrum averaged data and data with broad energy resolution. As a result of our fitting procedure, we will have full cross material and cross reaction covariance for all Zr isotopes and reactions.
    Physics of neutron interactions with 238U: New developments and challenges
    [Abstract]
    R. Capote, A. Trkov, M. Sin, M. Herman, A. Daskalakis, Y. Danon, Nucl. Data Sheets 118 (2014) pp. 26-31
    doi:10.1016/j.nds.2014.04.003
    Abstract
    The latest release of the EMPIRE-3.1 system (codename Rivoli) is being used in the advanced modeling of neutron induced reactions on the 238U nucleus with the aim of improving our knowledge of neutron scattering. The reaction model includes: (i) a new rotational-vibrational dispersive optical model potential coupling the low-lying collective bands of vibrational character observed in even-even actinides, (ii) the Engelbrecht-Weidenmüller transformation allowing for inclusion of compound-direct interference effects enhanced by a dispersive treatment of the optical model potential, (iii) a multi-humped fission barrier with absorption in the secondary well as described within the optical model for fission, and (iv) a modified Lorentzian model (MLO) of the radiative strength function. Impact of the advanced modeling on elastic and inelastic scattering cross section is being assessed by both comparison with selected microscopic experimental data and integral criticality benchmarks (e.g. FLATTOP, JEMIMA and BIGTEN assemblies). Benchmark calculations provide feedback to improve the reaction modeling and reduce both model and model-parameters uncertainties. Additionally, neutron scattering yields on 238U measured accurately at RPI by the time-of-flight technique at 29, 60, 112 and 153 degrees have been used as a further constraint on the incident energy dependence of elastic and inelastically scattered neutrons. Improvement of scattering cross sections in existing libraries is discussed.
    Elastic and inelastic scattering of neutrons on 238U nucleus
    [Abstract]
    R. Capote, A. Trkov, M. Sin, M.W. Herman, E.Sh. Soukhovitskiĩ, EPJ Web of Conferences 69 00008 (2014)
    doi:10.1051/epjconf/20136900008
    Abstract
    Advanced modelling of neutron induced reactions on the 238U nucleus is aimed at improving our knowledge of neutron scattering. Capture and fission channels are well constrained by available experimental data and neutron standard evaluation. A focus of this contribution is on elastic and inelastic scattering cross sections. The employed nuclear reaction model includes – a new rotational-vibrational dispersive optical model potential coupling the low-lying collective bands of vibrational character observed in even-even actinides; – the Engelbrecht-Weidenmüller transformation allowing for inclusion of compound-direct interference effects; – and a multi-humped fission barrier with absorption in the secondary well described within the optical model for fission. Impact of the advanced modelling on elastic and inelastic scattering cross sections including angular distributions and emission spectra is assessed both by comparison with selected microscopic experimental data and integral criticality benchmarks including measured reaction rates (e.g. JEMIMA, FLAPTOP and BIG TEN). Benchmark calculations provided feedback to improve the reaction modelling. Improvement of existing libraries will be discussed.
    Quasi-differential neutron scattering from 238U from 0.5 to 20 MeV
    [Abstract]
    A.M. Daskalakis, R.M. Bahran, E.J. Blain, B.J. McDermott, S. Piela, Y. Danon, D.P. Barry, G. Leinweber, R.C. Block, M.J. Rapp, R. Capote, A. Trkov, Ann. Nucl. Energy 73 (2014) pp. 455-464
    doi:10.1016/j.anucene.2014.07.023
    Abstract
    The Rensselaer Polytechnic Institute Linear Accelerator was used to produce a pulsed neutron beam that was incident on a 238U scattering sample 30 m from the source. Eight liquid scintillator (EJ-301) proton recoil fast neutron detectors located at several angles surrounding the sample were positioned at a distance 0.5 m. Neutrons resulting from elastic scattering, inelastic scattering, and fission reactions were recorded as a function of time-of-flight. Pulse shape analysis including a new gamma misclassification correction was used to reduce erroneous counts from gamma events produced from fission and inelastic scattering reactions. The experimental data were simulated using an improved model of the Rensselaer Polytechnic Institute neutron scattering system that included individual detector efficiencies and neutron flux shape. The experimental data were compared with several evaluated nuclear data libraries using a figure-of-merit. Overall, the JENDL-4.0 evaluation provided the best agreement with the 238U experimental data. Furthermore, the Rensselaer Polytechnic Institute scattering model was used to constrain uncertainties that allowed for improvements to a new 238U evaluation.
    Recent Developments in the Experimental Nuclear Reaction Data Library EXFOR
    [Abstract]
    V. Semkova, N. Otuka, S. Simakov, V. Zerkin, EPJ Web of Conferences 66 03078 (2014)
    doi:10.1051/epjconf/20146603078
    Abstract
    The International Network of Nuclear Reaction Data Centres (NRDC) provides nuclear reaction data services to users through collection and compilation of experimental nuclear reaction data in the EXFOR database. The database includes neutron-induced, charged-particle-induced, and photonuclear data for projectile energies up to 1 GeV. Sophisticated search options and user-friendly retrieval interface for downloading data in different formats have been developed at IAEA Nuclear Data Section. Additional output options such as data plotting capabilities are provided as well. The database is constantly revised and extended and at present contains about 20,000 experimental works accumulated in its 40 years of history. The paper will present several recent IAEA NDS activities related to the development of the EXFOR database and retrieval system.
    Measurement of Neutron Activation Cross Sections on Mo isotopes in the Energy Range from 7 MeV to 15 MeV
    [Abstract]
    Valentina Semkova, Ralf Nolte, EPJ Web of Conferences 66 03077 (2014)
    doi:10.1051/epjconf/20146603077
    Abstract
    An experimental study of the 92Mo(n,p)92Nbm, 92Mo(n,α)89Zr, 95Mo(n,p)95mNb, 95Mo(n,p)95Nb, 96Mo(n,p)96Nb, 97Mo(n,p)97Nb, 98Mo(n,p)98Nbm, 98Mo(n,α)95Zr, 100Mo(n,α) 97Zr, and 92Mo(n,2n)99Mo activation reaction cross sections were carried out in the 7-15 MeV energy range at the CV28 compact cyclotron at Physikalisch-Technische Bundesanstalt, Braunschweig. The PTB TOF spectrometer with a D(d,n) source is well suited for this difficult energy range were significant correction for non-monoenergetic neutrons have to be applied. Gamma-ray spectrometry was applied for the measurements of the activity of the reaction products.
    Quality Assurance of the Cross-sections Measured on p+Li/C Source
    [Abstract]
    M. Majerle, P. Bém, J. Novák, E. Šimečkova, M. Štefánik, S. Simakov, and U. Fischer, Nuclear Data Sheets 119 (2014) 425-428
    doi:doi:10.1016/j.nds.2014.08.120
    Abstract
    Irradiation of material with quasi-monoenergetic neutrons with energies up to 35 MeV is routinely used for cross-section measurement. Neutron irradiation, gamma measurement, and cross-section extraction are three steps in obtaining the final cross-section, each of them contributing to the final uncertainty. The nature of the spectra, which consists of the monoenergetic peak and the continuum at lower energies, makes the extraction of the cross-sections a non-trivial problem and different methods of extraction are used. In this paper, we identify the main sources of uncertainties, discuss possible improvements, and address the differences between some commonly used methods of cross-section extraction.
    The Neutrons for Science Facility at SPIRAL-2
    [Abstract]
    X. Ledoux, M. Aïche, M. Avrigeanu, V. Avrigeanu, L. Audouin, E. Balanzat, B. Ban-détat, G. Ban, G. Barreau, E. Bauge, G. Bélier, P. Bem, V. Blideanu, C. Borcea, S. Bouffard, T. Caillaud, A. Chatillon, S. Czajkowski, P. Dessagne, D. Doré, M. Fallot, F. Farget, U. Fischer, L. Giot, T. Granier, S. Guillous, F. Gunsing, C. Gustavsson, B. Jacquot, K. Jansson, B. Jurado, M. Kerveno, A. Klix, O. Landoas, F.R. Lecolley, J.L. Lecouey, M. Majerl, N. Marie, T. Materna, J. Mrazek, F. Negoita, J. Novak, S. Oberstedt, A. Oberstedt, S. Panebianco, L. Perrot, A.J.M. Plompen, S. Pomp, J.M. Ramillon, D. Ridikas, B. Rossé, G. Rudolf, O. Serot, S.P. Simakov, E. Simeckova, A.G. Smith, J.C. Sublet, J. Taieb, L. Tassan-Got, D. Tarrio, A. Takibayev, I. Thfoin, I. Tsekhanovich, and C. Varignon, Nuclear Data Sheets 119 (2014) 353-356
    doi:doi:10.1016/j.nds.2014.08.097
    Abstract
    The Neutrons For Science (NFS) facility is a component of SPIRAL-2 laboratory under construction at Caen (France). SPIRAL-2 is dedicated to the production of high intensity Radioactive Ions Beams (RIB). It is based on a high-power linear accelerator (LINAG) to accelerate deuterons beams in order to produce neutrons by breakup reactions on a C converter. These neutrons will induce fission in 238U for production of radioactive isotopes. Additionally to the RIB production, the proton and deuteron beams delivered by the accelerator will be used in the NFS facility. NFS is composed of a pulsed neutron beam and irradiation stations for cross-section measurements and material studies. The beams delivered by the LINAG will allow producing intense neutron beams in the 100 keV-40 MeV energy range with either a continuous or quasi-mono-energetic spectrum. At NFS available average fluxes will be up to 2 orders of magnitude higher than those of other existing time-of-flight facilities in the 1 MeV - 40 MeV range. NFS will be a very powerful tool for fundamental physics and application related research in support of the transmutation of nuclear waste, design of future fission and fusion reactors, nuclear medicine or test and development of new detectors. The facility and its characteristics are described, and several examples of the first potential experiments are presented.
    The CIELO Collaboration: Neutron Reactions on 1H, 16O, 56Fe, 235,238U, and 239Pu
    [Abstract]
    M.B. Chadwick, E. Dupont, E. Bauge, A. Blokhin, O. Bouland, D.A. Brown, R. Capote, A. Carlson, Y. Danon, C. De Saint Jean, M. Dunn, U. Fischer, R.A. Forrest, S.C. Frankle, T. Fukahori, Z. Ge, S.M. Grimes, G.M. Hale, M. Herman, A. Ignatyuk, M. Ishikawa, N. Iwamoto, O. Iwamoto, M. Jandel, R. Jacqmin, T. Kawano, S. Kunieda, A. Kahler, B. Kiedrowski, I. Kodeli, A.J. Koning, L. Leal, Y.O. Lee, J.P. Lestone, C. Lubitz, M. MacInnes, D. McNabb, R. McKnight, M. Moxon, S. Mughabghab, G. Noguere, G. Palmiotti, A. Plompen, B. Pritychenko, V. Pronyaev, D. Rochman, P. Romain, D. Roubtsov, P. Schillebeeckx, M. Salvatores, S. Simakov, E.Sh. Soukhovitskiĩ, J.C. Sublet, P. Talou, I. Thompson, A. Trkov, R. Vogt, and S. van der Marck, Nuclear Data Sheets 118 (2014) pp. 1-25
    doi:10.1016/j.nds.2014.04.002
    Abstract
    CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. The focus will initially be on a small number of the highest-priority isotopes, namely 1H, 16O, 56Fe, 235,238U, and 239Pu. This paper identifies discrepancies between various evaluations of the highest priority isotopes, and was commissioned by the OECD’s Nuclear Energy Agency WPEC (Working Party on International Nuclear Data Evaluation Co-operation) during a meeting held in May 2012. The evaluated data for these materials in the existing nuclear data libraries — ENDF/BVII.1, JEFF-3.1, JENDL-4.0, CENDL-3.1, ROSFOND, IRDFF 1.0 — are reviewed, discrepancies are identified, and some integral properties are given. The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations.
    Working Party on International Nuclear Data Evaluation Cooperation (WPEC)
    [Abstract]
    E. Dupont, M.B. Chadwick, Y. Danon, C. De Saint Jean, M. Dunn, U. Fischer, R.A. Forrest, T. Fukahori, Z. Ge, H. Harada, M. Herman,0 M. Igashira,1 A. Ignatyuk,2 M. Ishikawa, O. Iwamoto,8 R. Jacqmin, A.C. Kahler, T. Kawano, A.J. Koning,3 L. Leal, Y.O. Lee,4 R. McKnight, D. McNabb, R.W. Mills, G. Palmiotti, A. Plompen, M. Salvatores, and P. Schillebeeckx, Nuclear Data Sheets 118 (2014) 264-267
    doi:10.1016/j.nds.2014.07.063
    Abstract
    The OECD Nuclear Energy Agency (NEA) organizes cooperation between the major nuclear data evaluation projects in the world. The NEA Working Party on International Nuclear Data Evaluation Cooperation (WPEC) was established to promote the exchange of information on nuclear data evaluation, measurement, nuclear model calculation, validation, and related topics, and to provide a framework for cooperative activities between the participating projects. The working party assesses nuclear data improvement needs and addresses these needs by initiating joint activities in the framework of dedicated WPEC subgroups. Studies recently completed comprise a number of works related to nuclear data covariance and associated processing issues, as well as more specific studies related to the resonance parameter representation in the unresolved resonance region, the gamma production from fission product capture reactions, the 235U capture cross section, the EXFOR database, and the improvement of nuclear data for advanced reactor systems. Ongoing activities focus on the evaluation of 239Pu in the resonance region, scattering angular distribution in the fast energy range, and reporting/usage of experimental data for evaluation in the resolved resonance region. New activities include two subgroups on improved fission product yield evaluation methodologies and on modern nuclear database structures. Future activities under discussion include a pilot project for a Collaborative International Evaluated Library Organization (CIELO) and methods to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data. In addition to the above mentioned short-term task-oriented subgroups, WPEC also hosts a longer-term subgroup charged with reviewing and compiling the most important nuclear data requirements in a high priority request list (HPRL).
    Deuteron-induced activation cross-sections on natural copper up to 24 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, M. Murakami, N. Otuka, H.A.Kassim, J. Radioanal. Nucl. Chem. 302 (2014) pp. 759-764.
    doi:10.1007/s10967-014-3186-y
    Abstract
    Activation cross-sections of natCu(d,x)62,65Zn, 64Cu,60g+mCo,59Fe reactions were measured using a stacked foil activation technique combined with HPGe gamma-ray spectrometry up to the deuteron energy of 24 MeV. Measured data were critically compared with the available literature data and theoretical data extracted from the TENDL-2012 library, and found only partial agreements among them. Cross-sections of natCu(d,x)59Fe reactions are reported here for the first time in the energy region of 19–23 MeV. Measured cross-sections of the long-lived 65Zn, 60gCo and 59Fe radionuclides are significant for understanding the activation behaviour of copper, an essential structural material used in accelerator and nuclear industry.
    Activation cross-sections of deuteron-induced nuclear reactions on natural titanium
    [Abstract]
    M.U. Khandaker, H. Haba, J. Kanaya, N. Otuka, H.A. Kassim, Nuclear Data Sheets 119 (2014) pp. 252-254.
    doi:10.1016/j.nds.2014.08.069
    Abstract
    Activation cross-sections of deuteron-induced nuclear reactions on natural titanium were measured up to 24-MeV energy using a stacked-foil activation technique in combination with HPGe γ-ray spectrometry. Measured cross-sections show an overall good agreement with the earlier measurements, but only a partial agreement with predictions by the TALYS code extracted from the TENDL-2011 library. The new cross-sections of the investigated reaction products find importance in nuclear medicine, accelerator and nuclear technology, and testing of nuclear reaction theories.
    Documentation of uncertainties in experimental cross sections for EXFOR
    [Abstract]
    N. Otuka, D.L. Smith, Nuclear Data Sheets 120 (2014) pp. 281-284.
    doi:10.1016/j.nds.2014.07.067
    Abstract
    Documentation of uncertainties and covariances in experimental nuclear reaction cross sections has been assessed. Following consideration of the importance of covariances for nuclear data in various nuclear applications, and presentation of a simple numerical example to demonstrate this point, the minimum basic concepts (mean, covariance, standard derivation, partial uncertainties, micro- and macro-correlation coefficients) are introduced. A deterministic approach to propagating the covariances in primary measured parameters (e.g., counts) to the derived cross sections is discussed, using a neutron-induced activation cross section measurement as an example. Finally, various approaches to documentation (publication, compilation) of experimental cross sections to facilitate their use in future evaluations are mentioned.
    First Compilation and Evaluation of Beta-Delayed Neutron Emission Probabilities and Associated Half-Lives for A ≤ 72 Nuclei
    [Abstract]
    M. Birch, B. Singh, D. Abriola, I. Dillmann, T.D. Johnson, E.A. McCutchan, and A.A. Sonzogni, Nuclear Data Sheets 120 (2014) 66–69
    doi:10.1016/j.nds.2014.07.008
    Abstract
    A comprehensive compilation and evaluation of beta-delayed neutron ( β− n ) emission probabilities, Pn, and associated half-lives for A ≤ 72 nuclei has been performed for the first time. The recommended values have been used to analyze the systematics of β− n emission in this region. The ratio Pn/T1/2 is better correlated with the Q-value of the β− n decay mode than the previously proposed Kratz-Herrmann Formula (KHF). The recommended values are also compared with theoretical quasi-particle random phase approximation (QRPA) calculations
    A New Approach to Estimating the Probability for β-delayed Neutron Emission
    [Abstract]
    E.A. McCutchan, A.A. Sonzogni, T.D. Johnson, D. Abriola, M. Birch, and B. Singh, Nuclear Data Sheets 120 (2014) 62–65
    doi:10.1016/j.nds.2014.07.007
    Abstract
    The probability for neutron emission following β decay, Pn, is a crucial property for a wide range of physics and applications including nuclear structure, r-process nucleosynthesis, the control of nuclear reactors, and the post-processing of nuclear fuel. Despite much experimental effort, knowledge of Pn values is still lacking in very neutron-rich nuclei, requiring predictions from either systematics or theoretical models. Traditionally, systematic predictions were made by investigating the Pn value as a function of the decay Q value and the neutron separation energy in the daughter nucleus. A new approach to Pn systematics is presented which incorporates the half-life of the decay and the Q value for β-delayed neutron emission. This prescription correlates the known data better, and thus improves the estimation of Pn values for neutron-rich nuclei. Such an approach can be applied to generate input values for r-process network calculations or in the modeling of advanced fuel cycles.
    Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC)
    [Abstract]
    N. Otuka, E. Dupont, V. Semkova, B. Pritychenko, A.I. Blokhin, M. Aikawa, S. Babykina, M. Bossant, G. Chen, S. Dunaeva, R.A. Forrest, T. Fukahori, N. Furutachi, S. Ganesan, Z. Ge, O.O. Gritzay, M. Herman, S. Hlavač, K. Katō, B. Lalremruata, Y.O. Lee, A. Makinaga, K. Matsumoto, M. Mikhaylyukova, G. Pikulina, V.G. Pronyaev, A. Saxena, O. Schwerer, S.P. Simakov, N. Soppera, R. Suzuki, S. Takács, X. Tao, S. Taova, F. Tárkányi, V.V. Varlamov, J. Wang, S.C. Yang, V. Zerkin, Y. Zhuang, Nuclear Data Sheets 120 (2014) pp. 272–276.
    doi:10.1016/j.nds.2014.07.065
    Abstract
    The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by the IAEA Nuclear Data Section (NDS) successfully collaborates in the maintenance and development of the EXFOR library. As the scope of published data expands (e.g. to higher energy, to heavier projectile) to meet the needs of research and applications, it has become a challenging task to maintain both the completeness and accuracy of the EXFOR library. Evolution of the library highlighting recent developments is described.
    Developments of the EXFOR Database: Possible New Formats
    [Abstract]
    R.A. Forrest, V. Zerkin, S. Simakov, Nuclear Data Sheets 120, June 2014 268–271
    doi:10.1016/j.nds.2014.07.064
    Abstract
    The EXFOR database is a collection of experimental nuclear reaction data, maintained by the IAEA on behalf of the International Network of Nuclear Reaction Data Centres (NRDC). The format for the storage of such data was first described in 1969 and while there have been many incremental changes over the years so that the format is now capable of containing a very wide range of measurement results, there is a growing realisation that a major change is required. Consequently the IAEA Nuclear Data Section (NDS) organised a Consultant's Meeting on ‘Further Development of EXFOR’ in 2012. This was an opportunity for a range of international experts to discuss ways of improving EXFOR and while this focused on new formats there was also discussion on ways of storing new data, new output formats and software tools such as editors. This paper will discuss recent and proposed changes to enable new quantities to be stored (such as coincidence measurements and covariances), the range of output formats available (e.g. C4 and X4+) which make interaction with the data more user friendly and the possible use of XML to modernise the database.
    Inventory Simulations Under Neutron Irradiation: Visualization Techniques as an Aid to Materials Design
    [Abstract]
    M.R. Gilbert, L.W. Packer, J.-Ch. Sublet, and R.A. Forrest, Nuclear Science and Engineering 177 (2014) 291–306
    doi:10.13182/NSE13-76
    Abstract
    The simulation of neutron irradiation–induced transmutation using inventory codes is an important part of the research into materials in various nuclear environments, including fusion, fission, medical physics, nuclear security, and astrophysics. These simulations, even in their simplest form, such as the neutron irradiation of a single pure element, generate large time-dependent data sets of complex results. For each nuclide in the inventory, as a function of time, the output data will include the number of atoms and its contribution to a variety of radiological quantities including total or specific activity, gamma dose, heat output, and ingestion and inhalation hazards. A key challenge when performing inventory calculations is thus to represent the full complexity of the results in a visual and understandable format. This paper discusses two different approaches to visualizing inventory data: (a) nuclide maps, which allow the concentrations or activity contributions from all nuclides in the inventory to be displayed and also for the variation to be traced in time under a specific irradiation scenario, and (b) importance diagrams, which are a neutron spectrum–independent representation of the dominant nuclides that contribute to the activity of an irradiated material. Finally, these techniques are applied in parallel to investigate how the activation response of molybdenum can be improved via isotopic tailoring (enrichment or depletion), which could make it a more viable alternative armor material in the design of fusion reactors.
    Investigation of (d,x) nuclear reactions on natural ytterbium up to 24 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, N. Otuka, A.R. Usman, Nucl. Instrum. Meth. Phys. Res. B 335 (2013) pp. 8-18.
    doi:10.1016/j.nimb.2014.05.020
    Abstract
    Production cross-sections of the natYb(d,x)169,170,171,172,173,174m,174,176m,177gLu and 169,175,177Yb reactions have been measured from a 24-MeV deuteron energy down to their respective thresholds by using a stacked-foil activation technique combined with high resolution γ-ray spectrometry. Our new experimental data extended the experimental database toward the lower energy region for 169Yb, 171Lu, 172Lu, and 176mLu, and the higher region for 174Lu, 176mLu, and 177Yb. An overall good agreement is found with some of the earlier measurements, whereas a partial agreement is obtained with the theoretical data extracted from the TENDL-2013 library. The (d,p) channel contribution underestimated by the TENDL-2013 library is successfully reproduced in the global renormalization by Ignatyuk for the FENDL-3.0 library. The production cross-sections of 175Yb available in the literature were revised based on the latest γ-ray intensity adopted in 2004. Physical thick target yields for the investigated reaction products were also deduced and compared with the directly measured ones in the literature. The derived thick target yields for 173Lu and 174gLu are higher than the directly measured ones by Dmitriev et al. at 22 MeV. The deduced yield curves indicate that a low energy (<11 MeV) cyclotron and a highly enriched 176Yb target could be used to obtain 177gLu with negligible impurity from 177mLu.
    Improvements and Extensions of the Neutron Cross Section and Fluence Standards
    [Abstract]
    A.D. Carlson, V.G. Pronyaev, R. Capote, F.-J. Hambsch, F. Kappeler, C. Lederer, W. Mannhart, A. Mengoni, R.O. Nelson, A.J.M. Plompen, P. Schillebeeckx, S. Simakov, P. Talou, S. Tagesen, H. Vonach, A. Vorobyev, and A. Wallner, Nuclear Data Sheets 118 (2014) 126-131
    doi:/10.1016/j.nds.2014.04.017
    Abstract
    Improvements have been made to the nuclear data standards largely as a result of an IAEA Data Development Project. The work includes the traditional activities related to standards, extending the energy ranges of some standards, and reference data that are not as well known as the standards but can be very useful in the measurements of certain types of cross sections. Also included is an effort to improve evaluations of 235U thermal and 252Cf spontaneous fission neutron spectra.
    Validation of the International Reactor Dosimetry and Fusion File
    [Abstract]
    S. Simakov, L. Greenwood, R. Capote Noy, Proc. 12th Int. Conf. on Radiation Shielding (ICRS-12), 2-7 September 2012, Nara, Japan; Progress in Nuclear Science and Technology 4 (2014) pp. 591-595
    Abstract
    Evaluated nuclear data files for nuclides of the thorium-uranium cycle were released as a result of a coordinated research project of the International Atomic Energy Agency. To validate the data a series of benchmark test cases were analysed, with emphasis on the most important nuclides 232Th and 233U. Remaining nuclides appearing in the benchmarks were taken from the ENDF/B-VII beta-2 library, except for a few sensitivity studies where the data were taken from other sources. The results show marked improvement in the agreement with measurements, much of it coming from the new evaluations
    Databases and coordinated research projects at the IAEA on atomic processes in plasmas
    [Abstract]
    B.J. Braams, H.-K. Chung, AIP Conference Proceedings 1438 (2012) pp. 222-227.
    doi:10.1063/1.4707881
    Abstract
    The Atomic and Molecular Data Unit at the IAEA works with a network of national data centres to encourage and coordinate production and dissemination of fundamental data for atomic, molecular and plasma-material interaction (A+M/PMI) processes that are relevant to the realization of fusion energy. The Unit maintains numerical and bibliographical databases and has started a Wiki-style knowledge base. The Unit also contributes to A+M database interface standards and provides a search engine that offers a common interface to multiple numerical A+M/PMI databases. Coordinated Research Projects (CRPs) bring together fusion energy researchers and atomic, molecular and surface physicists for joint work towards the development of new data and new methods. The databases and current CRPs on A+M/PMI processes are briefly described here.
    First Joint IAEA-ITER Technical Meeting on Analysis of ITER Materials and Technologies. Preface
    [Abstract]
    R. Kamendje, B.J. Braams, Fusion Sci. Technol. 61 Issue 2 (2012) pp.III
    Abstract
    The first Joint IAEA-ITER Technical Meeting on Analysis of ITER Materials and Technologies was held November 23–25, 2010, in the Principality of Monaco, in conjunction with the first Monaco ITER International Fusion Energy Days. The meeting aimed to contribute to the development of a knowledge base of properties, processes, and technologies relevant to ITER structural and plasma-facing materials and components, and of the effects of energetic particles and radiation on ITER materials. The present issue of Fusion Science and Technology features papers describing some of the material that was presented and discussed at the meeting.
    Analytical potential energy surface for O + C2H2 system
    [Abstract]
    S. Garashchuk, V.A. Rassolov and B.J. Braams, Chem. Phys. Lett. 588 (2013) pp. 22-26.
    doi:10.1016/j.cplett.2013.09.060
    Abstract
    Full-dimensional analytical potential energy surfaces (PESs) for the O(1P) + C2H2 and O(3P) + C2H2 reactions are presented. The PESs are constructed by fitting thousands of ab initio data points using permutationally invariant polynomials. Electronic structure data are obtained within the restricted coupled cluster theory with single and double excitations with perturbative triple corrections and correlation consistent basis set of triple-zeta with diffuse functions. Motivated by experiments, formation of DOCC and cyclic DCCO at collision energies of 2.5–4 eV is examined using quasi-classical trajectory dynamics on the triplet surface.
    Coordinated Research Projects of the IAEA (CRP). 5. Summary
    [Abstract]
    B.J. Braams, M. Imai and D. Kato, Journal of the Japan Society of Plasma Science and Nuclear Fusion Research 89 Issue No.9 (2013) pp. 615-621.
    Abstract
    A summary is provided of the twelve (12) special topic articles connected to recent CRPs or other activities of the IAEA Atomic and Molecular Data Unit.
    Coordinated Research Projects of the IAEA (CRP). 1. Introduction
    [Abstract]
    B.J. Braams, M. Imai and D. Kato, Journal of the Japan Society of Plasma Science and Nuclear Fusion Research 89 Issue 9 (2013) pp. 579-582.
    Abstract
    The present special topic articles of the Journal of Plasma and Fusion Research contain contributions from (mainly) Japanese researchers in the field of fusion science or related atomic, molecular or plasma-material interaction processes reflecting the interests of one of the recent CRPs or other activities of the IAEA Atomic and Molecular Data Unit.
    The upcoming international code of practice for small static photon field dosimetry
    [Abstract]
    H. Palmans, R. Alfonso, P. Andreo, R. Capote, M.S. Huq, J. Izewska, J. Johansson, W. Kilby, T.R. Mackie, A. Meghzifene, K. Rosser, J. Seuntjens, W. Ullrich, Med. Phys. 39 (2012) 4633.
    doi:10.1118/1.4740154
    Abstract
    The increased use of small photon fields in stereotactic and intensity‐modulated radiotherapy has raised the need for standardizing the dosimetry of such fields using procedures consistent with those for conventional radiotherapy. An international working group, established by the IAEA in collaboration with AAPM and IPEM, is finalising a Code of Practice for the dosimetry of small static photon fields. Procedures for reference dosimetry in nonstandard machine specific reference (msr) fields are provided following the formalism of Alfonso et al. (Med. Phys. 35: 5179; 2008). Reference dosimetry using ionization chambers in machines that cannot establish a conventional 10 cm × 10 cm reference field is based on either a direct calibration in the msr field traceable to primary standards, a calibration in a reference field and a generic correction factor or the product of a correction factor for a virtual reference field and a correction factor for the difference between the msr and virtual fields. For the latter method, procedures are provided for determining the beam quality in non‐reference conditions. For the measurement of field output factors in small fields, procedures for connecting large field measurements using ionization chambers to small field measurements using high‐resolution detectors such as diodes, diamond,liquidion chambers, organic scintillators and radiochromic film are given. The Code of Practice also presents consensus data on correction factors for use in conjunction with measured, detector‐specific output factors. Further research to determine missing data according to the proposed framework will be strongly encouraged by publication of this document.
    Astrophysical (α,γ) reaction in inverse kinematics; Electron screening effect in the beta-decay
    [Abstract]
    P. Ujic, F. de Oliveira Santos, A. Lagoyannis, T.J. Mertzimekis, S. Harissopulos, P. Demetriou, A. Spyrou et al., J. Phys.: Conf. Ser. 337 (2012) 012015.
    doi:10.1088/1742-6596/337/1/012015
    Abstract
    The abundance calculations of the p-nuclei produced in explosive stellar sites rely on the Hauser-Feshbach (HF) theory with the alpha-article optical model potential (α-OMP) one of its major ingredients. To date, most of the (α, γ) cross sections measured show that HF calculations can be wrong by a factor of ten or more especially when phenomenological α- OMP are employed. To investigate the relevant uncertainties entering the HF calculations and furthermore develop global microscopic α-OMPs, systematic (α, γ) cross-section measurements are necessary. This led us to perform a feasibility study of (α, γ) measurements in inverse kinematics that will allow us to employ also radioactive beams in the future. Hence, the 4He(78Kr,γ) 82Sr reaction was studied using the LISE3 spectrometer to separate the 82Sr recoils from the primary 78Kr beam. Although an excellent rejection factor > 1010 was achieved, the position of the ions of interest was unexpectedly masked by a secondary beam of high intensity. Given these, new setup improvements are proposed to remove the pollutant ions
    Experimental and theoretical study of the (n,2n) reaction on 174,176Hf isotopes
    [Abstract]
    M. Serris, S. Galanopoulos, M. Kokkoris, C.T. Papadopoulos, M. Lamprou, R. Vlastou, P. Demetriou, C.A. Kalfas, A. Lagoyannis, Phys. Rev. C 86 (2012) 034602.
    doi:10.1103/PhysRevC.86.034602
    Abstract
    Cross sections for the 174Hf(n, 2n)173Hf and 176Hf(n, 2n)175Hf reactions have been measured at the 5.5 MV VdG Tandem accelerator of NCSR \Demokritos" in Athens, in the neutron energy region from 8.8 to 11.0 MeV, using the activation technique. An experimental method to account for the contamination of the 176Hf(n, 2n) reaction by the 174Hf(n, ) reaction activated by the parasitic neutrons of the beam is presented. Statistical model calculations have also been performed using the nuclear-reaction codes EMPIRE-II and TALYS. The results and the e ect of the nuclear input parameters as well as pre-equilibrium emission are discussed in detail
    Nuclear Data Sheets for A=211
    [Abstract]
    B. Singh, D. Abriola, C. Baglin, P. Demetriou et al., Nuclear Data Sheets 114 (2013) 661-749
    doi:10.1016/j.nds.2013.05.001
    Abstract
    The evaluated spectroscopic data are presented for 11 known nuclides of mass 211 (Hg, Tl, Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th). The 211Pa nuclide is included here but its identification remains uncertain. For 211Hg, 211Tl, 211Ac and 211Th nuclei, only the ground–state information is available. Their decay characteristics are mostly unknown. 211Fr is suggested to decay partially through ε decay mode, but its decay scheme remains poorly known. While high–spin excitations, including several isomers, are well studied in 211Pb, 211Bi, 211Po, 211At, 211Rn and 211Fr, the particle–transfer data are available for only 211Po and 211Bi. This evaluation was carried out as part of joint IAEA–ICTP workshop for Nuclear Structure and Decay Data, organized and hosted by the IAEA, Vienna and ICTP, Trieste, August 6–17, 2012. This work supersedes previous A=211 evaluation (2004Br45) published by E. Browne which covered literature before January 2003.
    Investigation of α-induced reactions on the p nucleus 168Yb
    [Abstract]
    L. Netterdon, P. Demetriou, J. Endres, U. Giesen, G.G. Kiss, A. Sauerwein, T. Szücs, K.O. Zell, A. Zilges, Nucl. Phys. A 916 (2013) 149-167
    doi:10.1016/j.nuclphysa.2013.08.002
    Abstract
    Cross sections for the 168Yb(α,γ)172Hf and 168Yb(α,n)171Hf reactions were measured by means of the activation method using α particles with energies between 12.9 MeV and 15.1 MeV. The spectroscopy of the γ rays emitted by there action products was performed using three different HPGe detector types, namely clover-type high-purity germanium detectors, a low-energy photon spectrometer detector, and a coaxial high-purity germanium detector. The results were compared to Hauser–Feshbach statistical model calculations. Within certain assumptions, astrophysical conclusions could be drawn concerning the production of the p nucleus 168Yb. The data in this work can serve as a contribution to the current very fragmentary experimental database for charged-particle induced reactions. In addition, the absolute intensity for nine γ-ray transitions following the electron capture decay of 171Hf could be derived.
    Cross section measurements of proton capture reactions relevant to the p process: The case of 89Y(p,γ)90Zr and 121,123Sb(p,γ)122,124Te
    [Abstract]
    S. Harissopulos, A. Spyrou, A. Lagoyannis, M. Axiotis, P. Demetriou, J.W. Hammer, R. Kunz, H.-W. Becker, Phys. Rev. C 87 (2013) 025806
    doi:10.1103/PhysRevC.87.025806
    Abstract
    The cross sections of the 89Y(p,γ)90Zr and the 121,123Sb(p,γ)122,124Te reactions were determined from γ-angular distribution measurements at beam energies from 1.6 to 3.4 MeV. In addition, angle-integrated cross sections were also measured at Ep=2, 3, 4, and 4.8 MeV for the 89Y(p,γ)90Zr reaction using the 4π γ-summing method. Astrophysical S factors and reaction rates were deduced from the measured cross sections. Statistical model calculations were performed using the nuclear-reaction code Talys. The results from the comparison between theory and experiment are discussed in detail.
    Nuclear Data Sheets for A = 215
    [Abstract]
    B. Singh, G. Mukherjee, D. Abriola, S. Basu, P. Demetriou et al., Nuclear Data Sheets 114 (2013) 2023-2078
    doi:10.1016/j.nds.2013.11.003
    Abstract
    The evaluated spectroscopic data are presented for 12 known nuclides of mass 215 (Hg, Tl, Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa). For 215Hg, 215Tl, 215Pb, and 215Pa nuclei, no excited states are known. The decay characteristics of 215Hg and 215Tl are unknown. The decay scheme of 215Pb is considered as incomplete. Ordering of γ cascades in the decay of 36.9–s isomer of 215Bi and for high–spin states above 2251 keV in 215Fr are not established. High–spin excitations, including several isomeric states, are well known in 215Bi, 215Po, 215Rn, 215Fr, 215Ra, and 215Ac. No particle–transfer reaction data are available for any of the A=215 nuclei. The rms charge radii for 215Pb, 215Bi, 215Po, 215Rn, 215Fr and 215Ra have been evaluated by Daniel Abriola, from extrapolation or interpolation of available evaluated data in 2013An02 for radii of respective Z chains using formula 9 in 2004An14. This evaluation was carried out as part of ENSDD–workshop at VECC, Kolkata for Nuclear Structure and Decay Data, organized and hosted by VECC and Board of Research in Nuclear Sciences (BRNS) in Kolkata, India, November 26–29, 2012. This work supersedes the previous A=215 evaluation (2001Br31) published by E. Browne which covered literature prior to May 2001.
    Coordinated activities on evaluation of collisional data for fusion applications
    [Abstract]
    H.-K. Chung and B.J. Braams, AIP Conf. Proc. 1545 (2013) 260
    doi:10.1063/1.4815862
    Abstract
    It is the role of the Atomic and Molecular Data Unit of the International Atomic Energy Agency to review progress in the production, compilation and evaluation of atomic, molecular and plasma-surface interaction (AM/PSI) data for the fusion program and to support the development of internationally recommended libraries of AM/PSI data for fusion. In response to increasing requests from the fusion community the Unit has increased its effort to promote the assessment of data quality by organizing a series of meetings on the relevant issues: 1) Error propagation and sensitivity analysis, 2) Current status of evaluated databases, 3) Uncertainty estimates of theoretical data, 4) Experimental data evaluation, 5) Data evaluation methods and semi-empirical fits and 6) Establishment of an evaluators’ network. The discussions and conclusions are summarized here.
    Comparison and analysis of collisional-radiative models at the NLTE-7 workshop
    [Abstract]
    H.-K. Chung, C. Bowen, C.J. Fontes, S.B. Hansen, Yu. Ralchenko, High Energy Dens. Phys. 9, 645 (2013)
    doi:10.1016/j.hedp.2013.06.001
    Abstract
    We present the main results of the 7th Non-Local Thermodynamic Equilibrium Code Comparison Workshop held in December 2011 in Vienna, Austria. More than twenty researchers from nine countries, who actively work on development of collisional-radiative codes for plasma kinetics modeling, attended the meeting and submitted their results for a number of comparison cases. The cases included free-electron-laser-inspired time-dependent relaxation of photoexcited Ne-like Ar, ionization balance and spectra for highly charged tungsten, spectroscopic diagnostics of krypton L-shell spectra, and an investigation of Ne model convergence with principal quantum number.
    Observations of the Effect of Ionization-Potential Depression in Hot Dense Plasma
    [Abstract]
    D.J. Hoarty, P. Allan, S.F. James, C.R.D. Brown, L.M.R. Hobbs, M.P. Hill, J.W.O. Harris, J. Morton, M.G. Brookes, R. Shepherd, J. Dunn, H. Chen, E. Von Marley, P. Beiersdorfer, H.K. Chung, R.W. Lee, G. Brown, and J. Emig, Phys. Rev. Lett. 110, 265003 (2013)
    doi:10.1103/PhysRevLett.110.265003
    Abstract
    The newly commissioned Orion laser system has been used to study dense plasmas created by a combination of short pulse laser heating and compression by laser driven shocks. Thus the plasma density was systematically varied between 1 and 10 g=cc by using aluminum samples buried in plastic foils or diamond sheets. The aluminum was heated to electron temperatures between 500 and 700 eVallowing the plasma conditions to be diagnosed by K-shell emission spectroscopy. The K-shell spectra show the effect of the ionization potential depression as a function of density. The data are compared to simulated spectra which account for the change in the ionization potential by the commonly used Stewart and Pyatt prescription and an alternative due to Ecker and Kro¨ll suggested by recent x-ray free-electron laser experiments. The experimental data are in closer agreement with simulations using the model of Stewart and Pyatt.
    Results of total cross section measurements for 197Au in the neutron energy region from 4 to 108 keV at GELINA
    [Abstract]
    I. Sirakov, B. Becker, R. Capote, E. Dupont, S. Kopecky, C. Massimi and P. Schillebeeckx, Eur. Phys. J. A 49 (2013) 144
    doi:10.1140/epja/i2013-13144-2
    Abstract
    Transmission measurements have been performed to determine the total cross section for neutron-induced reactions with 197Au in the energy region from 4 keV to 108 keV. The experiments were carried out at a 50m measurement station of the time-of-flight facility GELINA using a 6Li glass scintillator. The average total cross section as a function of neutron energy was derived after correcting the observed average transmission for cross section fluctuations due to resonance structures. The results have been compared with literature data and with the total cross section resulting from a dispersive coupled-channel optical model potential. The neutron strength function for s-wave neutrons and an orbital-independent scattering radius, together with their covariance matrix, have been derived in the neutron energy region between 4 keV and 108 keV through a parameterization of the total cross section based on a nuclear reaction theory.
    A dispersive optical model potential for nucleon induced reactions on 238U and 232Th nuclei with full coupling
    [Abstract]
    J.M. Quesada, E.S. Soukhovitski, R. Capote and S. Chiba, EPJ Web of Conferences 42 (2013) 02005
    doi:10.1051/epjconf/20134202005
    Abstract
    A dispersive coupled-channel optical model potential (DCCOMP) that couples the ground-state rotational and low-lying vibrational bands of 238U and 232Th nuclei is studied. The derived DCCOMP couples almost all excited levels below 1 MeV of excitation energy of the corresponding even-even actinides. The ground state, octupole, beta, gamma, and non-axial bands are coupled. The first two isobar analogue states (IAS) populated in the quasi-elastic (p,n) reaction are also coupled in the proton induced calculation, making the potential approximately Lane consistent. The coupled-channel potential is based on a soft-rotor description of the target nucleus structure, where dynamic vibrations are considered as perturbations of the rigid rotor underlying structure. Matrix elements required to use the proposed structure model in Tamura coupled-channel scheme are derived. Calculated ratio R(U238/Th232) of the total cross-section difference to the averaged σT for 238U and 232Th nuclei is shown to be in excellent agreement with measured data.
    Dispersive coupled-channels optical-model potential with soft-rotator couplings for Cr, Fe, and Ni isotopes
    [Abstract]
    Li Rui, Sun Weili, E. Sh. Soukhovitski, J.M. Quesada, R. Capote, Phys. Rev. C 87 (2013) 054611
    doi:10.1103/PhysRevC.87.054611
    Abstract
    An approximate Lane-consistent dispersive coupled-channels optical potential is derived that describes nucleon-induced reactions on even iron isotopes. Realistic saturated couplings for 54,56,58Fe nuclei are built using nuclear wave functions of the soft-rotator model with the Hamiltonian parameters adjusted to reproduce the energy of the low-lying collective levels of these isotopes.E2- andE3-transition probabilities between low-lying collective levels are well reproduced. The comprehensive experimental database used in the fitting process includes all scattering data for neutron and proton scattering up to 200 MeV on iron nuclei. The derived potential is shown to be applicable to Ni and Cr isotopes, assuming the applicability of the soft-rotator model to these nuclei and to the odd 57Fe nucleus within the rigid-rotor model. The approximate Lane consistency of the derived potential is validated by describing the quasielastic (p, n) scattering with excitation of isobaric analog states. Elastic and inelastic analyzing powers for both neutron- and proton-induced reactions are shown to be in good agreement with experimental data, demonstrating the reliability of the derived dispersive spin-orbit potential
    Measurement and modeling of the cross sections for the reaction 230Th(3He,3n)230U
    [Abstract]
    A. Morgenstern, K. Abbas, F. Simonelli, R. Capote, M. Sin, B. Zielinska, F. Bruchertseifer, C. Apostolidis, Phys. Rev. C 87 (2013) 064602
    doi:10.1103/PhysRevC.87.064602
    Abstract
    230U and its daughter nuclide 226Th are promising therapeutic nuclides for application in targeted α therapy of cancer. We investigated the feasibility of producing 230U/226Th via irradiation of 230Th with 3He particles according to the reaction 230Th(3He,3n)230U. The experimental excitation function for this reaction is reported here. Cross sections were measured by using thin targets of 230Th prepared by electrodeposition, and 230U yields were analyzed by using α spectrometry. Beam intensities were obtained via monitor reactions on aluminum foils by using high-resolution γ spectrometry and International Atomic Energy Agency recommended cross sections. Incident particle energies were calculated by using the SRIM-2003 code. The experimental cross sections for the reaction 230Th(3He,3n)230U are in good agreement with model calculations by the EMPIRE-3 code once breakup and transfer reactions are properly considered in the incident channel. The obtained cross sections are too low to allow for the production of 230U/226Th in clinically relevant levels.
    Impact of model defect and experimental uncertainties on evaluated output
    [Abstract]
    D. Neudecker, R. Capote, H. Leeb, Nucl. Instrum. Meth. A 723 (2013) pp. 163-172
    doi:10.1016/j.nima.2013.05.005
    Abstract
    One of the current major problems in nuclear data evaluation is the unreasonably small evaluated uncertainties often obtained. These small uncertainties are partly attributed to missing correlations of experimental uncertainties as well as to deficiencies of the model employed for the prior information. In this article, both uncertainty sources are included in an evaluation of 55Mn cross-sections for incident neutrons. Their impact on the evaluated output is studied using a prior obtained by the Full Bayesian Evaluation Technique and a prior obtained by the nuclear model program EMPIRE. It is shown analytically and by means of an evaluation that unreasonably small evaluated uncertainties can be obtained not only if correlated systematic uncertainties of the experiment are neglected but also if prior uncertainties are smaller or about the same magnitude as the experimental ones. Furthermore, it is shown that including model defect uncertainties in the evaluation of 55Mn leads to larger evaluated uncertainties for channels where the model is deficient. It is concluded that including correlated experimental uncertainties is equally important as model defect uncertainties, if the model calculations deviate significantly from the measurements.
    Measurement of the MACS of 181Ta(n,γ) at kT=30 keV as a test of a method for Maxwellian neutron spectra generation
    [Abstract]
    J. Praena, P.F. Mastinu, M. Pignatari, J.M. Quesada, J. Garcia-Lopez, M. Lozano, N. Dzysiuk, R. Capote, G. Martin-Hernandez, Nucl. Instrum. Meth. A 727 (2013) pp. 1-6
    doi:10.1016/j.nima.2013.05.151
    Abstract
    Measurement of the Maxwellian-Averaged Cross-Section (MACS) of the reaction at kT=30 keV by the activation technique using an innovative method for the generation of Maxwellian neutron spectra is presented. The method is based on the shaping of the proton beam to produce a desired neutron spectrum using the 7Li(p,n) reaction as a neutron source. The characterization of neutron spectra has been performed by combining measured proton distributions, an analytical description of the differential neutron yield in angle and energy of the 7Li(p,n) reaction, and with Monte Carlo simulations of the neutron transport. A measured value equal to 815±73 mbarn is reported for the MACS of the reaction at kT=30 keV. The MACS of the reaction provided by KADoNiS has been used as a reference.
    Activation cross-sections of deuteron-induced nuclear reactions on natural iron up to 24 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, J. Kanaya, N. Otuka, Nucl. Instrum. Meth. B 316 (2013) pp. 33-41.
    doi:10.1016/j.nimb.2013.08.032
    Abstract
    Activation cross-sections of the natFe(d,x)55,56,57,58g+mCo, 52g,54,56Mn, 51Cr, 59Fe reactions were measured from their respective thresholds to 24 MeV via a stacked foil activation technique combined with HPGe γ-ray spectrometry. An overall good agreement is found with some of the earlier measurements, whereas partial agreements are obtained with the theoretical data extracted from the TENDL-2011 library. The present measurement reports four cross-sections of 58g+mCo, 56Mn and 59Fe radionuclides in the energy range of 20–24 MeV for the first time. Physical thick target yields deduced from the measured cross-sections are compared with the directly measured yields available in the literature. The measured 58Fe(d,p)59Fe cross section is underestimated by the original TENDL-2011 library while overestimated by the TENDL-2011 library renormalized by Ignatyuk for the FENDL-3 library.
    Status of the McDeLicious Approach for the D-Li Neutron Source Term Modeling in IFMIF Neutronics Calculations
    [Abstract]
    S.P. Simakov, U. Fischer, K. Kondo, P. Pereslavtsev, Fusion Science & Technology 62 (2012) pp. 233.
    Abstract
    McDeLicious is an extension to the MCNP Monte Carlo code with the ability to simulate the generation of source neutrons based on D-Li interaction processes. This paper presents an overview of the McDeLicious approach for the D-Li neutron source term modeling including latest code extensions, improvements, validation efforts, and applications to IFMIF neutronics analyses. The current McDeLicious capabilities include the generation of source neutrons and photons based on evaluated d+6,7Li cross-section data and the sampling of the impinging deuteron beam intensity distribution using fitting functions or probability tables. The McDeLicious software has been updated to comply with the standard of the state-of-the-art version 5 of the MCNP code. A message passing interface program version enables one to run McDeLicious in parallel mode on large computer clusters. McDeLicious is in routine use for IFMIF neutronics calculations employing different nuclear data including a test version of the recent FENDL-3 nuclear data.
    Spectroscopic studies of hard x-ray free-electron laser-heated foils at 1016 Wcm-2
    [Abstract]
    J. Dunn, R. Shepherd, A. Graf, A. Steel, J. Park, S.J. Moon, R.W. Lee, P. Audebert, A. Levy, M. Gauthier, J. Fuchs, D.M. Fritz, M. Cammarata, D. Milathianaki, H.J. Lee, B. Nagler, C. Fourment, F. Deneuville, G. Williams, M. Fajardo, J. Gaudin, S. Vinko, O. Ciricosta, J. Wark, H.K. Chung, Proc. SPIE 8140, X-Ray Lasers and Coherent X-Ray Sources: Development and Applications IX, 81400O (October 05, 2011)
    doi:10.1117/12.895264
    Abstract
    We report a recent experiment where the first hard x-ray beam line, X-ray Pump Probe (XPP) instrument using the SLAC National Accelerator Laboratory's Linac Coherent Light Source (LCLS) free electron laser, was used to heat thin foils to high energy densities ~ 107 J/cm3. An intense 9 keV, 60 fs (FWHM) duration beam with energy of 2 - 4 mJ at the XPP beam line was focused using beryllium lenses to an irradiance approaching 1016 Wcm-2. Targets of 0.5 - 3.5 μm thick foils of Ag and Cu were studied using a suite of diagnostics including Fourier Domain Interferometry, energy calorimetry and grating and crystal spectrometers. The experimental details and spectroscopic results from the campaign will be described. Preliminary results indicate that the target is heated relatively uniformly to a temperature lower than 20 eV.
    IAEA coordinated activities on evaluation of atomic, molecular and plasma-surface interaction data for fusion applications
    [Abstract]
    H.-K. Chung and B. J. Braams, Fusion Sci. Tech. 63 413 (2013)
    Abstract
    The Atomic and Molecular Data Unit of the International Atomic Energy Agency collaborates with an international network of data centres and fusion laboratories to support the production, compilation and evaluation of atomic, molecular and plasma-surface interaction (AM/PSI) data relevant to fusion energy research. In recent years, there have been increasing requests from the fusion community for the development of internationally recommended libraries of AM/PSI data for fusion and the Unit has increased its effort to promote the assessment of data quality by organizing a series of meetings on the relevant issues. Meeting participants from the AM/PSI data community developed plans for increased collaboration on the evaluation and recommendation of AM/PSI data. The discussions, conclusions and future plans are summarized here.
    Method of time resolved refractive index measurements of x-ray laser heated solids
    [Abstract]
    G.O. Williams, H.-K. Chung, S.M. Vinko, S. Kunzel, A.B. Sardinha, Ph. Zeitoun and M. Fajardo, Phys. of Plasmas 20, 042701 (2013)
    doi:10.1063/1.4794964
    Abstract
    With the advent of new x-ray light-sources worldwide, the creation of dense, uniformly heated plasma states arising from intense x-ray irradiation of solids has been made possible. In the early stages of x-ray solid heating, before significant hydrodynamic motion occurs, the matter exists in a highly non-equilibrium state. A method based on wavefront sensing is proposed to probe some of the fundamental properties of these states. The deflection and absorption of a high harmonic probe beam propagated through the plasma can be measured with a wavefront sensor, and allow for the determination of the complex refractive index (RI) of the plasma, giving a 2D map of the optical properties as function of time in a pump-probe arrangement. A solid heating model has been used to estimate the expected temperatures of x-ray heated thin foils, and these temperatures are used in three separate models to estimate the changes in the refractive index. The calculations show the changes induced on an extreme ultra-violet (XUV) probe beam by a solid density thin foil plasma are significant, in terms of deflection angle and absorption, to be measured by already existing XUV Hartmann wavefront sensors. The method is applicable to a wide range of photon energies in the XUV (10 s to several 100 s of eV) and plasma parameters, and can add much needed experimental data to the fundamental properties of such dense plasma states.
    Combination of resonance integral and Maxwellian 30 keV data – A sensitive test of the resonance region
    [Abstract]
    J. Kopecky, R.A. Forrest, Fusion Engineering and Design 88 (2013) pp. 177-187.
    doi:10.1016/j.fusengdes.2013.01.095
    Abstract
    This paper presents the approach of a combined use of resonance integrals and average Maxwellian cross sections (MACS) at kT = 30 keV to test and validate the resolved resonance range or its reconstructed cross section curve. Based on these two integral measurements a sensitive and energy dependent test can be provided. These two integral quantities cover with their neutron spectra the energy region between En = 0.5 eV up to several hundred keV, respectively, with different weighting. Our principal motivation is to produce a validation tool, sensitive to the lower and upper parts of the resonance region through the difference in the applied 1/E and kT = 30 keV Maxwell–Boltzmann spectra of the resonance integral and MACS data.
    The 93Zr(n,γ) reaction up to 8 keV neutron energy
    [Abstract]
    G. Tagliente, R. Capote, et al., (n_TOF Collaboration), Physical Review C 87 (2013) 014622
    doi:10.1103/PhysRevC.87.014622
    Abstract
    The (n, γ ) reaction of the radioactive isotope 93Zr has been measured at the n_TOF high-resolution time-offlight facility at CERN. Resonance parameters have been extracted in the neutron energy range up to 8 keV, yielding capture widths smaller (14%) than reported in an earlier experiment. These results are important for detailed nucleosynthesis calculations and for refined studies of waste transmutation concepts.
    Experimental Uncertainty and Covariance Information in EXFOR Library
    [Abstract]
    N. Otuka, R. Capote, S. Kopecky, A.J.M. Plompen, V.G. Pronyaev, P. Schillebeeckx and D.L. Smith, EPJ Web of Conferences 27 (2012) 00007.
    doi:10.1051/epjconf/20122700007
    Abstract
    Compilation of experimental uncertainty and covariance information in the EXFOR Library is discussed. Following the presentation of a brief history of information provided in the EXFOR Library, the current EXFOR Formats and their limitations are reviewed. Proposed extensions for neutron-induced reaction cross sections in the fast neutron region and resonance region are also presented.
    Thermal Neutron Capture onto the Stable Tungsten Isotopes
    [Abstract]
    A.M. Hurst, R.B. Firestone, B.W. Sleaford, N.C. Summers, Zs. Revay, L. Szentmiklósi, T. Belgya, M.S. Basunia, R. Capote, et al., EPJ Web of Conferences 21 (2012) 10005
    doi:10.1051/epjconf/20122110005
    Abstract
    Thermal neutron-capture measurements of the stable tungsten isotopes have been carried out using the guided thermal-neutron beam at the Budapest Reactor. Prompt singles spectra were collected and analyzed using the HYPERMET γ-ray analysis software package for the compound tungsten systems 183W, 184W, and 187W, prepared from isotopically-enriched samples of 182W, 183W, and 186W, respectively. These new data provide both confirmation and new insights into the decay schemes and structure of the tungsten isotopes reported in the Evaluated Gamma-ray Activation File based upon previous elemental analysis. The experimental data have also been compared to Monte Carlo simulations of γ-ray emission following the thermal neutron-capture process using the statistical-decay code DICEBOX. Together, the experimental cross sections and modeled feeding contribution from the quasi continuum, have been used to determine the total radiative thermal neutron-capture cross sections for the tungsten isotopes and provide improved decay-scheme information for the structural- and neutron-data libraries.
    An implementation to read and write IAEA phase-space files in GEANT4-based simulations
    [Abstract]
    M.A. Cortés-Giraldo, J.M. Quesada, M.I. Gallardo, R. Capote, International Journal of Radiation Biology 88 (1-2) (2012) pp. 200-208
    doi:10.3109/09553002.2011.627977
    Abstract
    Purpose: To develop a stand-alone code to make any application coded with the GEANT4 (GEometry ANd Tracking, version 4) toolkit capable of reading and writing phase-space (phsp) files in the format created by the IAEA (International Atomic Energy Agency), so that the exchange of phsp files between other validated Monte Carlo (MC) codes and GEANT4 is possible. Methods: We present a stand-alone code, written in C++ object-oriented language, developed in a way that ensures the compatibility with future versions of the IAEA phsp format. The aim of the reader part is to get the information from a given IAEA phsp file and create the primary particles in a GEANT4 user application. On the other hand, the writer part of the code is the responsible for writing the IAEA phsp files during a run of the GEANT4 application. Results: A testing simulation was written with GEANT4 to verify the performance of this code, with satisfactory results. An example of use in a GEANT4 application which simulates the treatment head of a radiotherapy linear electron accelerator (linac) is also shown, comparing dose calculations with experimental data. Conclusions: This stand-alone package, which can be used in any GEANT4 application, allows the exchange of validated phsp files between different MC codes and the use of phsp data from many different accelerators and fields in dosimetry studies. Furthermore, it also offers additional utilities of interest in medical applications.
    Neutron-induced fission cross section of 245Cm: New results from data taken at the time-of-flight facility n_TOF
    [Abstract]
    M. Calviani, R. Capote, et al., (n_TOF collaboration), Physical Review C 85 (2012) 034616
    doi:10.1103/PhysRevC.85.034616
    Abstract
    The neutron-induced fission cross section of 245Cm was measured at n TOF in a wide energy range and with high resolution. The energy dependence, measured in a single measurement from 30 meV to 1 MeV neutron energy, has been determined with 5% accuracy relative to the 235U(n,f) cross section. In order to reduce the uncertainty on the absolute value, the data have been normalized at thermal energy to recent measurements performed at ILL and BR1. In the energy range of overlap, the results are in fair agreement with some previous measurements and confirm, on average, the evaluated cross section in the ENDF/B-VII.0 database, although sizable differences are observed for some important resonances below 20 eV. A similar behavior is observed relative to JENDL/AC-2008, a reactor-oriented database for actinides. The new results contribute to the overall improvement of the databases needed for the design of advanced reactor systems and may lead to refinements of fission models for the actinides.
    Measurement and resonance analysis of the 237Np neutron capture cross section
    [Abstract]
    C. Guerrero, R. Capote, et al., (n_TOF collaboration), Physical Review C 85 (4) (2012) 044616
    doi:10.1103/PhysRevC.85.044616
    Abstract
    The neutron capture cross section of 237Np was measured between 0.7 and 500 eV at the CERN n_TOF facility using the 4π BaF2 Total Absorption Calorimeter. The experimental capture yield was extracted minimizing all the systematic uncertainties and was analyzed together with the most reliable transmission data available using the SAMMY code. The result is a complete set of individual as well as average resonance parameters [D0 = 0.56(2) eV, γ = 40.9(18) meV, 104S0 = 0.98(6), R = 9.8(6) fm]. The capture cross section obtained in this work is in overall agreement with the evaluations and the data of Weston and Todd [Nucl. Sci. Eng. 79, 184 (1981)], thus showing sizable differences with respect to previous data from Scherbakov et al. [J. Nucl. Sci. Technol. 42, 135 (2005)] and large discrepancies with data Kobayashi et al. [J. Nucl. Sci. Technol. 39, 111 (2002)]. The results indicate that a new evaluation combining the present capture data with reliable transmission data would allow reaching an accuracy better than 4%, in line with the uncertainty requirements of the nuclear data community for the design and operation of current and future nuclear devices
    Resonance neutron-capture cross sections of stable magnesium isotopes and their astrophysical implications
    [Abstract]
    C. Massimi, R. Capote, et al., (n_TOF collaboration), Physical Review C 85 (4) (2012) 044615
    doi:10.1103/PhysRevC.85.044615
    Abstract
    We have measured the neutron capture cross sections of the stable magnesium isotopes 24,25,26Mg in the energy range of interest to the s process using the neutron time-of-flight facility n_TOF at CERN. Capture events from a natural metal sample and from samples enriched in 25Mg and 26Mg were recorded using the total energy method based on C6 2H6 detectors. Neutron resonance parameters were extracted by a simultaneous resonance shape analysis of the present capture data and existing transmission data on a natural isotopic sample. Maxwellian-averaged capture cross sections for the three isotopes were calculated up to thermal energies of 100 keV and their impact on s-process analyses was investigated. At 30 keV the new values of the stellar cross section for 24Mg, 25Mg, and 26Mg are 3.8±0.2 mb, 4.1±0.6 mb, and 0.14±0.01 mb, respectively.
    Measurement of resolved resonances of 232Th(n,γ) at the n-TOF facility at CERN
    [Abstract]
    F. Gunsing, R. Capote, et al., (n_TOF collaboration), Physical Review C 85 (6) (2012) 064601.
    doi:10.1103/PhysRevC.85.064601
    Abstract
    The yield of the neutron capture reaction 232Th(n, γ ) has been measured at the neutron time-of-flight facility n_TOF at CERN in the energy range from 1 eV to 1 MeV. The reduction of the acquired data to the capture yield for resolved resonances from 1 eV to 4 keV is described and compared to a recent evaluated data set. The resonance parameters were used to assign an orbital momentum to each resonance. A missing level estimator was used to extract the s-wave level spacing of D0 = 17.2 ± 0.9 eV.
    Status of the LEgnaro NeutrOn Source facility (LENOS)
    [Abstract]
    Pierfrancesco Mastinu, J. Praena, G. Martín-Hernández, N. Dzysiuk, G. Prete, R. Capote, M. Pignatari, A. Ventura, Physics Procedia 26 (2012) 261 – 273
    doi:10.1016/j.phpro.2012.03.034
    Abstract
    LENOS is a new facility under development at Laboratori Nazionali di Legnaro (LNL). It is based on a new technic for neutron beam shaping in accelerator based neutron sources. The main advantage of this method is to be able to shape the primary charged-particle beam to a defined energy distribution that, impinging on a neutron producing target, generates the desired neutron spectra at the sample position. Together with the proton energy distribution, other degrees of freedom are used to obtain the desired neutron energy spectra, e.g. the angular distribution of produced neutrons, the nuclear reactions used for the neutron spectra production, and the convolution of neutron spectra coming from different target materials. The main advantage of this new approach is the good control over the energy and spatial distribution of the produced neutron spectrum avoiding most of the problems due to neutron moderation, since it is easier to work with charged particles than with neutrons. The goal of the LENOS facility is to obtain a Maxwell-Boltzmann neutron energy spectrum with tunable temperature and a high neutron flux at sample position by using the 7Li(p,n) reaction. To maximize the neutron flux a very narrow primary proton beam has to be used, so the target has to remove a very high specific power. Currently available lithium targets are inadequate to sustain the high specific power that needs to be dissipated in the LENOS facility. A dedicated target based on micro-channel geometry and liquid metal cooling has been developed and tested. This contribution describes the status of the LENOS facility.
    Temperature-tuned Maxwell-Boltzmann neutron spectra for kT ranging from 30 up to 50keV for nuclear astrophysics studies
    [Abstract]
    G. Martín-Hernández, P.F. Mastinu, J. Praena, N. Dzysiuk, R. Capote, M. Pignatari, Applied Radiation and Isotopes 70 (8) (2012), pp. 1583-1589
    doi:10.1016/j.apradiso.2012.05.004
    Abstract
    The need of neutron capture cross section measurements for astrophysics motivates present work, where calculations to generate stellar neutron spectra at different temperatures are performed. The accelerator-based 7Li(p,n)7Be reaction is used. Shaping the proton beam energy and the sample covering a specific solid angle, neutron activation fo rmeasuring stellar-averaged capture cross section can be done. High-quality Maxwell–Boltzmann neutron spectra are predicted. Assuming a general behavior of the neutron capture cross section a weighted fit of the spectrum to Maxwell–Boltzmann distributions is successfully introduced.
    Neutron-induced fission cross section measurement of 233U, 241Am and 243Am in the energy range 0.5MeV < En < 20MeV at n-TOF at CERN
    [Abstract]
    F. Belloni, R. Capote, et al., (n_TOF collaboration), Physica Scripta, (2012) 014005
    doi:10.1088/0031-8949/2012/T150/014005
    Abstract
    Neutron-induced fission cross section measurements of 233U, 243Am and 241Am relative to 235U have been carried out at the neutron time-of-flight facility n_TOF at CERN. A fast ionization chamber has been employed. All samples were located in the same detector; therefore the studied elements and the reference 235U target are subject to the same neutron beam.
    Estimation of neutron-equivalent dose in organs of patients undergoing radiotherapy by the use of a novel online digital detector
    [Abstract]
    F. Sánchez-Doblado, C ,Domingo, F. Gómez, B. Sánchez-Nieto, J.L. Muñiz, M.J. García-Fusté, M.R. Expósito, R. Barquero, F. Fernández, F., Physics in Medicine and Biology 57 (19) (2012) pp. 6167
    doi:10.1088/0031-9155/57/19/6167
    Abstract
    Neutron peripheral contamination in patients undergoing high-energy photon radiotherapy is considered as a risk factor for secondary cancer induction. Organ-specific neutron-equivalent dose estimation is therefore essential for a reasonable assessment of these associated risks. This work aimed to develop a method to estimate neutron-equivalent doses in multiple organs of radiotherapy patients. The method involved the convolution, at 16 reference points in an anthropomorphic phantom, of the normalized Monte Carlo neutron fluence energy spectra with the kerma and energy-dependent radiationweighting factor. This was then scaled with the total neutron fluence measured with passive detectors, at the same reference points, in order to obtain the equivalent doses in organs. The latter were correlated with the readings of a neutron digital detector located inside the treatment room during phantom irradiation. This digital detector, designed and developed by our group, integrates the thermal neutron fluence. The correlation model, applied to the digital detector readings during patient irradiation, enables the online estimation of neutron-equivalent doses in organs. The model takes into account the specific irradiation site, the field parameters (energy, field size, angle incidence, etc) and the installation (linac and bunker geometry). This method, which is suitable for routine clinical use, will help to systematically generate the dosimetric data essential for the improvement of current risk-estimation models.
    Updating and extending the IRDF-2002 dosimetry library
    [Abstract]
    R. Capote, K.I. Zolotarev, V.G. Pronyaev, A. Trkov, ASTM Special Technical Publication 1550 STP (2012) pp.197-202
    doi:10.1520/STP155020120015
    Abstract
    The International Reactor Dosimetry File (IRDF)-2002 released in 2004 by the IAEA (see http://www-nds.iaea.org/irdf2002/) contains cross-section data and corresponding uncertainties for 66 dosimetry reactions. New cross-section evaluations have become available recently that re-define some of these dosimetry reactions including: (1) high-fidelity evaluation work undertaken by one of the authors (KIZ); (2) evaluations from the US ENDF/B-VII.0 and candidate evaluations from the US ENDF/B-VII.1 libraries that cover reactions within the International Evaluation of Neutron Cross-Section Standards; (3) European JEFF3.1 library; and (4) Japanese JENDL-4.0 library. Additional high-threshold reactions not included in IRDF-2002 (e.g.,59Co(n,3n) and 209Bi(n,3n)) have been also evaluated to characterize higher-energy neutron fields. Overall, 37 new evaluations of dosimetry reactions have been assessed and intercomparisons made with integral measurements in reference neutron fields to determine whether they should be adopted to update and improve IRDF-2002. Benchmark calculations performed for newly evaluated reactions using the ENDF/B-VII.0 235U thermal fission and 252Cf spontaneous fission neutron spectra show that calculated integral cross sections exhibit improved agreement with evaluated experimental data when compared with the equivalent data from the IRDF-2002 library. Data inconsistencies or deficiencies of new evaluations have been identified for 63Cu(n,2n), 60Ni(n,p)60m+gCo, 55Mn(n,γ), and 232Th(n,f) reactions. Compared with IRDF-2002, the upper neutron energy boundary was formally increased from the actual maximum energy of typically 20 MeV up to 60 MeV by using the TENDL-2010 cross sections and covariance matrices. This extension would allow the updated IRDF library to be also used in fusion dosimetry applications. Uncertainties in the cross sections for all new evaluations are given in the form of relative covariance matrices. Newly evaluated excitation functions should be considered as suitable candidates in the preparation of an improved version of the IRDF that was planned to be released for testing in December 2011.
    New work on updating and extending the nuclear data standards
    [Abstract]
    A.D. Carlson, V.G. Pronyaev, R. Capote, F.-J. Hambsch, F. Käppeler, C. Lederer, W. Mannhart, A. Mengoni, A. Wallner, ASTM Special Technical Publication 1550 STP (2012) pp. 141-160.
    doi:10.1520/STP155020120012
    Abstract
    An International Atomic Energy Agency (IAEA) Data Development Project was initiated to provide a mechanism for allowing new experimental data and improvements in evaluation procedures to be incorporated into new evaluations of the standards. The work on this project is ongoing. In the past very long periods sometimes occurred between evaluations of the standards. Through the use of this Project, such long periods should not occur. Work on the cross section standards through this Project has included an update of the experimental data to be used in the cross section standards evaluations, a study of the uncertainties obtained in the international standards evaluation, and improvements in the smoothing procedure for capture cross sections. It was decided that this Project should have a broader range of activities than just the cross section standards and thus encompass standards related activities. The following are being investigated: improvements in the gold cross section at energies below where it is considered a standard and work on certain cross sections that are not as well known as the cross section standards but could be very useful as reference cross sections relative to which certain types of cross section measurements can be made. This work includes prompt gamma-ray production in fast neutron-induced reactions, and work on the 252Cf spontaneous fission neutron spectrum and the 235U thermal neutron fission spectrum. Most of the data investigated through this Project are used in dosimetry applications.
    A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction 55Mn(n,γ)56Mn
    [Abstract]
    R. Capote, D.L. Smith, A. Trkov, M. Meghzifene, 2012 ASTM Special Technical Publication 1550 STP (2012) pp. 179-196.
    doi:10.1520/STP155020120014
    Abstract
    Two relatively new approaches to neutron cross section data evaluation are described. They are known collectively as Unified Monte Carlo (versions UMC-G and UMC-B). Comparisons are made between these two methods, as well as with the well-known generalized least-squares (GLSQ) technique, through the use of simple, hypothetical (toy) examples. These new Monte Carlo methods are based on stochastic sampling of probability functions that are constructed with the use of theoretical and experimental data by applying the principle of maximum entropy. No further assumptions are involved in either UMC-G or UMC-B. However, the GLSQ procedure requires the linearization of non-linear terms, such as those that occur when cross section ratio data are included in an evaluation. It is shown that these two stochastic techniques yield results that agree well with each other, and with the GLSQ method, when linear data are involved, or when the perturbations due to data discrepancies and nonlinearity effects are small. Otherwise, there can be noticeable differences. The present investigation also demonstrates, as observed in earlier work, that the least-squares approach breaks down when these conditions are not satisfied. This paper also presents an actual evaluation of the 55Mn(n,γ)56Mn neutron dosimetry reaction cross section in the energy range from 100 keV to 20 MeV, which was performed using both GLSQ and UMC-G approaches.
    Validating the ENDF-B/VII 235U(nth,f) Prompt Fission Neutron Spectrum Using Updated Dosimetry Cross Sections (IRDFF)
    [Abstract]
    R. Capote, K.I. Zolotarev, V.G. Pronyaev, A. Trkov, International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics 3 (2012) pp. 2690.
    Abstract
    The International Reactor Dosimetry File IRDF-2002 released in 2004 by the IAEA contains cross-section data and corresponding uncertainties for 66 dosimetry reactions. New cross-section evaluations have become available recently that re-define some of these dosimetry reactions for reactor applications including: 1) high fidelity evaluation work undertaken by one of the authors (KIZ); 2) evaluations from the ENDF/B-VII libraries that cover reactions within the International Evaluation of Neutron Cross-Section Standards; and 3) evaluations from JENDL-3.1 and JENDL- 4 libraries. Overall, 37 new evaluations of dosimetry reactions have been assessed to determine whether they should be adopted to update and improve IRDF-2002. A new dosimetry library (International Reactor Dosimetry File for Fission and Fusion - IRDFF) was assembled based on new evaluations combined with selected IRDF-2002 evaluations. A grand-total of 74 dosimetry reactions are included into the IRDFF dosimetry library available at www-nds.iaea.org/IRDFF1 . The assembled library was used to validate the 235U(nth,f) ENDF-B/VII.0 prompt fission neutron spectrum. An excellent average C/E value of 1.002 +/- 0.02 is achieved for reactions with mean neutron energy of the integrated response (E50%) lower than 11 MeV. C/E data for reactions with E50%-response higher than 11 MeV decreases up to 0.8. We conclude that the ENDF-B/VII.0 235U(nth,f) prompt fission neutron spectrum from 1-11 MeV is validated within quoted uncertainties by available integral measurements in 235U(nth,f) neutron field. Further investigations for high-threshold reactions are needed and new measurements of spectrum average cross sections for those reactions in the 235U(nth,f) neutron field are recommended
    48Ti(n,n′γ) gamma production cross section as a candidate for a reference cross section
    [Abstract]
    S.P. Simakov, V.G. Pronyaev, R. Capote, R.O. Nelson, Proc. of 13th Int. Conf. on Nuclear Reaction Mechanisms, Varenna, 11-15 June 2012, CERN-Proceedings-2012-002 (2012) pp. 321-330.
    Abstract
    The yield of 984 keV γ-rays from 48Ti(n,n') reaction has been evaluated from threshold up to 20 MeV. For this purpose all currently availale measured discrete gamma production and neutron inelastic cross sections were thoroughly analysed and renormalised to the updated standards when possible. The TALYS and EMPIRE nuclear reaction codes were used to get an optimal description of these cross sections for natural Titanium and its main isotope 48ti. The fial evaluation of the 984 keV γ-ray yield from 48Ti(n,n') reaction adn covariance matrix was perfromed o nthe basis of collected experimental data and optimised model calculations employing the least squares code GMA.
    The effects of ionization potential depression on the spectra emitted by hot dense aluminium plasmas
    [Abstract]
    T.R. Preston, S.M. Vinko, O. Ciricosta, H.-K. Chung, R.W. Lee and J.S. Wark, High Energy Dens. Phys. 9, 258 (2012)
    doi:10.1016/j.hedp.2012.12.014
    Abstract
    Recent experiments at the Linac Coherent Light Source (LCLS) X-ray Free-Electron-Laser (FEL) have demonstrated that the standard model used for simulating ionization potential depression (IPD) in a plasma (the Stewart–Pyatt (SP) model, J.C. Stewart and K.D. Pyatt Jr., Astrophysical Journal 144 (1966) 1203) considerably underestimates the degree of IPD in a solid density aluminium plasma at temperatures up to 200 eV. In contrast, good agreement with the experimental data was found by use of a modified Ecker–Kröll (mEK) model (G. Ecker and W. Kröll, Physics of Fluids 6 (1963) 62–69). We present here detailed simulations, using the FLYCHK code, of the predicted spectra from hot dense, hydrogenic and helium-like aluminium plasmas ranging in densities from 0.1 to 4 times solid density, and at temperatures up to 1000 eV. Importantly, we find that the greater IPDs predicted by the mEK model result in the loss of the n = 3 states for the hydrogenic ions for all densities above ≈0.8 times solid density, and for the helium-like ions above ≈0.65 solid density. Therefore, we posit that if the mEK model holds at these higher temperatures, the temperature of solid density highly-charged aluminium plasmas cannot be determined by using spectral features associated with the n = 3 principal quantum number, and propose a re-evaluation of previous experimental data where high densities have been inferred from the spectra, and the SP model has been used.
    Resonant Ka Spectroscopy of Solid-Density Aluminum Plasmas
    [Abstract]
    B.I. Cho, K. Engelhorn, S.M. Vinko, H.-K. Chung et al. Phys. Rev. Lett 109 245003 (2012)
    doi:10.1103/PhysRevLett.109.245003
    Abstract
    The x-ray intensities made available by x-ray free electron lasers (FEL) open up new x-ray matter interaction channels not accessible with previous sources. We report here on the resonant generation of Kα emission, that is to say the production of copious Kα radiation by tuning the x-ray FEL pulse to photon energies below that of the K edge of a solid aluminum sample. The sequential absorption of multiple photons in the same atom during the 80 fs pulse, with photons creating L-shell holes and then one resonantly exciting a K-shell electron into one of these holes, opens up a channel for the Kα production, as well as the absorption of further photons. We demonstrate rich spectra of such channels, and investigate the emission produced by tuning the FEL energy to the K-L transitions of those highly charged ions that have transition energies below the K edge of the cold material. The spectra are sensitive to x-ray intensity dependent opacity effects, with ions containing L-shell holes readily reabsorbing the Kα radiation.
    Excitation functions of (d,x) nuclear reactions on natural titanium up to 24 MeV
    [Abstract]
    M.U. Khandaker, H. Haba, J. Kanaya, N. Otuka, Nucl. Instrum. Meth. Phys. Res. B 296 (2013) pp. 14-21.
    doi:10.1016/j.nimb.2012.12.003
    Abstract
    Excitation functions of the natTi(d,x)48V and natTi(d,x)43,44m,44g,46,47,48Sc nuclear reactions were measured up to a 24-MeV deuteron energy by using a stacked-foil activation technique combined with γ-ray spectrometry with a high-purity germanium detector at the AVF cyclotron of the RIKEN RI Beam Factory, Wako, Japan. An overall good agreement is found between the measured cross-sections and the literature ones, whereas partial agreements are obtained for the theoretical calculations based on the TALYS code. Physical thick target yields, i.e., induced radioactivities per unit fluence of the 24-MeV deuteron were also deduced, and they were compared with the directly measured ones in the literature. The present results will have an important role in enrichment of the literature database of the deuteron-induced reactions on natural titanium leading to various applications.
    High-sensitivity isobar-free AMS measurements and reference materials for 55Fe, 68Ge and 202gPb
    [Abstract]
    A. Wallner, M. Bichler, K. Buczak, D. Fink, O. Forstner, R. Golser, M.A.C. Hotchkis, A. Klix, A. Krasa, W. Kutschera, C. Lederer, A. Plompen, A. Priller, D. Schumann, V. Semkova, P. Steier, J. Nucl. Instr. Meth. Phys. Res. B294 (2013) pp. 374-381.
    doi:10.1016/j.nimb.2012.03.029
    Abstract
    Isobaric interference represents one of the major limitations in mass spectrometry. For a few cases in AMS with tandem accelerators, isobaric interference is completely excluded like the well-known major isotopes 14C, 26Al, 129I. Additional isotopes are 55Fe, 68Ge, and 202Pb, with 68Ge and 202Pb never been used in AMS so far. Their respective stable isobars 55Mn, 68Zn and 202Hg do not form stable negative ions. The exceptional sensitivity of AMS for 55Fe, 68Ge and 202gPb offers important insights into such different fields like nuclear astrophysics, fundamental nuclear physics and technological applications. VERA, a dedicated AMS facility is well suited for developing procedures for new and non-standard isotopes. AMS measurements at the VERA facility established low backgrounds for these radionuclides in natural samples. Limits for isotope ratios of <10-15, <10-16 and <2x10-14 were measured for 55Fe/56Fe, 68Ge/70Ge and 202Pb/Pb, respectively. In order to generate accurate isotope ratios of sample materials, AMS relies on the parallel measurement of reference materials with well-known ratios. A new and highly accurate reference material for 55Fe measurements with an uncertainty of ±1.6% was produced from a certified reference solution. In case of 68Ge dedicated neutron activations produced a sufficiently large number of 68Ge atoms that allowed quantifying them through the activity of its decay product 68Ga. Finally, for 202Pb, the short-lived isobar 202Tl was produced via neutron activation and served as a proxy for 202Pb AMS measurements.
    Nuclear data from AMS & nuclear data for AMS - some examples
    [Abstract]
    A. Wallner, M. Bichler, T. Belgya, K. Buczak, I. Dillmann, O. Forstner, R. Golser, F. Käppeler, A. Klix, G. Korschinek, A. Krasa, W. Kutschera, C. Lederer, A. Mengoni, M. Paul, A. Plompen, A. Priller1, V. Semkova, P. Steier, EPJ Web of Conferences 35, 01003 (2012)
    doi:10.1051/epjconf/20123501003
    Abstract
    We summarize some recent cross-section measurements using accelerator mass spectrometry (AMS). AMS represents an ultra-sensitive technique for measuring a limited, but steadily increasing number of longer-lived radionuclides. This method implies a two-step procedure with sample activation and subsequent AMS measurement. Applications include nuclear astrophysics, nuclear technology (nuclear fusion, nuclear fission and advanced reactor concepts and radiation dose estimations). A series of additional applications involves cosmogenic radionuclides in environmental, geological and extraterrestrial studies. There is a lack of information for a list of nuclides, as pointed out by nuclear data requests. An overview of some recent measurements is given and the method is illustrated for some specific neutron-induced reactions.
    Experimental nuclear reaction data uncertainties: Basic concepts and documentation
    [Abstract]
    D.L. Smith, N. Otuka, Nucl. Data Sheets 113 (2012) pp. 3006-3053.
    doi:10.1016/j.nds.2012.11.004
    Abstract
    This paper has been written to provide experimental nuclear data researchers and data compilers with practical guidance on dealing with experimental nuclear reaction data uncertainties. It outlines some of the properties of random variables as well as principles of data uncertainty estimation, and illustrates them by means of simple examples which are relevant to the field of nuclear data. Emphasis is placed on the importance of generating mathematical models (or algorithms) that can adequately represent individual experiments for the purpose of estimating uncertainties in their results. Several types of uncertainties typically encountered in nuclear data experiments are discussed. The requirements and procedures for reporting information on measurement uncertainties for neutron reaction data, so that they will be useful in practical applications, are addressed. Consideration is given to the challenges and opportunities offered by reports, conference proceedings, journal articles, and computer libraries as vehicles for reporting and documenting numerical experimental data. Finally, contemporary formats used to compile reported experimental covariance data in the widely used library EXFOR are discussed, and several samples of EXFOR files are presented to demonstrate their use.
    Determination of resonance parameters and their covariances from neutron induced reaction cross section data
    [Abstract]
    P. Schillebeeckx, B. Becker, Y. Danon, K. Guber, H. Harada, J. Heyse, A.R. Junghans, S. Kopecky, C. Massimi, M.C. Moxon, N. Otuka, I. Sirakov, K. Volev, Nucl. Data Sheets 113 (2012) pp. 3054-3100.
    doi:10.1016/j.nds.2012.11.005
    Abstract
    Cross section data in the resolved and unresolved resonance region are represented by nuclear reaction formalisms using parameters which are determined by fitting them to experimental data. Therefore, the quality of evaluated cross sections in the resonance region strongly depends on the experimental data used in the adjustment process and an assessment of the experimental covariance data is of primary importance in determining the accuracy of evaluated cross section data. In this contribution, uncertainty components of experimental observables resulting from total and reaction cross section experiments are quantified by identifying the metrological parameters involved in the measurement, data reduction and analysis process. In addition, different methods that can be applied to propagate the covariance of the experimental observables (i.e. transmission and reaction yields) to the covariance of the resonance parameters are discussed and compared. The methods being discussed are: conventional uncertainty propagation, Monte Carlo sampling and marginalization. It is demonstrated that the final covariance matrix of the resonance parameters not only strongly depends on the type of experimental observables used in the adjustment process, the experimental conditions and the characteristics of the resonance structure, but also on the method that is used to propagate the covariances. Finally, a special data reduction concept and format is presented, which offers the possibility to store the full covariance information of experimental data in the EXFOR library and provides the information required to perform a full covariance evaluation.
    Data reduction and uncertainty propagation of time-of-flight spectra with AGS
    [Abstract]
    B. Becker, C. Bastian, F. Emiliani, F. Gunsing, J. Heyse, K. Kauwenberghs, S. Kopecky, C. Lampoudis, C. Massimi, N. Otuka, P. Schillebeeckx, I. Sirakov, J. Instrum. 7 (2012) P11002.
    doi:10.1088/1748-0221/7/11/P11002
    Abstract
    Results of neutron time-of-flight measurements are commonly used to parameterize neutron induced reaction cross sections in the resonance region based on the R-matrix reaction theory. Reaction yields or transmission as well as their covariance information are derived starting from measured counting spectra. They are then used in a least squares adjustment for obtaining model parameters. In this paper, a compact formalism is presented to propagate both the correlated and uncorrelated uncertainty components. Full information on the origin of each correlated component of the covariance matrix is maintained. This is particularly important in order to avoid a bias on the model parameters through a phenomenon known as Peelle’s Pertinent Puzzle (PPP). This compact formalism was implemented into the data reduction code AGS (Analysis of Geel Spectra).
    Direct Measurements of the Ionization Potential Depression in a Dense Plasma
    [Abstract]
    O. Ciricosta, S.M. Vinko, H.-K. Chung et al. Phys. Rev. Lett 109 (2012) pp.065002
    doi:10.1103/PhysRevLett.109.065002
    Abstract
    We have used the Linac Coherent Light Source to generate solid-density aluminum plasmas at temperatures of up to 180 eV. By varying the photon energy of the x rays that both create and probe the plasma, and observing the K- fluorescence, we can directly measure the position of the K edge of the highly charged ions within the system. The results are found to disagree with the predictions of the extensively used Stewart-Pyatt model, but are consistent with the earlier model of Ecker and Kroll, which predicts significantly greater depression of the ionization potential.
    Creation and diagnosis of a solid-density plasma with an X-ray free-electron laser
    [Abstract]
    S.M. Vinko, O. Ciricosta, B.I. Cho, K. Engelhorn, H.-K. Chung, C.R.D. Brown, T. Burian, J. Chalupský, R.W. Falcone, C. Graves, V. Hájková, A. Higginbotham, L. Juha, J. Krzywinski, H.J. Lee, M. Messerschmidt, C.D. Murphy, Y. Ping, A. Scherz, W. Schlotter, S. Toleikis, J.J. Turner, L. Vysin, T. Wang, B. Wu et al. Nature 482 (2012) pp.59-62
    doi:10.1038/nature10746
    Abstract
    Matter with a high energy density (>105 joules per cm3) is prevalent throughout the Universe, being present in all types of stars and towards the centre of the giant planets; it is also relevant for inertial confinement fusion. Its thermodynamic and transport properties are challenging to measure, requiring the creation of sufficiently long-lived samples at homogeneous temperatures and densities. With the advent of the Linac Coherent Light Source (LCLS) X-ray laser, high-intensity radiation (>1017 watts per cm2, previously the domain of optical lasers) can be produced at X-ray wavelengths. The interaction of single atoms with such intense X-rays has recently been investigated8. An understanding of the contrasting case of intense X-ray interaction with dense systems is important from a fundamental viewpoint and for applications. Here we report the experimental creation of a solid-density plasma at temperatures in excess of 106 kelvin on inertial-confinement timescales using an X-ray free-electron laser. We discuss the pertinent physics of the intense X-ray–matter interactions, and illustrate the importance of electron–ion collisions. Detailed simulations of the interaction process conducted with a radiative-collisional code show good qualitative agreement with the experimental results. We obtain insights into the evolution of the charge state distribution of the system, the electron density and temperature, and the timescales of collisional processes. Our results should inform future high-intensity X-ray experiments involving dense samples, such as X-ray diffractive imaging of biological systems, material science investigations, and the study of matter in extreme conditions.
    Benchmark of Spallation Models
    [Abstract]
    J.-C.David, D.Filges, F.Gallmeier, M.Khandaker, A,Konobeyev, S. Leray, G.Mank, A.Mengoni, R.Michel, N.Otuka, Y.Yariv, Prog.Nucl.Sci.Technol. 2 (2011) pp. 942-947.
    Abstract
    Spallation reactions play an important role in many branches of physics. If the nuclear reaction induced by low energy neutrons as in nuclear power plants or research reactors can be based on cross section database, it is not the case for spallation reactions due to the energy range, from 100 MeV up to ~3 GeV, and to the candidate targets (all nuclei). Then these reactions have to be modeled. Developments of codes are linked to new experiment and this explains why fifteen years ago a first benchmark has been launched, restricted to particle production, followed by a second one on residues. Since then new data have been measured and computer tools are improved day after day, so a new benchmark has been organized, under the auspices of the IAEA, taken into account all types of results, particle and residue production, with a possibility to update the data (experimental and code calculation) via a web site. Results of the benchmark concerning both the analysis of the prediction capabilities of the seventeen model-participants and the first conclusions on the physics of spallation models are presented.
    Systematic study of (n,p) reaction cross sections from the reaction threshold to 20 MeV
    [Abstract]
    B. Lalremruata, N. Otuka, G.J. Tambave, V.K. Mulik, B.J. Patil, S.D. Dhole, A. Saxena, S. Ganesan, V.N. Bhoraskar, Phys. Rev. C 85 (2011) 024624.
    doi:10.1103/PhysRevC.85.024624
    Abstract
    The cross sections of natCr(n,x)52V, 52Cr(n,p)52V, natCr(n,x)53V, 53Cr(n,p)53V, natZn(n,x)66Cu, 66Zn(n,p)66Cu, natZn(n,x)68Cum, 68Zn(n,p)68Cum, natMo(n,x)97Nbg, 97Mo(n,p)97Nbg, natMo(n,x)97Nbm, 97Mo(n,p)97Nbm, natSn(n,x)116Inm1+m2, 116Sn(n,p)116Inm1+m2, natSn(n,x)117Ing, 117Sn(n,p)117Ing, natSn(n,x)118Inm1+m2,118Sn(n,p)118Inm1+m2, natSn(n,x)120 Inx , 120Sn(n,p)120Inx , natBa(n,x)138Cs, and 138Ba(n,p)138Cs reactions have been measured at 14.8 MeV neutron energy. In the present work, the contributions of (n,np), (n,pn), and (n,d) reactions from heavier isotopes are subtracted. The cross sections were also estimated with the TALYS-1.2 nuclear model code using different level density models, at neutron energies varying from the reaction threshold to 20 MeV. The variations in the (n,p) cross sections with the neutron number in the isotopes of an element are also discussed in brief.
    Experimental Nuclear Reaction Data Library (EXFOR) – Compilation and Dissemination of Nuclear Reaction Data Provided by Nuclear Reaction Data Centres Network
    [Abstract]
    V. Semkova, N. Otuka, S.P. Simakov, V. Zerkin, Presented at 8th Int. Conf. “Nuclear and Radiation Physics”, 20-23 September 2011, Almaty, Kazakhstan pp. 191-194 ISBN 9965-675-78-3.
    Abstract
    The International Network of Nuclear Reaction Data Centres (NRDC) constitutes a worldwide cooperation of nuclear data centres under the auspices of the International Atomic Energy Agency. The main activity of the NRDC Network is collection and compilation of experimental nuclear reaction data and the related bibliographic information in the EXFOR and CINDA databases as well as dissemination of nuclear reaction data and associated documentation to users. The present status of the EXFOR database will be presented together with the latest development for data access and retreaval.
    Experimental Nuclear Reaction Data Collection EXFOR
    [Abstract]
    V. Semkova, N. Otuka, S.P. Simakov, V. Zerkin, 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA 2011), June 6-9, 2011, Ghent, Belgium, IEEE Conference Proceedings CFP1124I-CDR.
    doi:10.1109/ANIMMA.2011.6172861
    Abstract
    The International Network of Nuclear Reaction Data Centres (NRDC) constitutes a worldwide cooperation of 14 nuclear data centres. The main activity of the NRDC Network is collection and compilation of experimental nuclear reaction cross section data and the related bibliographic information in the EXFOR and CINDA databases as well as dissemination of nuclear reaction data and associated documentation to users. The database contains information and numerical data from more than about 19000 experiments consisting of more than 140000 datasets. EXFOR is kept up to date by constantly adding newly published experimental information. Tools developed for data dissemination utilise modern database technologies with fast online capabilities over the Internet. Users are provided with sophisticated search options, a user-friendly retrieval interface for downloading data in different formats, and additional output options such as improved data plotting capabilities. The present status of the EXFOR database will be presented together with the latest development for data access and retrieval.
    Proton elastic scattering differential cross-sections for 12C
    [Abstract]
    D. Abriola, A.F. Gurbich, M. Kokkoris, A. Lagoyannis, V. Paneta, J. Nucl. Instrum. Methods in Phys. Res. B269 (2011) pp. 2011-2016.
    doi:10.1016/j.nimb.2011.06.002
    Abstract
    Carbon depth profiling presents a strong analytical challenge for all the major ion beam analysis (IBA) techniques, with elastic backscattering spectroscopy (EBS) being widely implemented. In the past, the 12C(p,p)12C reaction has been successfully evaluated for proton beam energies up to 4.5 MeV. Currently, an attempt is being made to extend this evaluation to higher energies, namely up to Ep,lab = 7 MeV. There is a certain lack of available and/or coherent datasets in literature for these relatively high proton beam energies at backward angles, suitable for IBA. Moreover, the few existing datasets are in certain cases discrepant. Thus, in the present work, the differential cross-section of proton elastic scattering on carbon were measured between 140°and 170°, in steps of 10°, for the proton beam energy range between 2.7 and 7 MeV. The experimental results obtained, along with data from literature, were evaluated applying nuclear physics models. The evaluated results were benchmarked using a thick, mirror polished glassy carbon target at different beam energies and detector angles.
    Compilation, evaluation, and dissemination of covariances, in microscopic nuclear reaction data,
    [Abstract]
    N. Otuka, R. Capote, V. Zerkin, Transact. American Nucl. Soc. 104 (2011) pp. 774-775.
    Abstract
    Accurate uncertainty and covariance in microscopic nuclear reaction data (e.g., resonance parameters, cross sections) are needed for safe and economic design of new reactors. Evaluators of nuclear data libraries are trying to collect, evaluate, and distribute uncertainty and covariance information to satisfy those needs. To support these tasks, the IAEA Nuclear Data Section (NDS) is actively developing the experimental data library, appropriate evaluation methods and dissemination tools that will be reviewed in this paper.
    Assessment of Actinide Decay Data Evaluations: Findings of an IAEA Coordinated Research Project
    [Abstract]
    M.A. Kellett, presented at 18th Int. Conf. on Radionuclide Metrology and its Applications (ICRM 2011), 19-23 September 2011, Tsukuba, Japan; Appl. Radiat. Isot. 70, Issue 9 (September 2012), pp.1919-1923.
    doi:10.1016/j.apradiso.2012.02.036
    Abstract
    Organised under the auspices of the International Atomic Energy Agency, comprehensive decay scheme evaluations for over eighty actinides and their decay products have been completed on the basis of detailed assessments of the available experimental data. However, despite the application of sound evaluation procedures, such work cannot replace the need to perform and access good quality measurements for adoption. This evaluation programme provided a means of quantifying the quality of the underlying data to ensure that well-focused recommendations could be made for future experimental decay-data studies.
    ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
    [Abstract]
    M.B. Chadwick, R. Capote, et. al., Nucl. Data Sheets 112 (2011) 2887-2996.
    doi:10.1016/j.nds.2011.11.002
    Abstract
    The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. The principal advances in the new library are: (1) An increase in the breadth of neutron reaction cross section coverage, extending from 393 nuclides to 423 nuclides; (2) Covariance uncertainty data for 190 of the most important nuclides, as documented in companion papers in this edition; (3) R-matrix analyses of neutron reactions on light nuclei, including isotopes of He, Li, and Be; (4) Resonance parameter analyses at lower energies and statistical high energy reactions for isotopes of Cl, K, Ti, V, Mn, Cr, Ni, Zr and W; (5) Modifications to thermal neutron reactions on fission products (isotopes of Mo, Tc, Rh, Ag, Cs, Nd, Sm, Eu) and neutron absorber materials (Cd, Gd); (6) Improved minor actinide evaluations for isotopes of U, Np, Pu, and Am (we are not making changes to the major actinides 235,238U and 239Pu at this point, except for delayed neutron data and covariances, and instead we intend to update them after a further period of research in experiment and theory), and our adoption of JENDL-4.0 evaluations for isotopes of Cm, Bk, Cf, Es, Fm, and some other minor actinides; (7) Fission energy release evaluations; (8) Fission product yield advances for fission-spectrum neutrons and 14 MeV neutrons incident on 239Pu; and (9) A new decay data sublibrary. Integral validation testing of the ENDF/B-VII.1 library is provided for a variety of quantities: For nuclear criticality, the VII.1 library maintains the generally-good performance seen for VII.0 for a wide range of MCNP simulations of criticality benchmarks, with improved performance coming from new structural material evaluations, especially for Ti, Mn, Cr, Zr and W. For Be we see some improvements although the fast assembly data appear to be mutually inconsistent. Actinide cross section updates are also assessed through comparisons of fission and capture reaction rate measurements in critical assemblies and fast reactors, and improvements are evident. Maxwellian-averaged capture cross sections at 30 keV are also provided for astrophysics applications. We describe the cross section evaluations that have been updated for ENDF/B-VII.1 and the measured data and calculations that motivated the changes, and therefore this paper augments the ENDF/B-VII.0 publication [M. B. Chadwick, P. Obložinský, M. Herman, N. M. Greene, R. D. McKnight, D. L. Smith, P. G. Young, R. E. MacFarlane, G. M. Hale, S. C. Frankle, A. C. Kahler, T. Kawano, R. C. Little, D. G. Madland, P. Moller, R. D. Mosteller, P. R. Page, P. Talou, H. Trellue, M. C. White, W. B. Wilson, R. Arcilla, C. L. Dunford, S. F. Mughabghab, B. Pritychenko, D. Rochman, A. A. Sonzogni, C. R. Lubitz, T. H. Trumbull, J. P. Weinman, D. A. Br, D. E. Cullen, D. P. Heinrichs, D. P. McNabb, H. Derrien, M. E. Dunn, N. M. Larson, L. C. Leal, A. D. Carlson, R. C. Block, J. B. Briggs, E. T. Cheng, H. C. Huria, M. L. Zerkle, K. S. Kozier, A. Courcelle, V. Pronyaev, and S. C. van der Marck, “ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nuclear Data Sheets 107, 2931 (2006)].
    The Nuclear Science References (NSR) database and Web Retrieval System
    [Abstract]
    B. Pritychenko, E. Běták, M.A. Kellett, B. Singh, J. Totans, J. Nucl. Instrum. Methods in Phys. Res., A640 (2011) pp. 213-218.
    doi:10.1016/j.nima.2011.03.018
    Abstract
    The Nuclear Science References (NSR) database together with its associated Web interface is the world’s only comprehensive source of easily accessible low- and intermediate-energy nuclear physics bibliographic information for more than 200,000 articles since the beginning of nuclear science. The weekly updated NSR database provides essential support for nuclear data evaluation, compilation and research activities. The principles of the database and Web application development and maintenance are described. Examples of nuclear structure, reaction and decay applications are specifically included. The complete NSR database is freely available at the websites of the National Nuclear Data Center http://www.nndc.bnl.gov/nsr and the International Atomic Energy Agency http://www-nds.iaea.org/nsr.
    Covariances of Evaluated Nuclear Cross Section Data for 232Th, 180,182,183,184,186W and 55Mn
    [Abstract]
    A. Trkov, R. Capote, E.Sh. Soukhovitskii, L.C. Leal, M. Sin, I. Kodeli, D.W. Muir, Nuclear Data Sheets 112 (2011) 3098-3119.
    doi:10.1016/j.nds.2011.11.007
    Abstract
    The EMPIRE code system is a versatile package for nuclear model calculations that is often used for nuclear data evaluation. Its capabilities include random sampling of model parameters, which can be utilised to generate a full covariance matrix of all scattering cross sections, including crossreaction correlations. The EMPIRE system was used to prepare the prior covariance matrices of reaction cross sections of 232Th, 180,182,183,184,186W and 55Mn nuclei for incident neutron energies up to 60 MeV. The obtained modelling prior was fed to the GANDR system, which is a package for a global assessment of nuclear data, based on the Generalised Least-Squares method. By introducing experimental data from the EXFOR database into GANDR, the constrained covariance matrices and cross section adjustment functions were obtained. Applying the correction functions on the cross sections and formatting the covariance matrices, the final evaluations in ENDF-6 format including covariances were derived. In the resonance energy range, separate analyses were performed to determine the resonance parameters with their respective covariances. The data files thus obtained were then subjected to detailed testing and validation. Described evaluations with covariances of 232Th, 180,182,183,184,186W and 55Mn nuclei are included into the ENDF/B-VII.1 library release.
    Nuclear Data Activities at the IAEA Nuclear Data Section
    [Abstract]
    S.P. Simakov, Procs. 20th Int. Conf. Nuclear Energy for New Europe 2011, 305.1-305.8.
    Abstract
    The Nuclear Data Section of IAEA assembles, develops and disseminates nuclear data for basic science and practical applications. This paper gives an overview of the NDS activities aimed at the development and maintenance of general purpose databases, such as collection of experimental and evaluated reaction cross sections data, as well as those for the specific energy and material applications, namely for ion material beam analyses, neutron dosimetry, fission and fusion neutronics. The latest upgrades, developments and existing weaknesses are highlighted.
    Measurement of the 236U(n,f) cross section from 170 meV to 2 MeV at the CERN n_TOF facility
    [Abstract]
    R. Sarmento, R. Capote, et al., (the n_TOF Collaboration) Phys. Rev. C84 (2011) 044618.
    doi:10.1103/PhysRevC.84.044618
    Abstract
    The neutron-induced fission cross section of 236U was measured at the neutron Time-of-Flight (n_TOF) facility at CERN relative to the standard 235U(n,f) cross section for neutron energies ranging from above thermal to several MeV. The measurement, covering the full range simultaneously, was performed with a fast ionization chamber, taking advantage of the high resolution of the n_TOF spectrometer. The n_TOF results confirm that the first resonance at 5.45 eV is largely overestimated in some nuclear data libraries. The resonance triplet around 1.2 keV was measured with high resolution and resonance parameters were determined with good accuracy. Resonances at high energy have also been observed and characterized and different values for the cross section are provided for the region between 10 keV and the fission threshold. The present work indicates various shortcomings of the current nuclear data libraries in the subthreshold region and provides the basis for an accurate re-evaluation of the 236U(n,f) cross section, which is of great relevance for the development of emerging or innovative nuclear reactor technologies.
    96Zr(n,γ) measurement at the n_TOF facility at CERN
    [Abstract]
    G. Tagliente, R. Capote, et al., (the n_TOF Collaboration) Phys. Rev. C84 (2011) 055802.
    doi:10.1103/PhysRevC.84.055802
    Abstract
    The (n,γ) cross section of 96Zr has been investigated at the CERN n_TOF spallation neutron source. High resolution time-of-flight measurements using an enriched ZrO2 sample allowed us to analyze 15 resonances below 40 keV with improved accuracy. On average, the capture widths were found to be 25% smaller than reported in earlier experiments. If complemented with the contribution by direct radiative capture, the derived Maxwellian averaged cross sections are consistent with activation data at kT = 25 keV. The present results confirm the astrophysical implications for the s-process branching at sup>95Zr.
    Comparative study of the dust particle population sampled during four consecutive campaigns in full-tungsten ASDEX Upgrade
    [Abstract]
    N. Endstrasser, V. Rohde, M. Balden, P. Humrickhouse, U. von Toussaint, B.J Braams, H. K. Chung, R. Neu and the ASDEX Upgrade team, Phys. Scr. T145 (2011) 014021.
    doi:10.1088/0031-8949/2011/T145/014021
    Abstract
    Scanning electron microscopy images and energy-dispersive x-ray spectra were recorded for a total of about 4×104 dust particles collected on the same position within the vacuum vessel via silicon wafers during four consecutive full-tungsten first wall campaigns of ASDEX Upgrade between 2007 and 2009. By careful analysis of the elemental composition and shape of the sampled particles, seven statistically relevant classes of dust were identified. The particle flux and area coverage of each class were normalized to the total plasma duration of each sampling period, revealing a high sensitivity of the dust composition to device conditioning. According to the present results, particles produced by arcing on divertor tiles with delaminated coatings were transported to the main chamber first wall.
    Coordinated Research Projects of the IAEA Atomic and Molecular Data Unit
    [Abstract]
    B.J. Braams, H.-K. Chung, 7th Int. Conf. on Atomic and Molecular data and their applications - ICAMDATA-2010, Vilnius, Lithuania, 21–24 September 2010, AIP Conf. Proc. 1344 (2011) pp. 171-178.
    doi:10.1063/1.3585816
    Abstract
    The IAEA Atomic and Molecular Data Unit is dedicated to the provision of databases for atomic, molecular and plasma‐material interaction (AM∕PMI) data that are relevant for nuclear fusion research. IAEA Coordinated Research Projects (CRPs) are the principal mechanism by which the Unit encourages data evaluation and the production of new data. Ongoing and planned CRPs on AM∕PMI data are briefly described here.
    The Dynamics of Allyl Radical Dissociation
    [Abstract]
    Chao Chen, B. Braams, D.Y. Lee, J.M. Bowman, P.L. Houston, D. Stranges, J. Phys. Chem. A115 (2011) pp. 6797–6804.
    doi:10.1021/jp109344g
    Abstract
    Dissociation of the allyl radical, CH2CHCH2, and its deuterated isotopolog, CH2CDCH2, have been investigated using trajectory calculations on an ab initio ground-state potential energy surface calculated for 97 418 geometries at the coupled cluster single and double and perturbative treatment of triple excitations, with the augmented correlation consistent triple-ζ basis set level (CCSD(T)/AVTZ). At an excitation energy of 115 kcal/mol, corresponding to optical excitation at 248 nm, the primary channel is hydrogen loss with a quantum yield of 0.94 to give either allene or propyne in a ratio of 6.4:1. The total dissociation rate for CH2CHCH2 is 6.3 × 1010 s−1, corresponding to a 1/e time of 16 ps. Methyl and C2H2 are produced with a quantum yield of 0.06 by three different mechanisms: a 1,3 hydrogen shift followed by C−C cleavage to give methyl and acetylene, a double 1,2 shift followed by C−C cleavage to give methyl and acetylene, or a single 1,2 hydrogen shift followed by C−C cleavage to give methyl and vinylidene. In this last channel, the vinylidene eventually isomerizes to give internally excited acetylene, and the kinetic energy distribution is peaked at much lower energy (6.4 kcal/mol) than that for the other two channels (18 kcal/mol). The trajectory results also predict the v−J correlation, the anisotropy of dissociation, and distributions for the angular momentum of the fragments. The v−J correlation for the CH3 + HCCH channel is strongest for high rotational levels of acetylene, where v is perpendicular to J. Methyl elimination is anisotropic, with β = 0.66, whereas hydrogen elimination is nearly isotropic. In the hydrogen elimination channel, allene is rotationally excited with a total angular momentum distribution peaked near J = 17. In the methyl elimination channel, the peak of the methyl rotational distribution is at J ≈ 12, whereas the peak of the acetylene rotational distribution is at J ≈ 28.
    Flexible, ab initio potential, and dipole moment surfaces for water. I. Tests and applications for clusters up to the 22-mer
    [Abstract]
    Yimin Wang, Xinchuan Huang, B.C. Shepler, B.J. Braams and J.M. Bowman, J. Chem. Phys. 134 (2011) 094509.
    doi:10.1063/1.3554905
    Abstract
    We report full-dimensional, ab initio potential energy and dipole moment surfaces, denoted PES and DMS, respectively, for arbitrary numbers of water monomers. The PES is a sum of 1-, 2-, and 3-body potentials which can also be augmented by semiempirical long-range higher-body interactions. The 1-body potential is a spectroscopically accurate monomer potential, and the 2- and 3-body potentials are permutationally invariant fits to tens of thousands of CCSD(T)/aug-cc-pVTZ and MP2/aug-cc-pVTZ electronic energies, respectively. The DMS is a sum of 1- and 2-body DMS, which are covariant fits to tens of thousands MP2/aug-cc-pVTZ dipole moment data. We present the details of these new 2- and 3-body potentials and then extensive applications and tests of this PES are made to the structures, classical binding energies, and harmonic frequencies of water clusters up to the 22-mer. In addition, we report the dipole moment for these clusters at various minima and compare the results against available and new ab initio calculations.
    Nuclear Analytical Applications within the IAEA Nuclear Data Section
    [Abstract]
    M.A. Kellett, Procs. 11th Int. Conf. "Applications of Nuclear Techniques", Crete, (Greece), 12–18 June 2011, AIP Conf. Procs. 1412 (2011) pp. 430-437.
    doi:10.1063/1.3665345
    Abstract
    The Nuclear Data Section, International Atomic Energy Agency, supports Member States development of nuclear techniques through a number of targeted actions and projects. The Section fulfills this role by organizing Coordinated Research Projects, or through less formal Data Development Projects and/or Technical Meetings. Training workshops are also regularly organized in conjunction with the International Centre for Theoretical Physics (ICTP), Trieste, Italy. A number of projects relating to materials analysis techniques have been recently undertaken, e.g. neutron activation analysis, ion beam analysis, and proton induced X- or γ-ray emission. In particular, details of the Coordinated Research Project focusing on the nuclear data requirements for the k0 method of neutron activation analysis are given. The paper illustrates how the IAEA strives to bring together relevant partners and provides a unique and structured basis for international collaboration.
    Investigations of 89Y(p,x)86,88,89gZr, 86m+g,87g,87m,88gY, 85gSr, and 84gRb nuclear processes up to 42 MeV
    [Abstract]
    M.U. Khandaker, K. Kim, M.-W. Lee, K-S. Kim, G. Kim, N. Otuka, Nucl. Instr. Meth. Phys. Res. B 271 (2012) pp. 72-81.
    doi:10.1016/j.nimb.2011.11.009
    Abstract
    Production cross-sections of the 89Y(p,x)86,88,89gZr, 86m+g,87g,87m,88gY, 85gSr, and 84gRb nuclear processes were investigated up to 42-MeV proton energy by using a stacked-foil activation technique at the MC- 50 cyclotron of the Korea Institute of Radiological and Medical Sciences. Cumulative cross-sections of the 88gY radionuclide have been reported here for the first time from proton activation on natural yttrium target. The present data were compared with the available experimental data as well as theoretical calculations based on the TALYS and the ALICE-IPPE codes, and found in general good agreement among them. Due to the mono-isotopic characteristics of the natural yttrium, the investigated 89Y(p,x)86,88,89gZr, 86m+g,87g,87m,88gY, 85gSr, and 84gRb processes are suitable for testing of nuclear reaction theories and/or mechanism. A quantitative analysis has also done to understand more accurately the predictive power of the model codes by performing calculations of deviation factors between the measured data and respective model calculations. The thick target integral yields, i.e., induced radioactivity per unit fluence of 42-MeV protons were also deduced from the measured cross-sections of the investigated radionuclides. Optimal production pathway for the 89Zr-PET radionuclide using a cyclotron is discussed elaborately. The measured cross-sections of 87gY, 88gY, 88Zr, and 89gZr radionuclides find importance due to their suitable decay characteristics leading to medical and thin layer activation applications. In addition, the present experimental results will play an important role in enrichment of the literature data base for proton-induced reactions on natural yttrium leading to various applications.
    Development of a genetic algorithm for the search of optical model parameters
    [Abstract]
    D. Abriola, Nucl. Instr. Meth. Phys. Res. B269 (2011) pp. 2984-2989.
    doi:10.1016/j.nimb.2011.04.054
    Abstract
    The analysis of elastic scattering cross sections in terms of the Optical Model is subject to a series of well known ambiguities. Diverse assumptions about the initial values or shape of the potentials frequently produce different parameters, leading to different physical interpretations of the observed data. It would be important to have a starting set of ‘‘user independent’’ optical potentials that fit the experimental data to allow the evaluator to consider a large array of possibilities before committing to a particular optical potential. This work presents a Genetic Algorithm (GA) code that simulates natural selection and evolution, allowing a ‘‘blind search’’ of the multiparametric χ2 surface. In this GA, the genes subject to evolution are the parameters of the optical potential. The GA variables, operators and procedures are described, and the GA is applied to two cases in which the elastic scattering cross section is adjusted: one for the 7Li + 27Al system at energies close to the Coulomb barrier where the interaction occurs near the nuclear surface, and another for the 16O + 16O system where the two nuclei deeply interpenetrate each other. Further developments are described.
    Development of a reference database for Ion Beam Analysis and future perspectives
    [Abstract]
    D. Abriola, N.P. Barradas, I. Bogdanović-Radović, M. Chiari, A.F. Gurbich, C. Jeynes, M. Kokkoris, M. Mayer, A.R. Ramos, L. Shi, I. Vickridge, Nucl. Instr. Meth. Phys. Res. B269 (2011) pp. 2972-2978.
    doi:10.1016/j.nimb.2011.04.056
    Abstract
    Ion Beam Analysis (IBA) is a set of material characterization techniques using energetic ion beams. IBA provides information about composition and the depth profile of elements in the near-surface layers of a sample, from the energy spectra of backscattered primary particles, recoils, nuclear reaction products or emitted c-radiation. All IBA methods presuppose knowledge of the differential cross-section data however, only for strict Rutherford scattering is the cross-section known exactly. In order to address the data needs of the IBA community, the IAEA initiated the Coordinated Research Project (CRP) ‘‘Development of a Reference Database for Ion Beam Analysis’’ in 2005 which will conclude in 2010. The project focuses on the measurement, assessment, evaluation and benchmarking of elastic scattering and reaction cross sections. Data measured in this work have been incorporated in the IBANDL database (http://wwwnds. iaea.org/ibandl/), whereas the evaluated cross-sections (calculated from the fit to the data of a nuclear model) are made available to the community through the on-line calculator SigmaCalc (http:// www-nds.iaea.org/sigmacalc/). A summary of the results of the CRP activity is presented, and ways to further develop nuclear data for IBA are indicated. In particular, a newly proposed CRP devoted to particle induced gamma-ray emission is described.
    Time-resolved plasma temperature measurements in a laser-triggered hydrogen-filled capillary discharge waveguide
    [Abstract]
    C.J. Woolley, K. O’Keeffe, H.-K Chung, S.M. Hooker, Plasma Sources Sci. Technol. 20 (2011) 055014.
    doi:10.1088/0963-0252/20/5/055014
    Abstract
    Temporally resolved, spatially integrated measurements of the temperature of the plasma channel formed by a hydrogen-filled discharge capillary waveguide are presented. Plasma temperatures of 4–7 eV are measured for peak discharge currents between 80 and 150 A. It is demonstrated that laser-triggering the capillary discharge enables capillary discharges with a peak current as low as 23 A to be driven, reducing the plasma temperature to approximately 3 eV. This plasma temperature meets the requirements of a recently proposed soft x-ray recombination laser.
    Simulations of neon irradiated by intense X-ray laser radiation
    [Abstract]
    O. Ciricosta, H.-K. Chung, R.W. Lee, J.S. Wark, High Energy Density Physics 7 (2011) pp.111 116.
    doi:10.1016/j.hedp.2011.02.003
    Abstract
    We present simulations of the charge states produced by the interaction of intense X-ray laser radiation with a neon gas. We model the results of a recent experiment (Young et al., Nature 466, 56 (2010)), where mJ pulses of X-rays, with photon energies ranging from 800 to 2000 eV and pulse lengths ranging from 70 to 340 fs were incident on neon atoms at intensities of up to 1018 W cm2. Simulations using an adapted version of the SCFLY collisional-radiative code, which included the effect of electron collisions and a simple self-consistent temperature model, result in charge state distributions that are in good agreement with the experimental data. We calculate the electron temperature of the system during the evolution of the plasma, and comment upon the role that collisions may play in determining the charge state distributions as a function of the neon ion number density.
    Low and medium energy deuteron-induced reactions on 63,65Cu nuclei
    [Abstract]
    E. Šimečková, P. Bém, M. Honusek, M. Štefánik, U. Fischer, S.P. Simakov, R.A. Forrest, A.J. Koning, J.-C. Sublet, M. Avrigeanu, F.L. Roman V. Avrigeanu, Phys. Rev. C84 (2011) 014605.
    doi:10.1103/PhysRevC.84.014605
    Abstract
    The activation cross sections of (d,p), (d,2n), (d,3n), and (d,2p) reactions on 63,65Cu were measured in the energy range from 4 to 20 MeV using the stacked-foil technique. Then, following the available elastic-scattering data analysis that provided the optical potential for reaction cross-section calculations, an increased effort was devoted to the breakup mechanism, direct reaction stripping, and pre-equilibrium and compound-nucleus cross-section calculations, corrected for the breakup and stripping decrease of the total reaction cross section. The overall agreement between the measured and calculated deuteron activation cross sections proves the correctness of the nuclear mechanism account, next to the simultaneous analysis of the elastic-scattering and reaction data.
    Shutdown dose rate analyses for the IFMIF HFTM
    [Abstract]
    A. Serikov, F. Arbeiter, U. Fischer, V. Heinzel, A. Klix, S.P. Simakov, Fusion Eng. Des. 86 (2011) pp. 2639–2642.
    doi:10.1016/j.fusengdes.2010.11.030
    Abstract
    This work contributes to neutronic support activity for the high flux test module (HFTM) designing in the framework of the IFMIF/EVEDA project. The engineering design of the IFMIF maintenance and remote handling systems is significantly affected by the radiation doses originating from radioactive materials generated during operation in the IFMIF HFTM. Two aspects of shutdown doses have been analyses for the HFTM radioactive materials removed from the IFMIF target and test cell (TTC) and then placed into the hot cell. First aspect is machine reliability expressed through absorbed gamma dose rate in the envisaged radiation-sensitive silicon-based electronics located closely to the radioactive HFTM materials. Second one is radiation protection and safety of a human being presented quantitatively as human biological dose equivalent rate around the HFTM materials. Shutdown dose rate assessments were performed for different materials subjected to the radiation by decay photons emitted from the HFTM. Three different decay radiation sources were considered in the analyses: a simple Eurofer specimen, a single HFTM rig packed with specimens and an assembly consisting of 12 rigs. The shutdown dose rate has been assessed taking into account transport of decay gammas by means of subsequent use of three computer codes: McDeLicious, FISPACT-2007, and MCNP5.
    State-of-the-art of computational tools and data for IFMIF neutronics and activation analyses
    [Abstract]
    U. Fischer, A. Klix, J. Li, P. Pereslavstev, S.P. Simakov, R.A. Forrest, F. Wasastjerna, J. Nucl. Mats. 417 (2011) pp.1311–1315.
    doi:10.1016/j.jnucmat.2010.12.266
    Abstract
    An overview is presented of the state-of-the-art of computational tools, data and models developed for neutronics and activation analyses of the IFMIF neutron source. Significant progress has been achieved in making available computational tools for simulating the d-Li neutron (and photon) source term with the McDeLicious Monte Carlo code and associated d+6,7Li cross-section data, in generating neutronics Monte Carlo geometry models by the McCad conversion software, and in providing the interface programme MCDO to enable coupled 3D Monte Carlo and discrete ordinates shielding calculations. In the field of nuclear data for IFMIF, a major milestone has been achieved with the launching of the FENDL- 3 research project co-ordinated by the IAEA. Another major achievement is the production of the European Activation File, version EAF-2007, which has the neutron energy range extended to the needs of IFMIF and also provides calculated data libraries for deuteron and proton induced activation reactions.
    Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
    [Abstract]
    O. Cabellos, A. Klix, U. Fischer, N. Garcia-Herranz, J. Sanz, S. Simakov, J. Nucl. Mats. 417 (2011) pp. 1307–1310.
    doi:10.1016/j.jnucmat.2010.12.269
    Abstract
    The prediction of the tritium production is required for handling procedures of samples, safety & maintenance and licensing of the International Fusion Materials Irradiation Facility (IFMIF). A comparison of the evaluated tritium production cross-sections with available experimental data from the EXFOR data base has shown insufficient validation. And significant discrepancies in evaluated cross-section libraries, including lack of tritium production reactions for some important elements, were found. Here, we have addressed an uncertainty analysis to draw conclusions on the reliability of the tritium prediction under the potential impact of activation cross-section uncertainties. We conclude that there is not sufficient experimental validation of the evaluated tritium production cross-sections, especially for iron and sodium. Therefore a dedicated experimental validation program for those elements should be desirable.
    Displacement damage induced in iron by gammas and neutrons under irradiation in the IFMIF test cell
    [Abstract]
    S.P. Simakov and U. Fischer, J. Nucl. Mat., 417 (2011) pp. 1321–1324.
    doi:10.1016/j.jnucmat.2010.12.175
    Abstract
    This work presents a complete comparative analysis of the radiation damage induced in iron-based materials in IFMIF by photons and neutrons. The gamma induced damage takes into account, for the first time, both photonuclear and photoatomic reaction mechanisms. The relevant cross sections were taken from available data evaluations. The gamma and neutron radiation fields were calculated by the McDeLicious Monte Carlo code using a 3-D geometry model. Finally the gamma and neutron induced damages in the iron have been assessed inside the IFMIF test cell and the surrounding concrete walls. It was found that the photoatomic mechanism dominates the photonuclear with at least one hundred times higher damage rates. The ratio of the gamma and the neutron induced displacement damage was found to be 10-3 inside the concrete wall and 10-5 in the components close to d-Li source. This fraction may increase a few times due to the uncertainty of the evaluated γ-dpa cross sections and the different surviving probabilities for defects produced by gammas and neutrons, nevertheless unlikely exceed 1%.
    Modelling d-Be and d-C neutron sources for SPIRAL-2
    [Abstract]
    M. Majerle and S.P. Simakov, Procs. Workshop “Nuclear Measurements, Evaluations and Applications – NEMEA-6”, 25-28 October 2010, Krakow, Poland, NEA/NSC/DOC(2011)4, OECD 2011, pp. 131-136.
    Abstract
    SPIRAL-2 facility, which is currently under construction, will produce intense white neutron spectra using deuteron beams (30-40 MeV) bombarding thick Be and C targets. The experimental data describing neutron production and induced radioactivity in these types were studies and data were fitted to phenomenological models to be used in future calculations concerning SPIRAL-2 and similar facilities.
    High energy density matter generation using a focused soft-X-ray laser for volumetric heating of thin foils
    [Abstract]
    B. Rus, T. Mocek, M. Kozlová, J. Polan, P. Homer, M. Fajardo, M.E. Foord,*, H. Chung, S.J. Moon, R.W. Lee, J. High Energy Density Physics 7 (2011) pp. 11-16.
    doi:10.1016/j.hedp.2010.05.001
    Abstract
    We report on time-resolved transmission measurements of a 21.2 nm X-ray laser through thin Al and polyimide foils in the intensity range 1010-1012 Wcm-2. Absolute time-integrated and relative timedependent transmission measurements indicate significant differences with cold opacity data, due to the heating, leading to partially ionized states with temperatures of 0.5-20 eV. The transmission data are compared with simulations that qualitatively reproduce the time-dependent transmission measurements and demonstrate the importance of including detailed atomic absorption processes in the warm dense matter regime.
    ADS-related activities at IAEA: From accelerators, neutron sources to fuel cycle and databases
    [Abstract]
    F. Mulhauser, P. Adelfang, R.M. Capote Noy, V. Inozemtsev, G. Mank, D. Ridikas, A. Stanculescu, A. Zeman, Procs. Workshop on Technology and Components of Accelerator driven Systems, Karlsruhe, Germany, March 2010, Nuclear Science 2011, OECD-NEA, ISBN 978-92-64 11727-3, pp. 307-319.
    Abstract
    The ADS-related activities at the IAEA address nuclear science and nuclear energy topics, and are implemented as a joint effort between the Departments of Nuclear Sciences and Applications and Nuclear Energy. The IAEA is pursuing efforts on utilising accelerators and research reactors to support the basic and applied research, provide intense neutron sources, characterise and qualify materials of nuclear interest and concomitantly, train and qualify a highly educated nuclear workforce. At the back end of the nuclear fuel cycle, environmental concerns linked with the long half-life radioisotopes generated from nuclear fission have led to increased R&D efforts to develop a technology aimed at reducing the amount of radioactive waste through transmutation in either fast fission reactors or ADS. In the framework of the project on Technology Advances in Fast Reactors and Accelerator-driven Systems, the IAEA has implemented a number of initiatives on utilisation of plutonium and transmutation of long-lived radioactive waste, accelerator-driven systems, thorium fuel options, innovative nuclear reactors and fuel cycles, non-conventional nuclear energy systems, and fusion/fission hybrids. This paper gives an overview of IAEA’s accelerator-related activities in nuclear science for materials development, and partitioning and transmutation of nuclear waste.
    JENDL-4.0: A new library for nuclear science and engineering
    [Abstract]
    K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto, A. Ichihara, S. Kunieda, S. Chiba, K. Furutaka, N. Otuka, T. Ohsawa, T. Murata, H. Matsunobu, A.Zukeran, So Kamada, J.I Katakura, J. Nucl. Sci. Technol. 48 (2011) pp. 1-30.
    doi:10.3327/jnst.48.1
    Abstract
    The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the improvements of fission product and minor actinoid data. Two nuclear model codes were developed in order to evaluate the cross sections of fission products and minor actinoids. Coupled-channel optical model parameters, which can be applied to wide mass and energy regions, were obtained for nuclear model calculations. Thermal cross sections of actinoids were carefully examined by considering experimental data or by the systematics of neighboring nuclei. Most of the fission cross sections were derived from experimental data. A simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. New evaluations were performed for the thirty fission product nuclides that had not been contained in the previous library JENDL-3.3. The data for light elements and structural materials were partly reevaluated. Moreover, covariances were estimated mainly for actinoids. The new library was released as JENDL-4.0, and the data can be retrieved from the Web site of the JAEA Nuclear Data Center.
    Neutron capture on 94Zr: Resonance parameters and Maxwellian-averaged cross sections
    [Abstract]
    G. Tagliente, R. Capote, et. al., (the n_TOF collaboration), Phys. Rev. C84 (2011) 015801.
    doi:10.1103/PhysRevC.84.015801
    Abstract
    The neutron capture cross sections of the Zr isotopes play an important role in nucleosynthesis studies. The s-process reaction flow between the Fe seed and the heavier isotopes passes through the neutron magic nucleus 90Zr and through 91,92,93,94Zr, but only part of the flow extends to 96Zr because of the branching point at 95Zr. Apart from their effect on the s-process flow, the comparably small isotopic (n,γ) cross sections make Zr also an interesting structural material for nuclear reactors. The 94Zr (n,γ) cross section has been measured with high resolution at the spallation neutron source n_TOF at CERN and resonance parameters are reported up to 60 keV neutron energy.
    Neutron-induced fission cross section of natPb and 209Bi from threshold to 1 GeV: An improved parametrization
    [Abstract]
    D. Tarrio, R. Capote, et. al., (the n_TOF collaboration), Phys. Rev. C83 (2011) 044620.
    doi:10.1103/PhysRevC.83.044620
    Abstract
    Neutron-induced fission cross sections for natPb and 209Bi were measured with a white-spectrum neutron source at the CERN Neutron Time-of-Flight (n TOF) facility. The experiment, using neutrons from threshold up to 1 GeV, provides the first results for these nuclei above 200 MeV. The cross sections were measured relative to 235U and 238U in a dedicated fission chamber with parallel plate avalanche counter detectors. Results are compared with previous experimental data. Upgraded parametrizations of the cross sections are presented, from threshold energy up to 1 GeV. The proposed new sets of fitting parameters improve former results along the whole energy range.
    197Au(n,γ) cross section in the unresolved resonance region
    [Abstract]
    C. Lederer, R. Capote, et. al., (the n_TOF collaboration), Phys. Rev. C83 (2011) 034608.
    doi:10.1103/PhysRevC.83.034608
    Abstract
    The cross section of the reaction 197Au(n,γ ) was measured with the time-of-flight technique at the n_TOF (neutron time-of-flight) facility in the unresolved resonance region between 5 and 400 keV using a pair of C6D6 (where D denotes 2H) liquid scintillators for the detection of prompt capture γ rays. The results with a total uncertainty of 3.9%–6.7% for a resolution of 20 bins per energy decade show fair agreement with the Evaluated Nuclear Data File Version B-VII.0 (ENDF/B-VII.0), which contains the standard evaluation. The Maxwellian averaged cross section (MACS) at 30 keV is in excellent agreement with the one according to the ENDF/B-VII.0 evaluation and 4.7% higher than the MACS measured independently by activation technique. Structures in the cross section, which had also been reported earlier, have been interpreted as being due to clusters of resonances.
    Towards an improved evaluation of neutron-induced fission cross sections on actinides
    [Abstract]
    S. Goriely, S. Hilaire, A.J. Koning, R. Capote, Phys. Rev. C83 (2011) 034601.
    doi:10.1103/PhysRevC.83.034601
    Abstract
    Mean-field calculations can now provide all the nuclear ingredients required to describe the fission path from the equilibrium deformation up to the nuclear scission point. The information obtained from microscopic mean-field models has been included in the TALYS reaction code to improve the predictions of neutron-induced fission cross sections. The nuclear inputs concern not only the details of the energy surface along the fission path, but also the coherent estimate of the nuclear level density derived within the combinatorial approach on the basis of the same single-particle properties, in particular at the fission saddle points. The predictive power of such a microscopic approach is tested on the experimental data available for the uranium isotopic chain. It is also shown that the various inputs can be tuned to reproduce, at best, experimental data in one unique coherent framework, so that in a close future it should become possible to make, on the basis of such models, accurate fission-cross-section calculations and the corresponding estimates for nuclei, energy ranges, or reaction channels for which no data exist. Such model uncertainties are usually not taken into account in data evaluations.
    Nuclear data evaluation of 55Mn by the EMPIRE code with emphasis on the capture cross-section
    [Abstract]
    A. Miloccoa, A. Trkov, R. Capote, Nucl. Eng. Design 241 (2011) pp. 1071-1077.
    doi:10.1016/j.nucengdes.2010.05.045
    Abstract
    Manganese is one of the constituents of alloys for structural components of fission and fusion devices and a well-known neutron dosimeter; however, existing ENDF-B/VII.0 55Mn evaluation was produced by Shibata (1989). This work is an attempt to re-evaluate neutron-induced cross-sections of 55Mn using the latest release of the EMPIRE code. Sensitivity studies on the physical and fitting parameters are presented, with special emphasis on the capture and neutron inelastic cross-sections. A calculated nuclear data file in ENDF-6 format of the neutron interaction cross-sections is produced. It extends up to 150 MeV, which is of interest for fusion and accelerator driven system applications. This evaluation is compared with the ENDF/B-VII.0 evaluation and with a selection of experimental microscopic cross-sections. The evaluation is tested using integral data: the OKTAVIAN integral experiment on a manganese shell and an FNG experiment with manganese activation foils. Benchmark results provide needed feedback for the refinement of the physics parameters.
    Giant dipole resonance parameters with uncertainties from photonuclear cross sections
    [Abstract]
    V.A. Plujko, R. Capote, O.M. Gorbachenko, Atomic Data and Nuclear Data Tables 97 (2011) pp. 567-585.
    doi:10.1016/j.adt.2011.04.001
    Abstract
    Updated values and corresponding uncertainties of isovector giant dipole resonance (IVGDR or GDR) model parameters are presented that are obtained by the least-squares fitting of theoretical photoabsorption cross sections to experimental data. The theoretical photoabsorption cross section is taken as a sum of the components corresponding to excitation of the GDR and quasideuteron contribution to the experimental photoabsorption cross section. The present compilation covers experimental data as of January 2010.
    Neutron-induced fission cross-section of 233U in the energy range 0.5 < En < 20MeV
    [Abstract]
    F. Belloni, R. Capote, (the n_TOF Collaboration), Eur. Physical. J. A (2011) p. 47:2.
    doi:10.1140/epja/i2011-11002-y
    Abstract
    The neutron-induced fission cross-section of 233U has been measured at the CERN n TOF facility relative to the standard fission cross-section of 235U between 0.5 and 20MeV. The experiment was performed with a fast ionization chamber for the detection of the fission fragments and to discriminate against α-particles from the natural radioactivity of the samples. The high instantaneous flux and the low background of the n_TOF facility result in data with uncertainties of ≈ 3%, which were found in good agreement with previous experiments. The high quality of the present results allows to improve the evaluation of the 233U(n,f) cross-section and, consequently, the design of energy systems based on the Th/U cycle.
    Influence of resonance parameters’ correlations on the resonance integral uncertainty; 55Mn case
    [Abstract]
    G. Žerovnik, A. Trkov, R. Capote, D. Rochman, Nucl. Instr. Meth. Phys. Res. A632 (2011) pp. 137-141.
    doi:10.1016/j.nima.2010.12.210
    Abstract
    For nuclides with a large number of resonances the covariance matrix of resonance parameters can become very large and expensive to process in terms of the computation time. By converting covariance matrix of resonance parameters into covariance matrices of background cross-section in a more or less coarse group structure a considerable amount of computer time and memory can be saved. The question is how important is the information that is discarded in the process. First, the uncertainty of the 55Mn resonance integral was estimated in narrow resonance approximation for different levels of self-shielding using Bondarenko method by random sampling of resonance parameters according to their covariance matrices from two different 55Mn evaluations: one from Nuclear Research and Consultancy Group NRG (with large uncertainties but no correlations between resonances), the other from Oak Ridge National Laboratory (with smaller uncertainties but full covariance matrix). We have found out that if all (or at least significant part of the) resonance parameters are correlated, the resonance integral uncertainty greatly depends on the level of self-shielding. Second, it was shown that the commonly used 640-group SAND-II representation cannot describe the increase of the resonance integral uncertainty. A much finer energy mesh for the background covariance matrix would have to be used to take the resonance structure into account explicitly, but then the objective of a more compact data representation is lost.
    Assessment of the unresolved resonance treatment for cross-section and covariance representation
    [Abstract]
    L. Leal, G. Noguère, C. de Saint John, I. Sirakov, R. Capote, J.-C. Sublet, P. Ribon, M. Coste Delclaux, C. Jouanne, O. Iwamoto, G. Chiba, K. Shibata, R.E. MacFarlane, A.C. Kahler Jr., C.R. Libutz, D. Cullen, M. Herman, (Members of Subgroup 32 – International Evaluation Cooperation, NEA/OECD), NEA/NSC/WPEC/DOC(2011)430, OECD/NEA 2011.
    Abstract
    The report was issued by WPEC Subgroup 32, which investigates the methodologies used in the unresolved resonance region (URR) for cross-section and covariance representation. The objectives of the subgroup were to: - investigate the use of the Single-level Breit-Wigner formalism in the URR for fissile and fertile isotopes; - investigate URR parameter representation based on the LSSF = 0 or LSSF - 1 option; - report on teh URR resonance parameter interpolation issue; - report on the URR covariance representation.
    Covariance data in the fast neutron region
    [Abstract]
    E. Bauge, R. Capote, U. Fisher, A.Yu. Konobeyev, P.E. Pereslavtsev, M. Herman, P. Obložinský, M.T. Pigni, T. Kawano, P. Talou, I. Kodeli, A. Trkov, A. Koning, D. Rochman, H. Leeb, D. Neudecker, D.L. Smith (Members of Subgroup 24 – International Evaluation Cooperation, NEA/OECD), NEA/NSC/WPEC/DOC(2010)427, OECD/NEA 2011.
    Abstract
    The report has been issued by WPEC Subgroup 24, whose mission was to review methodologies and develop tools for producing data uncertainties (covariance data) in the fast neutron energy region. These involve both least-squares procedures and, more recently, stochastic (Monte Carlo) techniques. Since all modern approaches depend on extensive usage of nuclear reaction modelling, consideration is given to recent attempts to determine the extent to which nuclear modelling deficiencies contribute to the uncertainty of contemporary nuclear data evaluation.
    Measurements and evaluation of differential cross-sections for ion beam analysis
    [Abstract]
    A.F. Gurbich, D. Abriola, N.P. Barradas, A.R. Ramos, I. Bogdanovic-Radovic, M. Chiari, C. Jeynes, M. Kokkoris, M. Mayer, L. Shi, I. Vickridge. Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 2010-2013.
    doi:10.3938/jkps.59.2010
    Abstract
    Ion beam analysis (IBA) methods always rely on available differential cross-section data to obtain quantitative results about composition and structure of the near-surface layer of a sample. In order to meet the nuclear data needs of the IBA community, the Coordinated Research Project (CRP) "Development of a Reference Database for Ion Beam Analysis" was initiated by the IAEA in 2005 and will be concluded in 2010. A summary of the results of this IAEA Coordinated Research Project activity is presented, problems still existing in the eld are discussed, and ways to further develop nuclear data for IBA are indicated.
    Fission cross-section measurements of 233U, 245Cm and 241,243Am at CERN n_TOF facility
    [Abstract]
    M. Calviani, R. Capote, et al., (the n_TOF collaboration), Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1912-1915.
    doi:10.3938/jkps.59.1912
    Abstract
    Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.
    237Np(n,f) cross section: New data and present status
    [Abstract]
    C. Paradela, R. Capote, et al., (the n_TOF collaboration), Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1908-1911.
    doi:10.3938/jkps.59.1908
    Abstract
    In this document, we present the final result obtained at the n_TOF experiment for the neutron- induced fission cross section of the 237Np, from the fission threshold up to 1 GeV. The method applied to get this result is briefly discussed. n_TOF data are compared to the last experimental measurements using other TOF facilities or the surrogate method, reported experiments performed with monoenergetic sources and the FISCAL systematic, including a discussion about the existing discrepancies.
    High-energy neutron-induced fission cross sections of natural lead and bismuth-209
    [Abstract]
    D. Tarrío, R. Capote, et al., (the n_TOF collaboration), Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1904-1907.
    doi:10.3938/jkps.59.1904
    Abstract
    The CERN Neutron Time-Of-Flight (n_TOF) facility is well suited to measure small neutron- induced ssion cross sections, as those of subactinides. The cross section ratios of natPb and 209Bi relative to 235U and 238U were measured using PPAC detectors. The fragment coincidence method allows to unambiguously identify the ssion events. The present experiment provides the first results for neutron-induced fission up to 1 GeV for natPb and 209Bi. A good agreement with previous experimental data below 200 MeV is shown. The comparison with proton-induced ssion indicates that the limiting regime where neutron-induced and proton-induced ssion reach equal cross section is close to 1 GeV.
    Neutron capture measurements on minor actinides at the n_TOF facility at CERN: Past, present and future
    [Abstract]
    D. Cano-Ott. R Capote, et al., (the n_TOF collaboration), Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1809-1818.
    doi:10.3938/jkps.59.1809
    Abstract
    The successful development of advanced nuclear systems for sustainable energy production and nuclear waste management depends on high quality nuclear data libraries. Recent sensitivity stud- ies and reports [1-3] have identi ed the need for substantially improving the accuracy of neutron cross-section data for minor actinides. The n TOF collaboration has initiated an ambitious exper- imental program for the measurement of neutron capture cross sections of minor actinides. Two experimental setups have been constructed for this purpose: a Total Absorption Calorimeter (TAC) [4] for measuring neutron capture cross-sections of low-mass and/or radioactive samples and a set of two low neutron sensitivity C6D6 detectors for the less radioactive materials.
    The measurement of neutron activation cross section of 59Co below 36 MeV
    [Abstract]
    E. Šimečková, P. Bém, V. Burjan, U. Fischer, R.A. Forrest, M. Götz, M. Honusek, V. Kroha, J. Novák, S.P. Simakov, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1801-1804.
    doi:10.3938/jkps.59.1801
    Abstract
    An accurate knowledge of the cross section for neutron-induced reactions on 59Co is of importance due to use of cobalt as a structural material in fission and fusion reactors, its applicability in neutron dosimetry and for testing theoretical models as well. The thin Co foils (0.25 mm thickness, 99.9% purity, Goodfellow product) were irradiated in the quasi-momoenergetic p-Li neutron field. For the production of the neutron fields, the proton beam from the NPI energy-variable cyclotron U120M at proton energies 19.8, 25.1, 27.6, 30.1, 32.7, 35.0 and 37.4 MeV and thin 7Li target with carbon stopper were used. The reaction 7Li(p,n) produces the high-energy quasi-monoenergetic neutrons with tail to lower energies. The flux density and neutron spectra were evaluated by MCNPX code using 7Li(p,n) cross section measurement of other authors and including correction to the NPI target layout. The time profile of the neutron source strength during the irradiation was monitored by the proton beam current on the neutron-source target, recorded by a calibrated current-to-frequency converter on a PC. Au foils were used as additional monitors. The foil activity determination was performed by the nuclear spectrometry method employing two calibrated HPGe detectors of 23 and 50% efficiency and of FWHM (Full Width Half Maximum) 1.8 keV at 1.3 MeV for gamma-ray measurement. The reaction rates for 59Co(n,p)59Fe, 59Co(n,α)56Mn, 59Co(n,2nα)54Mn, 59Co(n,3n)57Co, 59Co(n2n)58mCo and 59Co(n,2n)58gCo were obtained. Integral activation cross sections were estimated. The preliminary results are discussed.
    Neutron-induced activation cross sections on hafnium isotopes from the threshold to 20 MeV
    [Abstract]
    V. Semkova, R. Jaime Tornin, N. Janeva, N. Koyumdjieva, A. Moens, A.J. Plompen, K. Volev, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1737-1740.
    doi:10.3938/jkps.59.1737
    Abstract
    Results of new cross section measurements are presented for the following neutron-induced reactions : 178Hf(n,α)175Yb, 180Hf(n,α)177Yb, 177Hf(n,p)177Lug, 178Hf(n,x)177Lug, 180Hf(n,p)180Lu, 180Hf(n,n'γ)180Hfm, 174Hf(n,2n)173Hf, 176Hf(n,2n)175Hf, and 177Hf(n,3n)175Hf obtained with the activation technique. The irradiations were carried out at the 7-MV Van de Graaff accelerator at IRMM, Geel. Quasi monoenergetic neutrons with energies between 14.8 and 20.5 MeV were produced via the 3H(d,n)4He reaction at Ed = 1, 1.4, 2, 3, and 4 MeV. The 3H(p,n)3He reaction was employed for the production of neutrons in the 2 - 3 MeV energy range. Both natural and enriched samples were used to facilitate correction for interference between reactions leading to the same product. The radioactivity of the samples was determined by standard γ-ray spectrometry using HPGe detector. The current measurements are compared with the data from other authors and Evaluated Nuclear Data Files. Cross sections for three of the studied reactions are reported for the first time.
    Renewed database of GDR parameters for atomic nuclei
    [Abstract]
    by V.A. Plujko, O.M. Gorbachenko, V.M. Bondar, R. Capote, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1514-1517.
    doi:10.3938/jkps.59.1514
    Abstract
    Updated values of giant dipole resonance parameters with uncertainties are presented which were obtained by a chi-square t of the theoretical photoabsorption cross sections to the experimental data. Renewed systematics for giant dipole resonance parameters are given. Different Lorentzian-type models of dipole strength functions are tested by comparison of the calculations with experimental data. It is demonstrated that closed-form approaches with asymmetric shape of the gamma strength provide the most reliable simple method for estimation of the γ-decay.
    Study of photon strength function of actinides: The case of 235U, 238Np and 241Pu
    [Abstract]
    C. Guerrero, R. Capote, et al., (the n_TOF collaboration), Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1510-1513.
    doi:10.3938/jkps.59.1510
    Abstract
    The decay from excited levels in medium and heavy nuclei can be described in a statistical approach by means of Photon Strength Functions and Level Density distributions. The study of electromagnetic cascades following neutron capture based on the use of high efficiency detectors has been shown to be well suited for probing the properties of the Photon Strength Function of heavy (high level density) and/or radioactive (high background) nuclei. In this work we have investigated for the first time the validity of the recommended PSF of actinides, in particular 235U, 238Np and 241Pu. Our study includes the search for resonance structures in the PSF below Sn and draws conclusions regarding their existence and their characteristics in terms of energy, width and electromagnetic nature.
    New IAEA actinide decay data library
    [Abstract]
    M.A. Kellett, M.-M. Bé, V. Chechev, X. Huang, F.G. Kondev, A. Luca, G. Mukherjee, A.L. Nichols, A. Pearce, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1455-1460.
    doi:10.3938/jkps.59.1455
    Abstract
    A recently completed IAEA Coordinated Research Project (CRP) entitled "Updated Decay Data Library for Actinides" has resulted in new and comprehensive evaluations of the decay scheme data for over forty nuclear-power related actinides, along with a further forty radionuclides that arise from their natural decay. A number of data inadequacies remain despite a series of well-defined measurements being undertaken under the auspices of this CRP, which were subsequently incorporated into the relevant evaluations. A list is given of these outstanding measurement requirements as identified from observed shortcomings in the available data. The final data library is available in two standard formats: ENSDF for use in nuclear structure studies, and ENDF for nuclear plant applications including design and operation. Evaluations were undertaken by following the precise methodology of the Decay Data Evaluation Project (DDEP) to ensure that a uniform approach was applied by all participants. The library and associated documentation are available from a dedicated IAEA webpage (http://www-nds.iaea.org/act ddl/).
    Production of long-lived radionuclides 10Be, 14C, 53Mn, 55Fe, 59Ni and 202gPb in a fusion environment
    [Abstract]
    A. Wallner, K. Buczak, C. Lederer, H. Vonach, T. Faestermann, G. Korschinek, M. Poutivtsev, G. Rugel, A. Klix, K. Seidel, A. Plompen, V. Semkova, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1378 1381.
    doi:10.3938/jkps.59.1378
    Abstract
    In a fusion reactor and also in future advanced reactor types, long-lived activation products may lead to significant long-term waste disposals and radiation damage. Many of these production cross sections are not well-known, making it difficult to calculate concentration limits. Some prominent long-lived activation products comprise 10Be, 14C, and 26Al; in the medium-mass range the radionuclides 53Mn, 55,60Fe, 59,63Ni; and for heavier isotopes 202mPb, 210mBi. Since a few years the technique of accelerator mass spectrometry (AMS) has been applied at the Vienna Environmental Research Accelerator (VERA) facility for the detection of long-lived radionuclides for such studies. In this respect, samples were irradiated with quasi-monoenergetic neutrons at TU Dresden's 14-MeV neutron generator and the van de Graaff accelerator at IRMM. After the activations the samples were prepared for isotope ratio measurements via AMS. Production of long-lived 53Mn and 59Ni was measured via AMS utilizing the 14-MV tandem of the Maier-Leibnitz- laboratory, TU Munich. Radionuclides 10Be, 14C, 26Al, 55Fe, 210mBi, and 202gPb are measured at the VERA facility.
    Neutron activation experiments on niobium in NPI p-7Li quasi-monoenergetic neutron field
    [Abstract]
    M. Honusek, P. Bém, V. Burjan, U. Fischer, M. Götz, V. Kroha, J. Novák, S.P. Simakov, E. Šimečková, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1374 1377.
    doi:10.3938/jkps.59.1374
    Abstract
    The work aims to make the study of neutron activation cross section data up to 35 MeV neutron energy using the reaction 7Li(p,n). This reaction produces the high energy quasi-monoenergetic neutrons with the tail to lower energies. The cross-section data for niobium for neutron energies higher than 23 MeV do not exist. These data are needed to develop the dosimetry foil method for neutron spectrometry inside the test cell of IFMIF (International Fusion Material Irradiation Facility) and for the test of nuclear models as well. The reactions (n,2n), (n,3n), (n,4n), (n,3He), (n,α), and (n,α2n) are studied. The corresponding experimental cross sections are calculated.
    The European effort on the evaluation and validation of nuclear data for fusion technology applications
    [Abstract]
    U. Fischer, P. Batistoni, E. Dupont, R.A. Forrest, H. Henriksson, J. Izquierdo,J.-C. Sublet Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1369-1373.
    doi:10.3938/jkps.59.1369
    Abstract
    An overview is presented of the European Fusion File (EFF) and the European Activation File (EAF) efforts which aim at developing qualified nuclear data bases and validated computational tools for nuclear calculations of fusion systems tailored to the specific needs of the European fusion programme. The related tasks are conducted in the frame of the Fusion for Energy (F4E) work programme and are devoted to the evaluation, processing, testing and benchmarking of required nuclear cross section and uncertainty data, the development of computational tools for sensitivity/uncertainty calculations, and to conduct integral benchmark experiments exploiting also new measurement techniques. The data evaluations are integrated into the Joint Evaluated Fission and Fusion File (JEFF) after having passed a series of qualification tests including their validation through computational analyses of integral benchmark experiments.
    235U(n,f), 233U(n,f) and 239Pu(n,f) prompt fission neutron spectra
    [Abstract]
    V.M. Maslov, N.A. Tetereva, V.G. Pronyaev, A.B. Kagalenko, K.I. Zolotarev, R. Capote, T. Granier, B. Morillon, F.-J.Hambsch, J.-C. Sublet, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1337-1342.
    doi:10.3938/jkps.59.1337
    Abstract
    New prompt fission neutron spectra (PFNS) matrices for the n+235U, n+233U, and n+239Pu systems are prepared. Present and previous PFNS shapes are drastically different from each other, the former being consistent with measured data base. A combined generalized least-squares fit of nth+235U, nth+233U, nth+239Pu, and 252Cf(sf) measured data base is accomplished. The solution of the longstanding problem of inconsistency of 235U integral data testing and differential prompt fission neutron spectra data (PFNS) is proposed. Similar problems for the n+233U and n+239Pu are envisaged, revealing arbitrary tweaking of relevant neutron cross sections. Fast 235U integral critical assemblies like Godiva or Flattop benchmarks are reproduced with the same accuracy as with the PFNS of the major data libraries. That reveals a rather delicate compensation effect, tracking the success of the distorted PFNS of the major data libraries to the excessive number of neutrons at energies of 1-3 MeV. Thermal assembly benchmarking reveals positive biases in keff which might be attributed to the influence of a soft energy tail of the present PFNS. For some of Valduc's LCT benchmarks biases in keff are less than 20 pcm. Fast 239Pu integral critical experiments like Jezebel reveal the influence of overestimated inelastic scattering for 239Pu, arbitrarily introduced previously to diminish the influence on the keff of the distortion of the PFNS.
    Exploratory data analysis of the EXFOR database
    [Abstract]
    E. Dupont, A.J. Koning, N. Otuka, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1333-1337.
    doi:10.3938/jkps.59.1333
    Abstract
    The EXFOR database is a large collection of experimental nuclear reaction data for incident neutrons, charged particles and photons. The EXchange FORmat was designed to be very flexible in order to be able to store the data as published. However, this flexibility is a drawback for systematic comparison of EXFOR data with evaluated data or nuclear reaction code results. The WPEC Subgroup 30 on "Improvement of Accessibility and Quality of the EXFOR Database" was founded with the aims to establish EXFOR as a more easily accessible and reliable database. In this framework, a directory-structured database was created in simple tabular format. The content of this database was verified with various statistical tests and compared with default results from the TALYS code. This work allowed various problems to be identified, either in the EXFOR translating codes or in the EXFOR database, and sometimes in the original publications.
    Information management tools for Evaluated Nuclear Structure Data File (ENSDF) interrogation and dissemination
    [Abstract]
    M. Verpelli, D. Abriola, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1322-1324.
    doi:10.3938/jkps.59.1322
    Abstract
    The evolution of Information Technology has made it possible to provide the Nuclear Data community with various flexible tools customized to respond to individual data queries, to provide visualization, and facilitate dissemination. In another effort to further these developments, the IAEA's Nuclear Data Section has developed a set of applications based on a relational database designed for nuclear structure and decay data. The tools presented in this work mainly use the nuclear structure and decay data obtained from ENSDF and the Nuclear Wallet cards. The present set of applications comprises an interactive Chart of Nuclides (LiveChart) not only presenting the Chart graphically, but also allowing the visualization of data patterns while changing filtering criteria, a web-based query application and a desktop version of the relational database giving support to expert users to customize their data-processing applications. Some examples of the three software tools are presented.
    Database for time-of-flight spectra including covariances
    [Abstract]
    N. Otuka, A. Borella, S. Kopecky, C. Lampoudis, P. Schillebeeckx, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1314-1317.
    doi:10.3938/jkps.59.1314
    Abstract
    A data format for time-of-flight spectra (transmission, reaction and self-indication yields) and their covariance matrices based on the AGS (Analysis of Geel Spectra) format is discussed in collaboration between EC-JRC IRMM and IAEA-NDS for the EXFOR library. Experimentalists are encouraged to consider the uncertainty propagation following the AGS principle and submission of their data to the International Networks Nuclear Reaction Data Centres (NRDC) for EXFOR compilation using a proposed template.
    Nuclear data activities in the International Atomic Energy Agency-Nuclear Data Section (IAEA-NDS)
    [Abstract]
    R.A. Forrest, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1303-1308.
    doi:10.3938/jkps.59.1303
    Abstract
    As part of its function the IAEA-NDS coordinates and supports nuclear data activities in the fields of neutron and charged-particle reactions and nuclear structure and decay data, and disseminates the resulting reports and databases. The NDS coordinates two international nuclear networks (and one atomic and molecular) - the International Network of Nuclear Reaction Data Centres (NRDC) and the International Network of Nuclear Structure and Decay Data Evaluators (NSDD). The NDS staff are also involved in several compilations and evaluations of nuclear data. Main activities include compilation for NSR and EXFOR, evaluation for ENSDF and DDEP and evaluation of neutron and charged-particle reaction cross sections and covariances. Most of the NDS support for nuclear data activities is in the form of Coordinated Research Projects and Data Development Projects; a summary of past, present and future activities is presented.
    The role of the nuclear reaction data centres in experimental nuclear data knowledge sharing
    [Abstract]
    N. Otuka, S. Dunaeva, E. Dupont, O. Schwerer, A. Blokhin, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1292-1297.
    doi:10.3938/jkps.59.1292
    Abstract
    The International Network of Nuclear Reaction Data Centres (NRDC) consists of 14 data centres from 10 countries and 2 international organisations, and is collaborating for compilation, exchange and dissemination of various types of nuclear reaction data information. The nuclear data centres common data collection, the EXFOR library today contains experimental information and numerical data from more than 18,000 experiments consisting of more than 134,000 data sets mainly of nuclear reaction data for incident neutrons, charged-particles and photons with incident energy lower than 1 GeV. A brief history and the current status of NRDC collaboration are presented for EXFOR as well as CINDA and ENDF.
    Unified Monte Carlo and mixed probability functions
    [Abstract]
    R. Capote, D.L. Smith, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010,J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1284-1287.
    doi:10.3938/jkps.59.1284
    Abstract
    The possibility of using the recently suggested Unified Monte Carlo (UMC) technique for the evaluation of nuclear reaction data other than those that are normally distributed is discussed in this paper. The alternative probability distributions examined here are: 1) lognormal distribution; 2) uniform interval distribution; and 3) exponential distribution. These distributions, together with the normal distribution, are capable of addressing most situations that are likely to be encountered in evaluating nuclear reaction data. The mathematical formalism is described and numerical examples are provided showing instances when the UMC method can lead to results which are quite different from those obtained using the Generalized Least Squares (GLS) method. We conclude that: 1) the GLS method gives reasonable results comparable to UMC for probability functions closely resembling symmetric normal distributions with small to modest uncertainties, but the UMC results are more reliable for broad or strongly asymmetric distributions; 2) the lognormal distribution can be used to good advantage in certain situations involving large uncertainties; 3) use of the uniform and exponential distributions by evaluators should be discouraged.
    Covariance evaluation for actinide nuclear data in JENDL-4
    [Abstract]
    O. Iwamoto, T. Nakagawa, S. Chiba, N. Otuka, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1224-1229.
    doi:10.3938/jkps.59.1224
    Abstract
    Covariances of actinide nuclear data stored in JENDL-4.0 have been evaluated based on available experimental data and reaction model calculation. The covariance matrix was basically deduced applying the consistent method with the nuclear data evaluation. For the fast neutron fission cross sections of 6 major actinides of 233,235,238U and 239,240,241Pu were evaluated simultaneously with experimental data of both cross sections and their ratios using the least-squares code SOK, resulting in giving the covariance matrices that has correlations between the data of different nuclei. For the minor actinide, the least-squares fitting code GMA was used for fission cross section evaluation. The covariances were obtained from the same calculation. For other reaction cross sections, covariances were evaluated using KALMAN code with the sensitivities calculated by CCONE code. Covariances for other data such as resonance parameters and average numbers of fission neutrons were also evaluated. The evaluated covariance data have been complied to the ENDF-6 format files. The JENDL-4.0 library contains covariance data of (1) average number of neutrons per fission (MF = 31), (2) resonance parameters (MF = 32), (3) cross sections (MF = 33), (4) angular distributions of elastic scattering (MF = 34), and (5) prompt fission spectra (MF = 35) for all 79 actinides.
    On the effects of correlations in evaluated nuclear data on the uncertainties in integral parameters
    [Abstract]
    A. Trkov, I. Kodeli, G. Žerovnik, R. Capote, D.W. Muir, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1213-1217.
    doi:10.3938/jkps.59.1213
    Abstract
    Taking the FNG-W benchmark with a D-T source in front of a large tungsten block as an example, the impact of the reaction cross-section covariance data on the predicted activities of monitor foils inside the block and the associated uncertainties were studied. Cross-material covariances between the isotopic cross sections of tungsten were obtained by including experimental measurements of the elemental total cross sections above the resonance range. Cross-material covariances of the elastic and the radiative capture reactions were considered. Since the original cross sections were evaluated accurately from the reasonably abundant isotopic data, the impact of introducing elemental data on the isotopic cross sections and their uncertainties were small. Correlations were observed mainly in the elastic channel, which has a relatively low sensitivity to the calculated monitor activities of the benchmark. Consequently, the impact on the predicted monitor sample activities was also small in terms of the absolute value and the uncertainty. The main achievement of the work was the demonstrated data consistency and the development of tools for including elemental data in isotopic cross section evaluation and the evaluation of cross-material covariances.
    Recent progress in neutron-, proton- and deuteron-induced reaction nuclear data for EAF-2010 and the European activation system
    [Abstract]
    L.W. Packer, J.-C. Sublet, J. Kopecky, R.A. Forrest, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1100-1103.
    doi:10.3938/jkps.59.1100
    Abstract
    The European Activation System (EASY) has been continuously developed and improved for more than 20 years. Its primary purpose is to carry out neutron- proton- and deuteron-induced activation calculations in support of nuclear technology, particularly for nuclear material selection, design and optimization. It comprises the EAF nuclear data libraries and the FISPACT inventory code. For fusion applications, materials used for the construction of ITER, particularly plasma facing components, will be submitted to intense neutron irradiation. These materials may be evaluated using EASY for their nuclide inventory, He gas production and decay heat production over time, for example. EASY includes data to 60 MeV, making it also relevant for IFMIF analysis, and now covers 66,256 reactions. Such large libraries require an extensive validation process, which includes the statistical analysis of cross sections (SACS) and comparisons with differential and integral data. The suite of these methods has now been extended to evaluate the next library release, EAF-2010. Furthermore, significant attention has been focused on improving the uncertainty file, a unique feature of EAF libraries. In this work we discuss recent data improvements to be included in EAF-2010 and extensions to the treatment of uncertainties both in EAF and within EASY.
    Status of the JEFF nuclear data library
    [Abstract]
    A.J. Koning, E. Bauge, C.J. Dean, E. Dupont, U. Fischer, R.A. Forrest, R. Jacqmin, H. Leeb, M.A. Kellett, R.W. Mills, C. Nordborg, M. Pescarini, Y. Rugama, P. Rullhusen, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1057-1062.
    doi:10.3938/jkps.59.1057
    Abstract
    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. Recently, the JEFF-3.1.1 nuclear data library was released and shortly after adopted by the French nuclear power industry for inclusion in their production and analysis codes. Recent updates include actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library, the decay data and fission yield sub-libraries, and fusion-related data files from the European F4E project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory, decay heat and shielding of thermal and fast systems. The next release of the library, JEFF-3.2, will be discussed. This will contain among others a significant increase of covariance data evaluations, modern evaluations for various structural materials, a larger emphasis on minor actinides and addition of high-quality gamma production data for many fission products.
    JENDL-4.0: A new library for innovative nuclear energy systems
    [Abstract]
    K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto, A. Ichihara, S.Kunieda, S. Chiba, J. Katakura, N. Otuka, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1046-1051.
    doi:10.3938/jkps.59.1046
    Abstract
    The fourth version of Japanese Evaluated Nuclear Data Library (JENDL-4.0) has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the improvements of fission product and minor actinide data. Achieving this, nuclear model codes were developed. Coupled-channel optical model parameters, which can be applied to a wide mass range, were obtained for evaluations. Thermal cross sections of many actinides were revised on the basis of experimental data or systematics. Simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. The new library JENDL-4.0 is made available on the Web site of the JAEA Nuclear Data Center.
    Self-consistent analyses of nuclear level structures, and nucleon interaction data of even-even Sn isotopes
    [Abstract]
    J.-Y. Lee, E. Sh. Soukhovitski, Y. Kim, R. Capote, S. Chiba, J.M. Quesada, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1019 1022.
    doi:10.3938/jkps.59.1019
    Abstract
    We have analyzed, within a unified approach, nuclear level structure, and nucleon interaction data of the even-even Sn isotopes - 116Sn, 118Sn, and 120Sn - using the soft-rotator nuclear model and an appropriate coupled-channels optical model with a dispersive Lane-consistent optical potential. Determined best-fit optical model potential is capable of simultaneously describing all the experimental nucleon interaction data available up to 200 MeV - total neutron cross sections, proton reaction cross sections, nucleon elastic and inelastic scattering cross sections, and direct (p,n) charge exchange reaction cross sections.
    Fission cross section calculations of actinides with EMPIRE code
    [Abstract]
    M. Sin, P. Obložinský, M. Herman, R. Capote, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1015-1018.
    doi:10.3938/jkps.59.1015
    Abstract
    Theoretical calculations of neutron induced reactions on 233,234,236U, 237Np, 238-242Pu, 241,243Am, 242-246Cm carried out in the energy range 1 keV - 20 MeV with EMPIRE code are presented, with emphasis on the fission channel. Beside a consistent, accurate set of calculations, the paper contains arguments supporting the choice of the reaction models and input parameters. A special attention is paid to the fission model parameters and their uncertainties.
    Towards improved evaluation of neutron-induced fission cross section
    [Abstract]
    S. Goriely, S. Hilaire, A.J. Koning, R. Capote, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 979-982.
    doi:10.3938/jkps.59.979
    Abstract
    Mean-field calculations can nowadays provide all the nuclear ingredients required to describe the fission path from the equilibrium deformation up to the nuclear scission point. The information obtained from microscopic mean-field models has been included in reaction codes to improve the predictions of neutron-induced fission cross section. The nuclear inputs concern not only the details of the energy surface along the fission path, but also the coherent estimate of the nuclear level density derived within the combinatorial approach on the basis of the same single-particle properties, in particular at the fission saddle points. The predictive power of such a microscopic approach is tested. It is also shown that the various inputs can be tuned to reproduce at best experimental data in one unique coherent framework, so that it is now possible to make reliable and accurate fission cross-section calculations on the basis of microscopic models, but also to use such approaches to estimate the corresponding modeling uncertainties for nuclei, energy ranges or reaction channels for which no data exist.
    Results from the IAEA benchmark of spallation models
    [Abstract]
    S. Leray, J.C. David, M. Khandaker, G. Mank, A. Mengoni, N. Otsuka, D. Filges, F. Gallmeier, A. Konobeyev, R. Michel, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 791-796.
    doi:10.3938/jkps.59.791
    Abstract
    Spallation reactions play an important role in a wide domain of applications. In the simulation codes used in this field, the nuclear interaction cross-sections and characteristics are computed by spallation models. The International Atomic Energy Agency (IAEA) has recently organised a benchmark of the spallation models used or that could be used in the future into high-energy transport codes. The objectives were, first, to assess the prediction capabilities of the different spallation models for the different mass and energy regions and the different exit channels and, second, to understand the reason for the success or deficiency of the models. Results of the benchmark concerning both the analysis of the prediction capabilities of the models and the first conclusions on the physics of spallation models are presented.
    The role of nuclear data for fusion technology studies
    [Abstract]
    R.A. Forrest, Procs. Int. Conf. Nuclear Energy for New Europe 2010, 6-9 September 2010, Portorož, Slovenia, pp. 001.1-001.8, Nucl. Eng. Des. 241 (2011) pp. 4326-4330.
    doi:10.1016/j.nucengdes.2011.08.033
    Abstract
    Nuclear data are of fundamental importance in studies of nuclear technology. In these studies, experiments to measure cross sections and decay properties and simulations of the design of fission power plants, fusion devices and accelerators are included. The large amount of data required is stored in computer readable formats in data libraries and the most common of these are the general purpose files used for neutronics or transport calculations. These files also contain the standards against which most measurements are made. The other class of libraries are the special purpose ones containing decay data, fission yields and cross section data for dosimetry and activation. This paper gives examples of what data are available and describes their use for various fusion applications. The focus will be on neutron-induced activation data with examples of how the reactions of particular importance can be identified. All data should be accompanied by estimates of the uncertainty. This is best achieved by including covariance data; however, this is extremely challenging and only a subset of the available data has such uncertainty data. The general principles of how covariance matrices are used are outlined.
    Experimental data for nuclear resonance fluorescence
    [Abstract]
    S.P. Simakov, N. Otsuka, V. Semkova, V. Zerkin, S. Hlavac, Procs. 52nd Annual Meeting of the Institute of Nuclear Materials Management (INMM), 17-21 July 2011, Palm Desert, U.S.A.
    Abstract
    The paper reports on compilation of all published NRF data for actinides in the EXFOR database. The Entries contain detailed information on experimental set-up and measured quantities. The survey of compiled data has indicated the relatively large uncertainties and discrepancies between different experiments even for the most intensive transitions.
    Analysis of the dosimetry cross sections measurements up to 35 MeV with a 7Li(p,xn) quasi-monoenergetic neutron source
    [Abstract]
    S.P. Simakov, P. Bám, V. Burjan, U. Fischer, R.A. Forrest, M. Götz, M. Honusek, V. Kroha, J. Novak, E. Šimečková, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1856-1859.
    doi:10.3938/jkps.59.1856
    Abstract
    To improve the status of the dosimetry reaction data above 20 MeV, the activation cross sections on Bi, Au, Co and Nb have been measured at the NPI/Řež cyclotron facility with a quasi-monoenergetic p-7Li neutron source. The present work comprises the computational analysis of this experiment. It includes the Monte-Carlo simulation of the experimental set-up with the MCNPX code and relevant cross section data for proton and neutron induced reactions to predict the energy differential neutron flux in the irradiated foils. This approach has been validated against p-Li neutron spectra measured by different techniques. By making use of the modified unfolding code SAND-II, the dosimetry cross sections have been derived from the detected γ-ray activities. This has brought the new experimental results in the neutron energy domain between 18 and 35 MeV with estimated uncertainty at the level of 10%. They were used for validation of the activation (EAF, IEAF, IRDF) and the general purpose (ENDF) cross section files.
    On low and medium energy deuteron-induced reactions on 63,65Cu
    [Abstract]
    E. Šimecková, P. P. Bém, M. Honusek, L. Závorka, U. Fischer, S.P. Simakov, R.A. Forrest, M. Avrigeanu, V. Avrigeanu, F.L. Roman, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1928-1931.
    doi:10.3938/jkps.59.1928
    Abstract
    The activation cross sections of (d,p), (d,2n), (d,3n), and (d,2p) reactions on 63,65Cu were measured in the energy range from 4 to 20 MeV using the stacked-foils technique. Errors of present experimental cross section data are composed of the scale factor (~5%, due to energy and beam current uncertainty) and datum uncertainty of the foil thickness ~2%) and a mean statistical error in the determination of specific activities ~3%). Following a previous extended analysis of elastic-scattering, breakup and direct-reaction of deuterons on light nuclei, for energies from 3 to 60 MeV, the pre-equilibrium and statistical emissions are considered in the same energy range. Finally, all available deuteron-induced reaction cross sections for 63,65Cu have been involved within a simultaneous analysis of the deuteron elastic-scattering and reaction data.
    Spectral flux of the p-7Li(C) q-m neutron source measured by proton recoil telescope
    [Abstract]
    J. Novák, P. Bém, U. Fischer, M. Götz, M. Honusek, S.P. Simakov, E. Šimecková, M. Štefa¡nik, Proc. Int. Conf. on Nuclear Data for Science and Technology 2010, J. Korean Physical Soc. 59 Vol. 2 (2011) pp. 1577-1580.
    doi:10.3938/jkps.59.1577
    Abstract
    The cyclotron-based fast neutron source at NPI produces mono-energetic neutron fields up to 35 MeV neutron energy using the p+7Li(carbon backing) reactions. To be applied for activation cross-section measurements, not only the intensity of neutron peak, but also the contribution of low-energy continuum in the spectra must be well determined. Simulations of the spectral flux from present source at a position of irradiated samples were performed using CYRIC TOF-data validated in the present work against LA150h by calculations with the transport Monte Carlo code MCNPX.   Simulated spectra were tested by absolute measurements using a proton-recoil telescope technique. The recoil-proton spectrometer consisted of a shielded scattering chamber with polyethylene and carbon radiators and the ∆E1-∆E2-E telescope of silicon-surface detectors located to the neutron beam axis at 45o in the laboratory system. Si-detectors were handled by usual data acquisition system. Dead-time - and pulse-overlap losses of events were determined from the count rate of pulse generator registered during duty cycle of accelerator operation. The proton beam charge and data were taken in the list mode for later replay and analysis.  The calculations for 7Li(p,n) and 12C(p,n) reactions reasonably reproduce CYRIC TOF neutron source spectra. The influence of neutron source set-up (proton beam dimensions, 7Li-foil, carbon stopper, cooling medium, target support/chamber and the geometry-arrangement of irradiated sample) on the spectral flux is discussed in details.
    Nuclear science and data needs for advanced nuclear systems
    [Abstract]
    R.A. Forrest, Energy Procedia 7 (2011) pp. 540-552.
    doi:10.1016/j.egypro.2011.06.075
    Abstract
    Nuclear data are of fundamental importance in studies of nuclear technology such as the design of fission power plants, fusion devices and accelerators. The large amounts of data required are stored in computer readable formats in data libraries and include the general purpose files used for neutronics calculations. The other class of libraries are special purpose ones containing decay data and cross sections for dosimetry and activation. This paper gives examples of available data and discusses some needs for various applications. The focus is on neutron-induced activation with examples of how the reactions of particular importance can be identified. All data should be accompanied by estimates of uncertainty. The climate of budget cuts worldwide means that the greatest nuclear data need is for resources to continue production of compiled and evaluated data essential for nuclear technology.
    Radiation deep penetration calculations for the IFMIF testcell wall
    [Abstract]
    S.P. Simakov, J. Li, U. Fischer, Fusion Eng. Design 85 (2010) 1924-1927.
    doi:10.1016/j.fusengdes.2010.06.025
    Abstract
    Deep radiation penetration calculations were performed for the IFMIF test cell wall on the basis of two different approaches employing the Monte-Carlo technique and a coupled Monte-Carlo/deterministic computational scheme called MCDO. For the Monte-Carlo calculations, the McDeLicious code was used which is an extension to MCNP-5 with the capability to simulate the d-Li neutron source on the basis of tabulated d-Li cross-section data. Use was made of a three dimensional geometry model of the IFMIF test cell representing in detail its interior and the shielding 3 m thick heavy concrete walls. The interface program MCDO, which couples McDeLicious and the 3D discrete ordinate code TORT, was used to transport the neutrons and photons through the wall and to obtain spatial distributions of the doses in the adjacent rooms. These coupled calculations have revealed hot spots of the radiation doses in the access room neighbouring the test cell in the d-beam downstream direction. The dose rate there exceeds several times the limit of 100 μSv/h for the work personnel.
    Analysis of proton-induced reactions by using simulation
    [Abstract]
    H. Iwamoto, Y. Iwamoto, Y. Hirata, N. Otuka, K. Niita, JAEA-Conf 2010-005 pp. 81-86.
    Abstract
    Energy spectrum of proton, neutron, composite particles (deuteron, triton, 3He, 4He)for p(175 MeV) + 58Ni and p(62.9 MeV) + 208Pb reactions are analyzed by using the Bertini and ISOBAR models implemented in PHITS and the INC-FRG model.
    Development of Web-based user interface for evaluated covariance data files
    [Abstract]
    T. Togashi, K. Kato, R. Suzuki, N. Otuka, JAEA-Conf. 2010-005, pp. 69-74.
    Abstract
    We develop a web-based interface which visualizes cross sections with their covariance compiled in the ENDF format in order to support evaluated covariance data users who do not have experience of NJOY calculation. A package of programs has been constructed without aid of any existing program libraries.
    Study of neutron-induced fission cross sections of U, Am, and Cm at n_TOF
    [Abstract]
    P.M. Milazzo, R. Capote, et al., (the n_TOF Collaboration), Procs. VIII Latin American Symposium on Nuclear Physics and Applications, Eds. R. Alcaron, H.F. Arellano, P.L. Cole, A.J. Kreiner, AIP Conf. Procs. 1265 (2010) pp. 477-482.
    doi:10.1063/1.3480244
    Abstract
    Neutron induced fission cross sections of several isotopes have been measured at the CERN n_TOF spallation neutron facility. Between them some measurements involve isotopes (233U, 241Am, 243Am, 245Cm) relevant for applications to nuclear technologies. The n_TOF facility delivers neutrons with high instantaneous flux and in a wide energy range, from thermal up to 250 MeV. The experimental apparatus consists of an ionization chamber that discriminates fission fragments and α particles coming from natural radioactivity of the samples. All the measurements were performed referring to the standard cross section of 235U.
    Astrophysics at n_TOF facility
    [Abstract]
    G. Tagliente, R. Capote, et al., (the n_TOF Collaboration), Procs. VIII Latin American Symposium on Nuclear Physics and Applications, Eds. R. Alcaron, H.F. Arellano, P.L. Cole, A.J. Kreiner, AIP Conf. Procs. 1265 (2010) pp. 160-165.
    doi:10.1088/1742-6596/312/4/042024
    Abstract
    The neutron time of flight (n_TOF) facility at CERN is a spallation neutron source with white neutron energy spectrum (from thermal to several GeV), covering the full energy range of interest for nuclear astrophysics, in particular for measurements of the neutron capture cross section required in s-process nucleosynthesis. This contribution presents an overview on the astrophysical program carried on at the n_TOF facility, the main results and their implications.
    Elastic Scattering of 7Li + 27Al at Several Angles in the 7 - 11 MeV Energy Range
    [Abstract]
    D. Abriola, et. al. 19th Int. Conf. on Ion Beam Analysis, 7-11 September 2009, Nucl. Instr. Meth. Phys. Res. B268 (2010) pp. 1793-1796.
    doi:10.1063/1.3480140
    Abstract
    We have measured elastic excitation functions for the 7Li + 27Al system, in an energy range close to its Coulomb barrier (Elab = 8.4 MeV) in steps of 0.25 MeV. For this purpose, an array of eight surface-barrier detectors was used. To get an insight on the background composition (mainly α particles), a telescope-detector was used for atomic-number identification. Identical measurements for the 6Li + 27Al system are planned for the near future.
    Radiative recombination rate coefficients for highly-charged tungsten ions
    [Abstract]
    M.B. Trzhaskovskayaa, V.K. Nikulin, R.E.H. Clark, Atomic Data and Nuclear Data Tables 96 (2010) 1-25.
    doi:10.1016/j.adt.2009.08.004
    Abstract
    Partial and total radiative recombination rate coefficients are presented for highly-charged ions of tungsten with closed shells, W28+, W38+, W46+, W56+, W64+, W70+, and W72+, as well as for the H-like ion W73+ and the bare nucleus W74+. The temperature range 103–1010K is considered. Calculations have been performed in the framework of the fully relativistic Dirac–Fock treatment of photoionization and radiative recombination processes taking into account all significant multipoles of the radiation field. We assess the influence of multipole effects on recombination rate coefficients as compared with the commonly used dipole approximation. For the first time, we show that the relativistic Maxwell–Boltzmann distribution of continuum electrons should be used at high temperature. This decreases the rate coefficient significantly compared to the nonrelativistic distribution.
    Measurements of emission spectra from hot, dense germanium plasma in short pulse laser experiments
    [Abstract]
    D.J. Hoarty, S.F. James, C.R.D. Brown, B.M. Williams, H.-K. Chung, J.W.O. Harris, L. Upcraft, B.J.B. Crowley, C.C. Smith, R.W. Lee, High Energy Density Physics 6 (2010) pp.105-108.
    doi:10.1016/j.hedp.2009.05.019
    Abstract
    Heating of thin foil targets by an high power laser at intensities of 1017–1019 W/cm2 has been studied as a method for producing high temperature, high density samples to investigate X-ray opacity and equation of state. The targets were plastic (parylene-N) foils with a microdot made of a mixture of germanium and titanium buried at depth of 1.5 mm. The L-shell spectra from the germanium and theK-shell spectra from the titanium were taken using crystal spectrometers recording onto film and an ultra fast X-ray streak camera coupled to a conical focussing crystal with a time resolution of 1 ps. The conditions in the microdot were inferred by comparing the measured spectra to synthetic spectra produced by the time-dependent collisional– radiative (CR) models FLY and FLYCHK. The data were also compared to simulated spectra from a number of opacity codes assuming local thermodynamic equilibrium (LTE). Temperature and density gradients were taken into account in the comparisons. The sample conditions were inferred from the CR modelling using FLYCHK to be 800  100 eV and 1.5  0.5 g/cc. The best fit to the LTE models was at a temperature 20% lower than with the CR model. Though the sample departs from LTE significantly useful spectral comparisons can still be made. The results and comparisons are discussed along with improvements to the experimental technique to achieve conditions closer to LTE.
    ERRORF - A code to calculate covariance of self-shielding factor and its temperature gradient
    [Abstract]
    N. Otuka, A. Zukeran, H. Takano, G. Chiba, M. Ishikawa, JAEA-Data/Code 2008-012, Japan Atomic Energy Agency, June 2008.
    Abstract
    A computer code, ERRORF, was developed for calculation of covariance of self-shielding factor and its temperature gradient. This code is based on several modules. With this code, covariance of self-shielding factor and its temperature gradient can be calculated from evaluated nuclear library in the ENDF format.
    Covarancies of resonance self-shielding factor and its temperature gradient for uncertainty evaluation of Doppler reactivity
    [Abstract]
    A. Zukeran, G. Chiba, N. Otuka, M. Ishikawa, H. Takano, JAEA-Research 2008-091, Japan Atomic Energy Agency, February 2009.
    Abstract
    Uncertainty of Doppler reactivity is theoretically formulated and then uncertainties of self-shielding factor and its temperature gradient due to errors of resonance parameters were evaluated from NJOY output. Sensitivity analysis was made for 235U, 238U, 239Pu and 240Pu of JENDL-3.3 based on JFS-3 70 group structure. Resultant sensitivity coefficients are provided for the uncertainty evaluation of Doppler reactivity.
    Neutron-induced activation cross sections on hafnium isotopes from the threshold to 20 MeV
    [Abstract]
    V. Semkova, R. J. Tornin, N. Janeva, N. Koyumdjieva, A. Moens, A.J.M. Plompen, K. Volev, Procs. of Scientific Workshop on Neutron Measurements, Theory and Applications Nuclear Data for Sustainable Nuclear Energy, 28-30 April 2009, Geel, Belgium, Ed. F. J. Hambsch, JRC Scientific and Technical Reports, EUR 23883 EN-2010, pp. 155-159, ISBN 978-92-79-11705-3, ISSN 1018-5593.
    Abstract
    Here in we report on 174Hf(n,2n)173Hf, 176Hf(n,2n)175Hf, 177Hf(n,3n)175Hf, 177Hf(n,p)177gLu, 178Hf(n,x)177gLu reaction cross section measurements using the activation technique. The irradiations were carried out at the 7-MV Van de Graaff accelerator at IRMM, Geel. Quasi-monoenergetic neutrons with energies between 14.8 and 20.5 MeV were produced via the 3H(d,n)4He reaction at Ed = 1, 1.4, 2, 3, and 4 MeV. Both natural and samples enriched in 177Hf and 178Hf were used to account for the interference between reactions leading to the same product. The radioactivity of the samples was determined by gamma-ray spectrometry using a HPGe detector. The current measurements are compared with the data from other authors and evaluated nuclear data files. Cross sections for three of the studied reactions are reported for the first time.
    Nuclear Data Sheets for A = 72
    [Abstract]
    D. Abriola and A.A. Sonzogni, Nuclear Data Sheets 111 (2010) 1-140
    doi:10.1016/j.nds.2009.12.001
    Abstract
    Experimental data on ground– and excited–state properties for all known nuclei with mass number A=72 have been compiled and evaluated. States populated in radioactive decay, as well as in nuclear reactions, have been considered. For these nuclei, level and decay schemes, as well as tables of nuclear properties, are given. This work supersedes the 1994 evaluation by W.–T. Chow and M.M. King (1994Ch45).
    Cyclotron production of the 105,106mAg, 100,101Pd, 100,101m,105Rh radionucldies by natPd(p,x) nuclear processes
    [Abstract]
    M.U. Khandaker, K. Kim, G. Kim, N. Otuka, Nucl. Instr. Meth. Phys. Res. B 268 (2010) pp. 2303-2311.
    doi:10.1016/j.nimb.2010.04.002
    Abstract
    Production cross-sections of the 105g+m,106mAg, 100,101Pd, and 100g+m,101m,105g+mRh radionuclides through proton-induced reactions on natural palladium were measured up to 40 MeV by using a stacked-foil activation technique combined with high-resolution c-ray spectrometry. The production cross-sections of 101Pd and 100g+m,105g+mRh radionuclides have been reported here for the first time from the natPd(p,x) nuclear processes. The present results are compared with the available literature values as well as the theoretical data calculated by the TALYS and the ALICE-IPPE computer codes. A quantitative comparison of the present results with the theoretical data has also been done with several deviation factor definitions. Optimal production pathways of the therapeutic 105gRh radionuclide with minimal contamination using cyclotrons are discussed elaborately.
    The 235U(n,f) prompt fission neutron spectrum at 100 K input neutron energy N. Kornilov, F.-J. Hambsch, I. Fabry, S. Oberstedt, T. Belgya, Z. Kis, L. Szentmiklosi, S. Simakov, Nucl. Sci. Eng. 165 (2010) pp.117-127.
    Neutron activation cross sections for zirconium isotopes
    [Abstract]
    V. Semkova, E. Bauge, A.J.M. Plompen, D.L. Smith, Nucl. Phys. A832 (2010) pp.149 169.
    doi:10.1016/j.nuclphysa.2009.10.133
    Abstract
    New experimental cross sections are presented for 90Zr(n,α)87mSr, 90Zr(n,x)89mY, 90Zr(n,p)90mY, 90Zr(n,2n)89Zr, 90Zr(n,2n)89mZr, 91Zr(n,nα)87mSr, 91Zr(n,x)90mY, 91Zr(n,p)91mY, 92Zr(n,x)91mY, 92Zr(n,p)92Y, 94Zr(n,alpha)91Sr, 94Zr(n,x)93Y and 94Zr(n,p)94Y reactions. These have been obtained with the activation technique using gamma-ray spectrometry and irradiations at the IRMM Van de Graaff laboratory. The new data were obtained in the energy range from 14 to 21 MeV. In nearly all cases this work provides the first data above 15 MeV and for the 92Zr(n,x)91mY and 91Zr(n,nalpha)87mSr reactions no earlier data were reported. The experimental results are compared with model calculations using the TALYS code to obtain a first indication of the impact of the new data on modeling of n +Zr reactions.
    High resolution measurements of the 241Am(n,2n) reaction cross section
    [Abstract]
    C. Sage, V. Semkova, O. Bouland, P. Dessagne, A. Fernandez, F. Gunsing, C. Nästren, G. Noguère, H. Ottmar, A.J.M. Plompen, P. Romain, G. Rudolf, J. Somers, F. Wastin, Phys. Rev. C81 (2010) 064604.
    doi:10.1103/PhysRevC.81.064604
    Abstract
    Measurements of the 241Am(n,2n) reaction cross section have been performed at the Joint Research Centre (JRC) Geel in the frame of a collaboration between the European Commission (EC) JRC and French laboratories from CNRS and the Commissariat `a L’Energie Atomique (CEA) Cadarache. Raw material coming from the Atalante facility of CEA Marcoule has been transformed by JRC Karlsruhe into suitable 241AmO2 samples embedded in Al2O3 matrices specifically designed for these measurements. The irradiations were carried out at the 7-MV Van de Graaff accelerator. The 241Am(n,2n) reaction cross section was determined relative to the 27Al(n,alpha)24Na standard cross section. The measurements were performed in four sessions, using quasi-monoenergetic neutrons with energies ranging from 8 to 21 MeV produced via the 2H(d,n)3He and the 3H(d,n)4He reactions. The induced activity was measured by standard gamma-ray spectrometry using a high-purity germanium detector. Below 15 MeV, the present results are in agreement with data obtained earlier. Above 15 MeV, these measurements allowed the experimental investigation of the 241Am(n,2n) reaction cross section for the first time. The present data are in good agreement with predictions obtained with the TALYS code that uses an optical and fission model developed at CEA.
    Neutron physics of the Re/Os clock. I. Measurement of the (n,?) cross sections of 186,187,188Os at the CERN n_TOF facility M. Mosconi, A. Mengoni, R. Capote, et al., (the n_TOF Collaboration), Phys. Rev. C82(2010) 015802.

    Neutron physics of the Re/Os clock. II. The (n,n?) cross section of 187Os at 30 keV neutron energy M. Mosconi, M. Heil, F. Käppeler, R. Plag. A. Mengoni, Phys. Rev. C82 (2010) 015803.

    Neutron physics of the Re/Os clock. III. Resonance analyses and stellar (n,?) cross sections of 186,187,188Os A. Mengoni, R. Capote, et al., (the n_TOF Collaboration), Phys. Rev. C82(2010)015804.

    IFMIF test facilities - 3 years of EVEDA F. Arbeiter, U. Fischer, P. Garin, R. Heidinger, V. Heinzel, A. Klix, A. Möslang, St. Simakov, K. Tian, P. Vladimirov, Jahrestagung Kerntechnik (Berlin 2010): INFORUM GmbH, 2010, compact 810.

    Comparative study of the tungsten irradiation conditions in IFMIF and DEMO S.P. Simakov, P. Pereslavtsev, U. Fischer, A. Möslang, Jahrestagung Kerntechnik (Berlin 2010): INFORUM GmbH, 2010, compact 811.

    Assessment of the tritium production in the HFTM specimen cells of IFMIF A. Klix, U. Fischer, S.P. Simakov, IEEE Transactions on Plasma Science (2010) 38 pp. 259 264.

    Modelling d-Be and d-C neutron sources for SPIRAL-2 Majerle, S.P. Simakov, Jahrestagung Kerntechnik (Berlin 2010): INFORUM GmbH, 2010, compact 812.

    Measurements of X- and γ-ray emission probabilities in the β- decay of 233Pa F.G. Kondev, I. Ahmad, J.P. Greene, M.A. Kellett, A.L. Nichols, Appl. Radiat. Isot. 68 (2010) pp. 2382-2386.

    Nuclear data evaluation methodology including estimates of covariances R. Capote, D.L. Smith, A. Trkov, EPJ Web of Conferences 8 (2010) 04001.

    Nuclear reaction data file for astrophysics (NRDF/A) in Hokkaido University Nuclear Reaction Data Center
    [Abstract]
    K. Kato, M. Kimura, N. Furutachi, T. Togashi, A. Makinaga, N. Otuka, Procs. Tours Symp. Nuclear Physics and Astrophysics - VII, Kobe, Japan, 16-20 November 2009, AIP Conf. Proc. 1238 (2010) pp. 199-204.
    doi:10.1063/1.3455928
    Abstract
    The activities of the Japan Nuclear Reaction Data Centre is explained. The main task of the centre is data compilation of Japanese nuclear reaction data in collaboration of the International Network of Nuclear Reaction Data Centres. As one of recent activities, preparation of a new database (NRDF∕A) and evaluation of astronuclear reaction data are reported. Collaboration in the nuclear data activities among Asian countries is proposed.
    High temperature, high density opacity measurements using short pulse lasers D.J. Hoarty, S.F. James, C.R.D. Brown, B.M. Williams, T. Guymer, M. Hill, J. Morton, D. Chapman, R. Shepherd, J. Dunn, G. Brown, M. Schneider, P. Beiersdorfer, H. K. Chung, J.W.O. Harris, L .Upcraft, C.C. Smith, R.W. Lee, J. Physics: Conference Series 244 (2010) 012002.

    Depression of reactivity by the collision energy in the single barrier H+CD4 -> HD+CD3 reaction Weiqing Zhang, Yong Zhou, Guorong Wu, Yunpeng Lu, Huilin Pan, Bina Fu, Quan Shuai, Lan Liu, Shu Liu, Liling Zhang, Bo Jiang, Dongxu Dai, Soo-Ying Lee, Zhen Xie, B.J. Braams, J.M. Bowman, M.A. Collins, Dong H. Zhang, Xueming Yang, Procs. Nat. Acad. Sci., 107 29 (2010) pp.12782-12785.

    Evidence for vinylidene production in the photodissociation of the allyl radical Chao Chen, B. Braams, D.Y. Lee, J.M. Bowman, P.L. Houston, D. Stranges, Phys. Chem. Letters, 1 12 (2010) pp.1875-1880.

    Ab-Initio-based potential energy surfaces for complex molecules and molecular complexes J.M. Bowman, B.J. Braams, S. Carter, C. Chen, G. Czako?, B. Fu, X. Huang, E. Kamarchik, A.R. Sharma, B.C. Shepler, Y. Wang, Z. Xie, Phys. Chem. Letters 1 12 (2010) pp. 1866-1874.

    Shared-proton mode lights up the infrared spectrum of fluxional cations H5+ and D5+ T.C. Cheng, B. Bandyopadyay, Yimin Wang, S. Carter, B.J. Braams, J.M. Bowman, M.A. Duncan, Phys. Chem. Letters 1 4 (2010) pp.758-762.

    Global potential energy surfaces for O(3P) + H2O(1A1) collisions P.F. Conforti, M. Braunstein, B.J. Braams, J. M. Bowman, Chem. Phys. 133 16 (2010) 164312.

    197Au(n,?) cross section in the resonance region C. Massimi, R. Capote, A. Mengoni, et al., (the n_TOF Collaboration), Phys. Rev. C81 (2010) 044616.

    The 92Zr(n,?) reaction and its implications for stellar nucleosynthesis G. Tagliente, R. Capote, A. Mengoni, et al., (the n_TOF Collaboration), Phys. Rev. C81 (2010) 055801.

    Neutron-induced fission cross section of 234U and 237Np measured at the CERN Neutron Time-of-Flight (n_TOF) facility C.Paradela, R. Capote, A. Mengoni, et al., (the n_TOF Collaboration), Phys. Rev. C82 (2010) 034601.

    Description of analysing power and (p,n) reaction by a global dispersive coupled-channel optical model potential W.L. Sun, L.J. Hao, E.Sh. Soukhovitskii, R. Capote, J.M. Quesada, Nucl. Phys. Trends: The 7th China-Japan Joint Nuclear Physics Symposium, Tsukuba (Japan), 9-13 November 2009, Eds. A. Ozawa, W. Liu, AIP Conf. Procs. 1235, ISBN: 978-0-7354-0780-0.

    Neutron cross-sections for next generation reactors: New data from n_TOF N. Colonna, R. Capote, A. Mengoni, et al., (the n_TOF Collaboration), Appl. Radiat. Isot. 68 (2010) pp. 643-646.

    Spectrum of prompt fission neutrons from 235U(n,F) V.M. Maslov, N.A. Tetereva, V.G. Pronyaev, A.B. Kagalenko, K.I. Zolotarev, R. Capote, T. Granier, B. Morillon, F.-J. Hambsch, J.-C. Sublet, Atomic Energy 108 6 (2010) pp. 432-443.

    Status of the problem of nuclear cross section data for IBA A. Gurbich , I. Bogdanovic-Radovic, M. Chiari , C. Jeynes, M. Kokkoris, O. Schwerer, A.R. Ramos, M. Mayer, E. Rauhala, Shi Liqun, I. Vickridge, J. Nucl. Instrum. Methods Phys. Res. B266 (2008) pp. 1198-1202.

    Measurements of the Zr-90,91,92,93,94,96(n,γ) cross-sections at n_TOF P.M. Milazzo, R. Capote, A. Mengoni,et al., (the n_TOF collaboration), Proc. 2nd Int. Conf., Current Problems in Nuclear Physics and Atomic Energy (NPAE-Kyiv2008), 9-15 June 2009, Kiev, Ukraine, pp.500-503.

    Permutationally invariant potential energy surfaces in high dimensionality B.J. Braams, J.M. Bowman, Int. Reviews in Physical Chemistry 28 (2009) pp. 577-606.

    Full-dimensional ab initio potential energy surface and vibrational configuration interaction calculations for vinyl A.R. Sharma, B.J. Braams, S. Carter, B.C. Shepler, J.M. Bowman, J. Chem. Phys. 130 (2009) 174301.

    Ab initio modeling of molecular IR spectra of astrophysical interest: application to CH4 R. Warmbier, R. Schneider, A.R. Sharma, B.J. Braams, J.M. Bowman, P.H. Hauschildt, J. Astronomy and Astrophysics 495 (2009) pp. 655-661.

    Ab Initio Calculation of the Photoelectron Spectra of the Hydroxycarbene Diradicals L. Koziol, V.A. Mozhayskiy, B.J. Braams, J.M. Bowman, A.I. Krylov, J. Phys. Chem. A113 (2009) pp. 7802-7809.

    Applications of NLTE population kinetics H.-K. Chung, R.W. Lee, J. High Energy Density Physics 5 (2009) pp. 1-14.

    X-ray spectroscopy of buried layer foils irradiated at laser intensities in excess of 1020 W/cm2 S.N. Chen, P.K. Patel, H.-K. Chung, A.J. Kemp, S. Le Pape, B.R. Maddox, S.C. Wilks, R.B. Stephens, F.N. Beg, J. Phys. Plasmas 16 (2009) 062701.

    Multi-Code Ab Initio Calculation of Ionization Distributions and Radiation Losses for Tungsten in Tokamak Plasmas Yu. Ralchenko, J. Abdallah, Jr., A. Bar-Shalom, J. Bauche, C. Bauche-Arnoult, C. Bowen, H.-K. Chung, J. Colgan, G. Faussurier, C.J. Fontes, M. Foster, F. de Gaufridy de Dortar, I. Golovkin, S.B. Hansen, R.W. Lee, V. Novikov, J. Oreg, O. Peyrusse, M. Poirier, A. Sasaki, H. Scott, H.L. Zhang, AIP Conf. Proc.–Atomic Processes in Plasmas: Procs. of 16th Int. Conf. on Atomic Processes in Plasmas, Ed. K.B. Fournier, 1161 (2009) pp. 242-250, AIP, Melville, New York, ISBN: 978-0-7354-0661-2.

    Radiative recombination and photoionization cross sections for heavy element impurities in plasmas: II. Ions of Si, Cl, Ar, Ti, Cr, Kr, and Xe M.B. Trzhaskovskayaa, V.K. Nikulin, R.E.H. Clark, Atomic Data and Nuclear Data Tables 95 (2009) pp. 987-1050.

    Development of new standards for exchange of atomic and molecular data Yu. Ralchenko, R.E.H. Clark, M.-L. Dubernet, S. Gagarin, D. Humbert, P.A. Loboda, N. Moreau, E. Roueff, D.R. Schultz, AIP Conf. Proc. - ICAMDATA-2008: 6th Int. Conf. on Molecular Data and Their Applications, Eds. Shaoping Zhu, Jun Yan, 1125 (2009) pp. 207-216, AIP, Melville, New York, ISBN: 978-0-7354-0661-2.

    Atomic, Molecular and Plasma-Surface Interaction Data for Fusion Energy Research R.E.H. Clark, D. Humbert, AIP Conf. Proc. - ICAMDATA-2008: 6th Int. Conf. on Molecular Data and Their Applications, Eds. Shaoping Zhu, Jun Yan, 1125 (2009) pp. 197 206, AIP, Melville, New York, ISBN: 978-0-7354-0661-2.

    Recent advances on hydrogenic retention in ITER's plasma-facing materials: Beryllium, Carbon, and Tungsten C.H. Skinner, A.A. Haasz, V.Kh. Alimov, N. Bekris, R.A. Causey, R.E.H. Clark, J.P. Coad, J.W. Davis, R.P. Doerner, M. Mayer, A. Pisarev, J. Roth, T. Tanabe, J. Fusion Science and Technology 54 (2008) pp. 891-945.

    n_TOF Experiment: Past, Present and Future S. Marrone, R. Capote, A. Mengoni, (the n_TOF Collaboration), AIP Conf. Proc. - Nuclear Physics and Applications: 1st Ulaanbaatar Conf. on Nuclear Physics and Applications, Eds. D. Dashdorj, U. Agvaanluvsan, G.E. Mitchell, 1109 (2009) pp. 78-83, AIP, Melville, New York, ISBN: 978-0-7354-0646-9.

    The n_TOF Total Absorption Calorimeter for neutron capture measurements at CERN C. Guerrero. R. Capote, et. al., (the n_TOF Collaboration), J. Nucl. Instr. Meth. Physics Research, Section A:Accelerators, spectrometers, detectors and associated equipment, 608 (2009) pp. 424-433.

    High-accuracy U-233(n, f) cross-section measurement at the white-neutron source n_TOF from near-thermal to 1 MeV neutron energy M. Calviani, R. Capote, et. al., Phys. Rev. C80 (2009) 044064.

    Evaluation and use of the prompt fission neutron spectrum and spectra covariance matrices in criticality and shielding
    [Abstract]
    I. Kodeli, A. Trkov, R. Capote, Y. Nagaya, V. Maslov, J. Nucl. Instr. Meth. Physics Research, Section A:Accelerators, spectrometers, detectors and associated equipment 610 (2009) pp. 540-552.


    doi:10.1016/j.nima.2009.08.076
    Abstract
    The prompt fission neutron spectra covariance matrices of 235U, 238U and 239Pu were evaluated using the Monte Carlo method for two empirical spectra formulations, Watt and Kornilov, and compared to the existing evaluations such as JENDL-3.3. The fission spectra, together with the covariance matrices and the methods for the calculation of the corresponding sensitivity profiles were validated on several applications, including shielding (VENUS-3 benchmark, pressure vessel dosimetry) as well as on fast and thermal reactor systems (KRITZ and SNEAK critical experiments). A new set of parameters for a Kornilov model is proposed that improve both benchmark performance and the agreement with recently measured differential spectra. A recommendation to use constrained sensitivity coefficients was confirmed for the case of the fission spectrum induced uncertainty in the effective multiplication factor ðkeff Þ and in the detector responses, in order to assure the proper normalisation of the corresponding covariance matrices.
    The determination of beam quality correction factors: Monte Carlo simulations and measurements D.M. Gonzalez-Castano, G.H. Hartmann, F, Sanchez-Doblado, F. Gomez, R.P. Kapsch, J. Pena, R. Capote, Physics in Medicine and Biology 54 (2009) pp. 4723-4741.

    Cross sections of the reaction Pa-231(d,3n)U-230 for the production of U-230/Th-226 for targeted alpha therapy A. Morgenstern, O. Lebeda, J. Stursa, R. Capote, M. Sin, F. Bruchertseifer, B. Zielinska, C. Apostolidis, Phys. Rev. C80 (2009) 054612.

    Nuclear Data Sheets for A = 84 D. Abriola, et. al., Nucl. Data Sheets, 110 (2009) pp. 2815-2944.

    RIPL – Reference Input Parameter Library for calculation of nuclear reactions and nuclear data evaluations R. Capote Noy, et. al., Nucl. Data Sheets, 110 (2009) pp. 3108-3214.

    The JEFF-3.1/-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries M.A. Kellett, O. Bersillon, R.W. Mills, OECD Data Bank 2009 - JEFF Report 20, ISBN 978-92-64-99087-6, NEA no. 6287.

    Current status of Nuclear reaction Data File for Astrophysics (NRDF/A)
    [Abstract]
    T. Yoshida, N. furutachi, M. Kimura, M. Asano. T. Togashi, H. Murakami, K. Kato, N Otuka, published in proceedings of the 2008 Annual Symposium on Nuclear Data, 20 - 21 November 2008, Ricotti, Tokai, Japan, (JAEA-Conf 2009-004) pp. 79-82.
    Abstract
    Recent activities in JCPRG for compilations of EXFOR and Nuclear Reaction Data File (NRDF) have been introduced. As an extension of such activities, a preparation of new nuclear data libraries: Nuclear Reaction Data File for Astrophysics (NRDF/A) has been planned. The framework of the data table has been almost built. As the next step, evaluations by using cluster models have been planned.
    A Dispersive, Lane-consistent Optical Potential, Coupled-channel Optical Model Code OPTMAN and its Application E.Sh. Soukhovitski, S. Chiba, R. Capote, J.M. Quesada, published in proceedings of the 2008 Annual Symposium on Nuclear Data, 20 - 21 November 2008, Ricotti, Tokai, Japan, (JAEA-Conf 2009-004) pp. 51-57.

    Low and medium energy deuteron-induced reactions on Al-27
    [Abstract]
    R. Bem, E. Simeckova, M. Honusek, U. Fischer, S.P. Simakov, R.A. Forrest, M. Avrigeanu, A.C. Obreja, F.L. Roman, V. Avrigeanu, Phys. Rev. C79 (2009) 044610.


    doi:10.1103/PhysRevC.79.044610
    Abstract
    The activation cross sections of (d,p), (d,2p), and (d,p) reactions on 27Al were measured in the energy range from 4 to 20 MeV using the stacked-foils technique. Following a previous extended analysis of elastic scattering, breakup, and direct reaction of deuterons on 27Al, for energies from 3 to 60 MeV, the preequilibrium and statistical emissions are considered in the same energy range. Finally, all deuteron-induced reactions on 27Al including the present data measured up to 20 MeV deuteron energy are properly described due to a simultaneous analysis of the elastic scattering and reaction data.
    Deformation-dependent Tamura-Udagawa-Lenske multistep direct model H. Wienke, R. Capote, M. Herman, M. Sin, Phys. Rev. C78 (2008) 064611.

    Towards a prediction of fission cross sections on the basis of microscopic nuclear inputs S. Goriely, S. Hilaire, A.J. Koning, M. Sin, R. Capote, Phys. Rev. C79 (2009) 024612.

    Multipole and relativistic effects in radiative recombination process in hot plasmas M.B. Trzhaskovskaya, V.K. Nikulin, R.E.H. Clark, Phys. Rev. E78 (2008) 035401.

    Radiative Recombination and Photoionization Cross Sections for Heavy Element Impurities in Plasmas M.B. Trzhaskovskaya, V.K. Nikulin, R.E.H. Clark, Atomic Data and Nucl. Data Tables 94 (2008) pp.71-139.

    Nuclear Data Sheets for A=96 D. Abriola and A.A. Sonzogni, Nucl. Data Sheets 109 (2008) pp.2501-2655.

    JENDL Actinoid File 2008
    [Abstract]
    O. Iwamoto, T. Nakagawa, N. Otuka, S. Chiba, K. Okumura, G. Chiba, T. Ohsawa, K. Furutaka, J. Nucl. Sci. Technol. 46 (2009) pp. 510-528.
    doi:10.3327/jnst.46.510
    Abstract
    JENDL Actinoid File 2008 (JENDL/AC-2008) was released in March 2008. It includes nuclear data for neutron-induced reactions for 79 nuclides from Ac (Z=89) to Fm (Z=100). The neutron energy range is 10−5 eV to 20 MeV. Almost all data for 62 actinoids in JENDL-3.3 were revised. New evaluations were performed for 17 nuclides, which have half-lives longer than one day. A new comprehensive theoretical model code CCONE was widely used for the evaluation of cross sections and neutron emission spectra. Thermal cross sections for many nuclides were revised based on experimental data. Resonance parameters were readjusted to reproduce them. Simultaneous evaluations of fission cross sections were performed for six important nuclei. The least-squares fitting code GMA was used for the evaluation of fission cross sections for minor actinoids. In this paper, we present the evaluation methods and results of the JENDL/AC-2008.
    Neutron capture cross section of C-14 of astrophysical interest studied by Coulomb breakup of C-15 T. Nakamura, N. Fukuda, N. Aoi, N. Imai, M. Ishihara, H. Iwasaki, T. Kobayashi, T. Kubo, A. Mengoni, T. Motobayashi, M. Notani, H. Otsu, H. Sakurai, S. Shimoura, T. Teranishi, Y. X. Watanabe, and K. Yoneda, Phys. Rev. C79 (2009) 035805.

    JENDL Actinoid File 2008 and Plan of Covariance Evaluation
    [Abstract]
    O. Iwamoto, T. Nakagawa, N. Otuka, S. Chiba, K. Okumura, Nucl. Data Sheets 109 (2008) pp. 2885-2889.
    doi:10.1016/j.nds.2008.11.028
    Abstract
    JENDL Actinoid File 2008 (JENDL/AC-2008), which is one of JENDL special purpose files, was released in March 2008. It provides nuclear data for neutron induced nuclear reactions for actinoid nuclides from Ac (Z=89) to Fm (Z=100). The data for 62 nuclides in JENDL-3.3 were revised and newly evaluated data were added for 17 nuclides that have a half-life longer than 1 day. The energy range of incident neutrons is from 10−5 eV to 20 MeV. The nuclear reaction model code CCONE was widely used for the evaluation of cross sections and energy-angular distributions of secondary neutrons in the fast energy region. Covariance data for the fission and capture cross sections and the number of neutrons per fission will be evaluated for important nuclides in JENDL/AC-2008. The evaluation methods and the preliminary results of estimated covariances are presented.
    The measurement of the Pb-206(n,γ) cross section and stellar implications C Domingo-Pardo, R Capote, A Mengoni, et al., J. Phys. G: Nucl. Part. Phys. 35 (2008) 014020.

    Neutron capture cross section of Zr-90: Bottleneck in the s-process reaction flow G. Tagliente, R. Capote, A. Mengoni, et al., Phys. Rev. C77 (2008) 035802.

    Experimental study of the Zr-91(n,γ) reaction up to 26 keV G. Tagliente, R. Capote, A. Mengoni, et al., Phys. Rev. C78 (2008) 045804.

    Investigation of new reaction cross-section evaluations in order to update and extend the IRDF-2002 reactor dosimetry library E.M. Zsolnay, H.J. Nolthenius and A.L. Nichols. Presented at 13th Int. Symp. Reactor Dosimetry, 25-30 May 2008, Akersloot, near Alkmaar, the Netherlands; Reactor Dosimetry State of the Art 2008, Proc. 13th Int. Symp., W. Voorbraak, L. Debarberis, P. D’Hondt and J. Wagemans (Eds), World Scientific, Singapore, 2009, ISBN 981-4271-10-1.
    Nuclear Structure activities at the IAEA-NDS D. Abriola, poster presentation at Nuclear Structure Conference 2008, East Lansing, Michigan, USA, 3-6 June 2008.

    An ENDF-6 compatible evaluation for neutron induced reactions of Th-232 in the unresolved resonance region
    [Abstract]
    I. Sirakov, R. Capote, F. Gunsing, P. Schillebeeckx and A. Trkov, Annals Nucl. Energy 35 (2008) pp. 1223-1231.


    doi:10.1016/j.anucene.2007.12.008
    Abstract
    An evaluation for neutron induced reactions of 232Th has been performed in the unresolved resonance region from 4 to 100 keV. A generalized single-level representation compatible with the energy-dependent options of the ENDF-6 format has been used. The average partial cross sections have been expressed in terms of transmission coefficients by applying the Hauser–Feschbach statistical reaction theory including width-fluctuations. The evaluation is based on a combined analysis of experimental average cross section data (including the most recent capture cross section data obtained at the time-of-flight facilities GELINA and n_TOF), and results of dispersive coupled-channel optical model calculations. Experimental data on transmission and self-indication measurements as well as integral benchmark calculations have been used for validation. The evaluation also includes covariance information
    A new formalism for reference dosimetry of small and nonstandard fields R. Alfonso, P. Andreo, R. Capote, M. Saiful Huq, W. Kilby, P. Kjall, T.R Mackie, H. Palmans, K. Rosser, J. Seuntjens, W. Ullrich and S. Vatnitsky, Med Phys. 35 2008, pp. 5179-5186.

    Progress in Evaluated Nuclear Data for Tungsten with Covariances
    [Abstract]
    A. Trkov, R. Capote, I. Kodeli, L. Leal, Proc. PHYSOR 2008: Int. Conf. Physics of Reactors: A Sustainable Resource, Interlaken, Switzerland, 14-19 September 2008, CD-ROM, 2008 (ISBN 978-3-9521409-5-6).

    Abstract
    New evaluations for the tungsten isotopes 180,182,183,184,186W in the neutron energy range up to 150 MeV were produced, including the covariance information. Minor adjustments to the existing resonance parameters were made. Evaluations in the fast energy region were based on nuclear model calculations using the EMPIRE-2.19 code; covariance data were generated with the Monte Carlo technique to produce a prior estimate for the covariance matrix. Experimental data were introduced through the GANDR system. The evaluated files were tested on selected fusion neutronics benchmarks and fast reactor benchmarks. Marked improvement in predicting measured integral parameters was observed, compared to the ENDF/B-VII library
    Evaluation of the covariance matrix of the U-235 neutron induced prompt fission spectrum
    [Abstract]
    I. Kodeli, A. Trkov, R. Capote, Proc. PHYSOR 2008: Int. Conf. Physics of Reactors: A Sustainable Resource, Interlaken, Switzerland, 14-19 September 2008, CD-ROM, 2008 (ISBN 978-3-9521409-5-6).

    Abstract
    The new Monte Carlo (MC) method has been applied to produce the covariance matrix of the prompt fission neutron spectra (PFNS) for 235U neutron induced fission. Parameters of the model describing the PFNS were sampled randomly within the given uncertainty intervals, assuming normal distribution. The covariance matrix for the Watt spectrum generated by the MC method was validated by comparison with the matrix derived analytically. Analytical derivation is appropriate in case of linear dependence of the spectra on the underlying parameters, whereas in the MC approach the extension to more complex models is straightforward: PFNS covariance matrices were obtained both for the Watt model and for the phenomenological parameterization of the fission neutron spectra proposed by Kornilov et al. Derived covariance data were used in the cross section sensitivity and uncertainty analyses of several KRITZ UO2 and MOX critical configurations performed in the scope of the OECD international benchmark exercise. Two different approaches to calculate the sensitivity coefficients of keff relative to the fission spectra were used as a means to check and assure the mathematical correctness of the matrices.
    Decay studies of minor actinide nuclides, and future opportunities for improving the decay data of neutron-rich fission products F.G. Kondev, M.A. Kellett, A.L. Nichols, et al., Proc. PHYSOR 2008: Int. Conf. Physics of Reactors: A Sustainable Resource, Interlaken, Switzerland, 14-19 September 2008, CD-ROM, 2008 (ISBN 978-3-9521409-5-6).

    International efforts to measure, model and evaluate nuclear data for the minor actinides A. Mengoni, R. Capote, M.A. Kellett, A.L. Nichols, Proc. PHYSOR 2008: Int. Conf. Physics of Reactors: A Sustainable Resource, Interlaken, Switzerland, 14-19 September 2008, CD-ROM, 2008 (ISBN 978-3-9521409-5-6).

    Transmission through multi-humped fission barriers with absorption: A recursive approach M. Sin and R. Capote, Phys. Rev. C77 054601 (2008).

    Evaluation of Tungsten Nuclear Reaction Data with Covariances
    [Abstract]
    A. Trkov, R. Capote, I. Kodeli, L. Leal, Nucl. Data Sheets 109 (12) (2008) pp. 2905-2909.

    Abstract
    As a follow-up of the work presented at the ND-2007 conference in Nice, additional fast reactor benchmarks were analyzed. Adjustment to the cross sections in the keV region was necessary. Evaluated neutron cross section data files for 180,182,183,184,186W isotopes were produced. Covariances were generated for all isotopes except 180W. In the resonance range the retro-active method was used. Above the resolved resonance range the covariance prior was generated by the Monte Carlo technique from nuclear model calculations with the Empire-II code. Experimental data were taken into account through the GANDR system using the generalized least-squares technique. Introducing experimental data results in relatively small changes in the cross sections, but greatly constrains the uncertainties. The covariance files are currently undergoing testing.
    Covariances of Prompt Fission Neutron Spectra
    [Abstract]
    I. Kodeli, R. Capote and A. Trkov, Nucl. Data Sheets 109 (12) (2008) pp. 2840-2845.

    Abstract
    Following the outcomes and the recommendations of the Working Party on Evaluation Cooperation (WPEC) SG-26 the impact of the uncertainties and energy correlations in the prompt neutron fission spectra (PFNS) was studied in several critical benchmarks, both thermal and fast. Two different approaches to calculate the sensitivity of keff with respect to the fission neutron spectra, including the new so-called normalized sensitivity method, were used as a means to check and assure the mathematical correctness of the derived fission spectrum covariance matrices. A new Monte Carlo (MC) method has been proposed and applied to produce the covariance matrices of the PFNS for the neutron induced fission on 235U, 238U and 239Pu nuclei. The MC method was validated by comparison with the matrix derived analytically using the so-called File-30 formalism in ENDF terminology. Several sets of covariance matrices of the PFNS of 235U, 238U and 239Pu nuclei were derived from the uncertainties assigned to the model parameters of the Watt and the recently proposed Kornilov PFNS parameterizations.
    An Investigation of the Performance of the Unified Monte Carlo Method of Neutron Cross Section Data Evaluation R. Capote and D.L. Smith, Nucl. Data Sheets 109 (12) (2008) pp. 2768-2773.

    Development of Covariance Capabilities in EMPIRE Code M. Herman, M.T. Pigni, P. Obložinský, S.F. Mughabghab, C.M. Mattoon, R. Capote, Young Sik Cho and A. Trkov, Nucl. Data Sheets, 109 (12) (2008) pp. 2752-2761.

    Measurements of fission cross-sections of actinides at n_TOF N. Colonna, A. Mengoni, et al., published in proceedings CANDIDE workshop, 16-18 October 2007, NEMEA-4 Conference: Neutron Measurements, Evaluations and Applications, Nuclear data needs for Generation-IV and accelerator driven systems, pp. 65-70, Ed: A. Plompen, EUR 23235 EN—2008.

    Nuclear Data Activities at the International Atomic Energy Agency M.A. Kellett, published in book prepared for 50th Anniversary of the Karlsruhe Nuclide Chart, pp. 214-220, European Commission JRC Report, Eds: G. Pfennig, C. Normand, J. Magill, Th. Fanghaenel, EUR 23420 EN - 2008.

    Production of U-230/Th-226 for Targeted Alpha therapy via Proton Irradiation of Pa-231 A. Morgenstern, O. Lebeda, J. Stursa, F. Bruchertseifer, R. Capote, J. McGinley, G. Rasmussen, M. Sin, B. Zielinska and C. Apostolidis, Anal. Chem. 80 (2008) pp. 8763-8770.

    Exploring the reactor heat problem: Study of the beta decay of Tc-104,105 using the TAS technique A. Algora, J.L. Tain, B. Rubio, A.L. Nichols, et al., Eur. Phys. J. Special Topics 150 (2007) pp. 383-384.

    Mass chain evaluations for the evaluated nuclear structure data file (ENSDF) – An urgent appeal for European participation F.G. Kondev, A.L. Nichols and J.K. Tuli (invited paper), Nuclear Physics News, Vol. 17 No. 4, 2007, published on behalf of the Nuclear Physics European Collaboration Committee (NuPECC).

    Cross-sections of the reactions Th-232(p,3n)Pa-230 for production of U-230 for targeted alpha therapy A. Morgenstern, C. Apostolidis, F. Bruchertseifer, R. Capote, T. Gouder, F. Simonelli, M. Sin and K. Abbas, App. Radiat. Isot., 66 (2008) pp. 1275-1280.

    Measurement of the stellar cross sections for the reactions Be-9(n,γ)Be-10 and C-13(n,γ)C-14 via AMS A. Wallner, A. Mengoni et al., J. Phys. G: Nucl. Part. Phys 35 (2008) 014018.164.

    Maintaining the quality and credibility of a large nuclear database through extended multinational initiatives A.L. Nichols, S. Dunaeva, A. Trkov and V. Zerkin, , Proc. 2nd Int. Conf. Current Problems in Nuclear Physics and Atomic Energy (NPAE-Kyiv2008), 9–15 June 2009, Kiev, Ukraine, pp. 28-35.

    Towards predictions of neutron – induced fission cross section S. Goriely, S. Hilaire, A.J. Koning, M. Sin, R. Capote. Presented at 13th International Symposium on Capture Gamma-ray Spectroscopy and Related Topics (CGS-13), 25 – 29 August 2008, Cologne, Germany; Proc. 13th Int. Symp. Capture Gamma-ray Spectroscopy and Related Topics, J. Jolie, A. Zilges, N. Warr and A. Blazhev (Eds), AIP Conference Proceedings Vol. 1090 (2009) 621 - 622, American Institute of Physics, Melville, New York, ISBN 978-0-7354-0623-0.
    Applications of the total absorption technique to reactor decay heat calculations: Study of the beta decay of Tc-102,104,105 A. Algora, D. Jordan, J.L. Tain, B. Rubio, J. Agramunt, A.B. Perez-Cerdan, L. Caballero, E. Nácher, A. Krasznahorkay, M.D. Hunyadi, J. Gulyás, A. Vitéz, M. Czatlós, L. Csige, J. Äystö, H. Penttilä, S. Rinta-Antila, I. Moore, T. Eronen, A. Jokinen, A. Nieminen, J. Hakala, P. Karvonen, A. Kankainen, U. Hager, T. Sonoda, A. Saastamoinen, J. Rissanen, T. Kessler, C. Weber, J. Ronkainen, S. Rahaman, V. Elomaa, K. Burkard, W. Hüller, L. Batist, W. Gelletly, T. Yoshida, A.L. Nichols, A. Sonzogni and K. Peräjärvi (invited paper), presented at 13th International Symposium on Capture Gamma-ray Spectroscopy and Related Topics (CGS-13), 25 – 29 August 2008, Cologne, Germany; Proc. 13th Int. Symp. Capture Gamma-ray Spectroscopy and Related Topics, J. Jolie, A. Zilges, N. Warr and A. Blazhev (Eds), AIP Conference Proceedings Vol. 1090 (2009) pp. 207-214, American Institute of Physics, Melville, New York, ISBN 978-0-7354-0623-0.
    Studies of Nuclear Structure and Decay Data Properties of Actinide Nuclei F.G. Kondev, I. Ahmad, M.P. Carpenter, C. Chiara, J.P. Greene, R.V.F. Janssens, T.L. Khoo, T. Lauritsen, C.J. Lister, E.F. Moore, D. Seweryniak, S. Zhu, S.W. Yates, Z.M. Koening, A.L. Nichols, M.A. Kellett, C.E. Porter and L.K. Felker (invited paper), presented at 13th International Symposium on Capture Gamma-ray Spectroscopy and Related Topics (CGS-13), 25 — 29 August 2008, Cologne, Germany; Proc. 13th Int. Symp. Capture Gamma-ray Spectroscopy and Related Topics, J. Jolie, A. Zilges, N. Warr and A. Blazhev (Eds), AIP Conference Proceedings Vol. 1090 (2009) pp. 199-206, American Institute of Physics, Melville, New York, USA, ISBN 978-0-7354-0623-0.

    Development of JENDL actinoid file
    [Abstract]
    O. Iwamoto, T. Nakagawa, N. Otuka, S. Chiba, K. Okamura, G. Chiba, Proc. PHYSOR 2008: Int. Conf. Physics of Reactors: A Sustainable Resource, Interlaken, Switzerland, 14-19 September 2008, CD-ROM, 2008 (ISBN 978-3-9521409-5-6).

    Abstract
    Nuclear data for neutron induced reactions with actinides from Ac to Fm have been evaluated for JENDL Actinoid File (JENDL/AC). Almost all data in JENDL-3.3 have been updated based on available experimental data and using the newly developed theoretical model code CCONE. Integral benchmark tests for fission reactors are in progress using preliminary versions of JENDL/AC. The JENDL/AC will be released in 2008.
    Nuclear physics of the s process I. Dillmann, C. Domingo Pardo, F. Kaeppeler, A. Mengoni, K. Sonnabend, Pub. Astro. Soc. of Australia, 25 (2008) pp. 18-29; www.publish.csiro.au/journals/pasa

    A global dispersive coupled-channel optical model potential for actinides R. Capote, S. Chiba, E.Sh. Soukhovitskii, J.M. Quesada, E. Bauge, J. Nucl. Sci. Technol. 45 (2008) pp. 333-340.

    Covariance analyses of self-shielding factor and its temperature gradient for Uranium-238 neutron capture reaction
    [Abstract]
    N. Otuka, A. Zukeran, H. Takano, G. Chiba, M. Ishikawa, J. Nucl. Sci. Technol. 45 (2008) pp. 195-210.
    doi:10.3327/jnst.45.195
    Abstract
    Covariances of the self-shielding factor and its temperature gradient for the uranium-238 neutron capture reaction have been evaluated from the resonance parameter covariance matrix and the sensitivity of the self-shielding factor and its temperature gradient to the resonance parameters. The resonance parameters and their covariance matrix for uranium-238 were taken from JENDL-3.3, while the sensitivity coefficients were calculated by varying resonance parameters and temperature. A set of computer code modules has been developed for the calculation of the sensitivity coefficients at numerous resonance levels. The present result shows that the correlation among resonance parameters yields a substantial contribution to the standard deviations of the self-shielding factor and its temperature gradient. In addition to the standard deviations of these quantities, their correlation matrices in the JFS-3 70 group structure are also obtained.
    Nuclear physics for the Re/Os clock M. Mosconi, R. Capote, A. Mengoni, et al., J. Phys. G: Nucl. Part Phys. 35 (2008) 014015.

    Status and outlook of the neutron time-of-flight facility n_TOF at CERN F. Gunsing, R. Capote, A. Mengoni, et al., Nucl. Instrum. Methods Phys. Res. B261 (2007) pp. 925-929.

    Neutron reactions and nuclear cosmo-chronology M. Mosconi, M. Heil, F. Kaeppeler, R. Capote, A. Mengoni, et al., Prog. Part. Nucl. Phys. 59 (2007) pp. 165-173.

    The C-14(n,γ) cross section between 10 keV and 1 MeV R. Reifarth, M. Heil, C. Forssen, U. Besserer, A. Couture, S. Dababneh, L. Dorr, J. Gorres, R.C. Haight, F. Kappeler, A. Mengoni, S. O’Brien, N. Patronis, R. Plag, R.S. Rundberg, M. Wiescher, J.B. Wilhelmy, Phys. Rev. C77 (2008) 015804.

    The n_TOF facility at CERN D. Cano-Ott, R. Capote, A. Mengoni, et al., Proc. 8th Int. Topical Meeting Nucl. Applications and Utilization of Accelerators (ACCAPP '07 2007) pp. 821-826, American Nuclear Society, La Grange Park, USA.

    Measurement of the radiative neutron capture cross section of Pb-206 and its astrophysical implications C. Domingo Pardo, A. Mengoni, et al., (the n_TOF collaboration), Phys. Rev. C76 (2007) 045805.

    Measurement of the neutron induced fission cross section on transuranic (TRU) elements at the n_TOF facility at CERN A. Mengoni, et al. (n_TOF collaboration), presented at VII Latin American Symposium on Nuclear Physics and Applications, published in AIP 978-0-7354-0461-8/07, Eds: R. Alarcon, P.L. Cole C. Djalali and F. Umeres.

    Measurement of La-139(n,γ) cross section at n_TOF A. Mengoni, et al. (n_TOF collaboration), pp. 551-553 in AIP conference proceedings, Vol. 831, Eds: by S. V. Harissopulos, P. Demetriou and R. Julin, College Park, American Institute of Physics, 2006.

    Pulse shape analysis of signals from BaF2 and CeF3 scintillators for neutron capture experiments S. Marrone, E. Berthomieux, F. Becvar, D. Cano-Ott, N. Colonna, C. Domingo-Pardo, F. Gunsing, R.C. Haight, M. Heil, F. Kappeler, M. Krticka, P. Mastinu, A. Mengoni, P.M. Milazzo, J. O'Donnell, R. Plag, P. Schillebeeckx, G. Tagliente, J.L. Tain, R. Terlizzi and J.L. Ullmann, Nucl. Instrum. Methods Phys. Res. A568 (2006) pp. 904-911.

    Measurement of the neutron capture cross section of the s-only isotope Pb-204 from 1 eV to 440 keV C. Domingo-Pardo, U. Abbondanno, G. Aerts, et al. (n_TOF collaboration), Phys. Rev. C75 (2007) 015806.

    Angular distributions of protons scattered by Ar-40 nuclei with excitation of the 2+(1.46 MeV) and 3-(3.68 MeV) collective levels for incident energies of 25.1, 32.5, and 40.7 MeV N.T. Okumusoglu, F. Korkmaz Gorur, E.Sh. Soukhovitski, R. Capote, J.M. Quesada and S. Chiba, Phys. Rev. C75 (2007) 034616.

    The La-139(n,γ) cross section: Key for the onset of the s-process R. Terlizzi, U. Abbondanno, G. Aerts, et al. (n_TOF collaboration), Phys. Rev. C75 (2007) 035807.

    Neutron cross section measurements at n_TOF for ADS related studies R. Capote, A. Mengoni, et al., J. Phys. 41 (2006) pp. 352-360.

    Stellar neutron capture cross section of the unstable s-process branching point Sm-151 K. Wisshak, F. Voss, F. Kaeppeler, M. Krticka, S. Raman, A. Mengoni and R. Gallino, Phys. Rev. C73 (2006) 015802.

    Resonance capture cross section of Pb-207 C. Domingo-Pardo, U. Abbondanno, G. Aerts, et al. (n_TOF collaboration), Phys. Rev. C74 (2006) 055802.

    Letter to the editor A.L. Nichols, Ann. Nucl. Energy 32 (2005) pp. 1605-1607.

    Rare gases transition probabilities for plasma diagnostics K. Katsonis, R. E. H. Clark, M. Cornille, A. Siskos and A. Ndiaye, J. Abdallah, pp. 415-418 in AIP conference proceedings, v. 812, Eds: M. J. Sadowski, M. Dudek, H.-J. Hartfuss and E. Pawelec, College Park, American Institute of Physics, 2006.

    Implications of Sm-151(n,γ) cross section at n_TOF S. Marrone, A. Mengoni, et al. (n_TOF Collaboration), pp. 502-504 in AIP Conference Proceedings, Vol. 831, Eds: by S. V. Harissopulos, P. Demetriou and R. Julin, College Park, American Institute of Physics (2006), ISBN 0-7354-0323-6.

    EMPIRE: Nuclear Reaction Model Code System for Data Evaluation M. Herman, R. Capote, B.V. Carlson, P. Obložinský, M. Sin, M. Trkov, H. Wienke and V. Zerkin, Nuclear Data Sheets (2007) 0090-3752.

    Approximated lane consistency of the dispersive coupled channel potential for actinides J.M. Quesada, R. Capote, E.Sh. Soukhovitskii and S. Chiba; Phys. Rev. C76 (2007) 057602.

    Uncertainty estimation in intensity-modulated radiotherapy absolute dosimetry verification F. Sánchez-Doblado, G.H. Hartmann, J. Pena, R. Capote, M. Paiusco, B. Rhein, A. Leal and J.I. Lagares, Int. J. Radiation Oncology Biol. Phys. 68 (2007) pp. 301-310.

    IAEA Coordinated Research Project: updated decay data library for actinides M.A. Kellett, F.G. Kondev and A.L. Nichols, presented at 16th Int. Conf. on Radionuclide Metrology and its Applications (ICRM 2007), 3-7 September 2007, Cape Town, South Africa; also published in Appl. Radiat. Isot. 66 (2008) pp. 694-700.

    Heavy element and actinide decay data: UKHEDD2.5 A.L. Nichols and R.J. Perry, Serco Assurance report SA/NST/18923/W002, Issue 1; UKNSF (2007) p. 213, JEF/DOC-1166, February 2007.

    Activation product decay data: UKPADD6.7 A.L. Nichols and R.J. Perry, Serco Assurance report SA/NST/18923/W001, Issue 1; UKNSF (2007) p. 212, JEF/DOC-1165, February 2007.

    Recent advances in the JENDL project
    [Abstract]
    K. Shibata, T. Nakagawa, T. Fukahori, O. Iwamoto, A. Ichihara, N. Iwamoto, S. Kunieda, N. Otuka, J. Katakura, Y. Watanabe, K. Kosako, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 727-732.
    doi:10.1051/ndata:07743
    Abstract
    General- and special-purpose JENDL data files are being produced in cooperation with the Japanese Nuclear Data Committee. Nuclear model codes have been developed in order to raise the reliability of the fourth version of JENDL General-Purpose File (JENDL-4). MA and FP data have been evaluated for JENDL-4. The capture cross section of 235U was examined in the energy region from 2 keV to 1 MeV. As a follow-up action on the previous library JENDL-3.3, covariances of several nuclei were estimated for a study on ADS. The evaluation for the 2007 versions of JENDL High Energy File (JENDL/HE) and JENDL Photonuclear Data File (JENDL/PD), which are regarded as special-purpose files, is in the final stage. Analyses of neutron transmission experiments reveal the reliability of JENDL/HE.
    β -decay data requirements for reactor decay heat calculations: Study of the possible source of the gamma-ray discrepancy in reactor heat summation calculations A. Algora, A.L. Nichols, et al., in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.43-46.

    Neutron resonance spectroscopy at n_TOF at CERN F. Gunsing, R. Capote, A. Mengoni, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.537-542.

    IAEA coordinated research programme: Nuclear data for the production of therapeutic radionuclides R. Capote, E. Betak, B.V. Carlson, et al., in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.1367-1370.

    The U-234 neutron capture cross section measurement at the n_TOF facility C. Lampoudis, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.595-598.

    Inelastic neutron scattering cross section of Os-187 at 30 keV M. Mosconi, M. Heil, F. Kappeler, A. Mengoni, R. Plag, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 1307-1310.

    Design study for a new spallation target of the n_TOF facility at CERN C. Carrapico, S. Andriamonje, E. Berthoumieux, I. F. Goncalves, F. Gunsing, A. Mengoni, P. Vaz, V. Vlachoudis (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.445-448.

    New cross section measurements for neutron-induced reactions on Cr, Ni, Cu, Ta and W isotopes obtained with the activation technique V. Semkova, R. Capote, R. Jaime Tornin, A.J. Koning, A. Moens, A.J.M. Plompen, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.559-562.

    Measurement of neutron induced fission of U-235, U-233 and Cm-245 with the FIC detector at the CERN n_TOF facility M. Calviani, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.335-338.

    Measurement of the Zr-90,91,92,93,94,96(n,γ) and La-139(n,γ) cross sections at n_TOF G. Tagliente, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp.1303-1306.

    Neutron-induced fission cross sections measurements at n_TOF L. Audouin, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 421-424.

    Simultaneous measurement of the neutron capture and fission yields of U-233 E. Berthoumieux, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 571-574.

    Measurement of the Au-197 (n,γ) cross section at n_TOF: towards a new standard C. Massimi, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 537-542.

    Capture cross section measurements of Os-186,187,188 at n_TOF. The resolved resonance region K. Fujii, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 599-602.

    The neutron capture cross sections of Np-237(n,γ) and Pu-240(n,γ) and its relevance in the transmutation of nuclear waste C. Guerrero, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 627-630.

    Improved lead and bismuth (n,γ) cross sections and their astrophysical impact C. Domingo-Pardo, A. Mengoni, R. Capote, et al. (n_TOF Collaboration), in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 1311-1314.

    Extension of the nuclear reaction model code EMPIRE to actinides' nuclear data evaluation R. Capote, M. Sin, A. Trkov, M. Herman, B.V. Carlson, P. Obložinský, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 255-258.

    Lane consistency of the dispersive coupled-channel optical model potential R. Capote, E. Soukhovitskii, J.M. Quesada, S. Chiba, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 239-242.

    Development of IAEA nuclear reaction databases and services V. Zerkin, A. Trkov, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 769-772.

    Experimental studies to improve specific actinide decay data F.G. Kondev, M.A. Kellett, I. Ahmad, J.P. Greene, A.L. Nichols, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 93-96.

    The Global Assessment of Nuclear Data, GANDR D.W. Muir, A. Trkov, I. Kodeli, R. Capote, V. Zerkin, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 717-720.

    Deformation dependent TUL multi-step direct model H. Wienke, R. Capote, M. Herman, M. Sin, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 171-174.

    Evaluation of the Rh-103 neutron cross-section data in the unresolved resonance region for improved criticality safety L.C. Mihailescu, I. Sirakov, R. Capote, et al., in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 649-652.

    EMPIRE ultimate expansion: resonances and covariances M. Herman, S.F. Mughabghab, R. Capote, et al., in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 207-210.

    Neutron-induced fission cross section on actinides using microscopic fission energy surfaces M. Sin, R. Capote, S. Goriely, S. Hilaire, A.J. Koning, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 313-316.

    Evaluation of tungsten isotopes in the fast neutron range including cross section covariance estimation R. Capote, A. Trkov, I. Kodeli, E. Soukhovitskii, L.C. Leal, M. Herman, D.W. Muir, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 689-692.

    The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network
    [Abstract]
    H. Henriksson, O. Schwerer, D. Rochman, M.V. Mikhaylyukova, N. Otuka, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 737-740.
    doi:10.1051/ndata:07290
    Abstract
    The world-wide network of nuclear reaction data centres (NRDC) has, for about 40 years, provided data services to the scientific community. This network covers all types of nuclear reaction data, including neutron-induced, charged-particle-induced, and photonuclear data, used in a wide range of applications, such as fission reactors, accelerator driven systems, fusion facilities, nuclear medicine, materials analysis, environmental monitoring, and basic research. The now 13 nuclear data centres included in the NRDC are dividing the efforts of compilation and distribution for particular types of reactions and/or geographic regions all over the world. A central activity of the network is the collection and compilation of experimental nuclear reaction data and the related bibliographic information in the EXFOR and CINDA databases. Many of the individual data centres also distribute other types of nuclear data information, including evaluated data libraries, nuclear structure and decay data, and nuclear data reports. The network today ensures the world-wide transfer of information and coordinated evolution of an important source of nuclear data for current and future nuclear applications.
    The JEFF evaluated nuclear data project
    [Abstract]
    A.J. Koning, R.A. Forrest, M.A. Kellett, A.L. Nichols, et al., in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 721-726.


    doi:10.1051/ndata:07476
    Abstract
    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes.
    Status and future work of the NEA Working Party on international nuclear data Evaluation Cooperation A.J. Koning, J. Katakura, P. Obložinský, A.L. Nichols, C. Nordborg, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 741-746.

    The aims and activities of the International Network of Nuclear Structure and Decay Data Evaluators A.L. Nichols and J.K. Tuli, in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27, 2007, Nice, France, Eds: O.Bersillon, F.Gunsing, E.Bauge, R.Jacqmin, and S.Leray, EDP Sciences, 2008, pp. 37-42.

    IAEA fusion activities and nuclear data support for innovative concepts R.E.H. Clark. A. Malaquias, G. Mank, A.L. Nichols, Fusion Sci. Technol. 51 (2007) pp. 7-10.

    Measurement of the Pu-240 half-life I. Ahmad, F.G. Kondev, J.P. Green, M.A. Kellett and A.L. Nichols, Nucl. Instrum. Methods Phys. Res. A579 (2007) pp. 459-460.

    Measurement of the half-life of Cm-246 and the β-decay emission probabilities of Cm-246 and Cf-250 F.G. Kondev, I. Ahmad, J.P. Greene, M.A. Kellett and A.L. Nichols, Appl. Radiat. Isot. 65 (2007) pp. 335-340.

    Atomic and nuclear data services of the International Atomic Energy Agency A.L. Nichols, O. Schwerer and S. Dunaeva, presented to 56th Int. Conf. "Nucleus 2006", 4-8 September 2006, Sarov, Russia (also to be published in proceedings).

    Uncertainty estimation in intensity-modulated radiotherapy absolute dosimetry verification F. Sánchez-Doblado, G.H. Hartmann, J. Pena, R. Capote, M. Paiusco. B. Rhein, A. Leal and J.I. Lagares, Int. J. Radiation Oncology Biol. Phys. 68 (2007) pp. 301-310.

    Measurement of La-139(n,γ) Cross Section R. Terlizzi, R. Capote, A. Mengoni, et al., presented at 12th Int. Symposium on Capture Gamma-Ray Spectroscopy and Related Topics, 4-9 September 2005, University of Notre Dame, USA, also published in AIP 819, Eds: A. Woehr and A. Aprahamian (2006) pp. 283-287.

    Measurement of the resonance capture cross section of Pb-204,206 and termination of the s -process C. Domingo-Pardo, R. Capote, A. Mengoni, et al., presented at 12th Int. Symposium on Capture Gamma-Ray Spectroscopy and Related Topics, 4-9 September 2005, University of Notre Dame, USA, also published in AIP 819, Eds: A. Woehr and A. Aprahamian (2006) pp. 288-292.

    Neutron Capture Cross Section Measurements at n_TOF of Np-237, Pu-240 and Am-243 for the Transmutation of Nuclear Waste D. Cano-Ott, R. Capote, A. Mengoni, et al., presented at 12th Int. Symposium on Capture Gamma-Ray Spectroscopy and Related Topics, 4-9 September 2005, University of Notre Dame, USA, also published in AIP 819, Eds: A. Woehr and A. Aprahamian (2006) pp. 318-322.

    Monte Carlo correction factors for a Farmer 0.6 cm³ ion chamber dose measurement in the build-up region of the 6MV clinical beam J. Pena, F. Sánchez-Doblado, R. Capote, J.A. Terrón and F. Gómez, Phys. Med. Biol. 51 (2006) pp. 1523-1532.

    Measurement of the Sm-151(n,γ) cross section from 0.6 eV to 1 MeV via the neutron time-of-flight technique at the CERN n_Tof facility S. Marrone, R. Capote, A. Mengoni, et al.,Phys. Rev. C73 (2006) 034604:1-18.

    Neutron capture cross section of Th-232 measured at the n_TOF facility at CERN in the unresolved resonance region up to 1 MeV G. Aerts, R. Capote, A. Mengoni, et al., Phys. Rev. C73 (2006) 054610:1 10.

    Fission of light actinides: Th-232(n,f) and Pa-231(n,f) reactions M. Sin, R. Capote, A. Ventura, M. Herman and P. Obložinský, Phys. Rev. C74 (2006) 014608 pp. 1-13.

    New measurement of neutron capture resonances in Bi-209 C. Domingo-Pardo, R. Capote, A. Mengoni, et al., Phys. Rev. C74 (2006) 025807:1-10.

    Isospin dependent dispersive coupled channel optical model potential for actinides R. Capote, E.Sh. Soukhovitski, J.M. Quesada and S. Chiba, presented at Workshop on Nuclear Data for the Next Decade, 26-28 September 2005, CEA-DIF Bruyeres-le-Châtel, France; also published in NEA Workshop Proc. - Perspectives on Nuclear Data for the Next Decade, Ed.: E. Bauge (2006) pp. 43-55.

    International Atomic Energy Agency: Dedicated nuclear databases A.L. Nichols, presented at a plenary session on ‘Advances in Nuclear Data Libraries’, PHYSOR-2006, ANS Topical Meeting on Advances in Nuclear Analysis and Simulation, 10-14 September 2006, Vancouver, British Columbia, Canada, also published in proceedings PHYSOR-2006, ANS, Inc. topical Meeting on Reactor Physics, ISBN: 0-89448-697-7.

    Measurement of the Neutron Capture Cross Section of U-236 F. Gunsing, R. Capote, A. Mengoni, et al., presented at PHYSOR-2006, ANS Topical Meeting on "Advances in Nuclear Analysis and Simulation", 10-14 September 2006, Vancouver, British Columbia, Canada, also published in proceedings PHYSOR-2006, ANS, Inc. Topical Meeting on Reactor Physics, ISBN: 0-89448-697-7.

    Measurement at n_TOF of the Np-237(n,γ) and Pu-240(n,γ) Cross Sections for the Transmutation of Nuclear Waste A. Guerrero, R. Capote, A. Mengoni, et al. presented at PHYSOR-2006, ANS Topical Meeting on "Advances in Nuclear Analysis and Simulation", 10-14 September 2006, Vancouver, British Columbia, Canada, also published in proceedings PHYSOR-2006, ANS, Inc. Topical Meeting on Reactor Physics, ISBN: 0-89448-697-7.

    Measurement of the Neutron Capture Cross Section of U-234 in n_TOF at CERN W. Dridi, R. Capote, A. Mengoni, et al. presented at PHYSOR-2006, ANS Topical Meeting on "Advances in Nuclear Analysis and Simulation", 10-14 September 2006, Vancouver, British Columbia, Canada, also published in proceedings PHYSOR-2006, ANS, Inc. Topical Meeting on Reactor Physics, ISBN: 0-89448-697-7.

    n_TOF fission data of interest to GEN-IV and ADS C. Paradela, R. Capote, A. Mengoni, et al. presented at PHYSOR-2006, ANS Topical Meeting on "Advances in Nuclear Analysis and Simulation", 10-14 September 2006, Vancouver, British Columbia, Canada, also published in proceedings PHYSOR-2006, ANS, Inc. Topical Meeting on Reactor Physics, ISBN: 0-89448-697-7.

    Validation of Th-232 Evaluated Nuclear Data Through Benchmark Experiments
    [Abstract]
    A. Trkov and R. Capote presented at Nuclear Energy for New Europe, 18-21 September 2006, Portorož,Slovenia, also published in proceedings of the Int. Conf. Nuclear Energy for New Europe, 2006, pp. 110.1-110.7.

    Abstract
    Evaluated nuclear data files for nuclides of the thorium-uranium cycle were released as a result of a coordinated research project of the International Atomic Energy Agency. To validate the data a series of benchmark test cases were analysed, with emphasis on the most important nuclides 232Th and 233U. Remaining nuclides appearing in the benchmarks were taken from the ENDF/B-VII beta-2 library, except for a few sensitivity studies where the data were taken from other sources. The results show marked improvement in the agreement with measurements, much of it coming from the new evaluations
    Evaluation of neutron cross section data in the unresolved resonance region with a link to the optical model I. Sirakov, P. Schillebeeckx and R. Capote, presented to Wonder2006 – Workshop on Nuclear Data Evaluation for Reactor Applications, 9-11 October 2006, Chateau de Cadarache, Saint-Paul-lez-Durance, France (also to be published in proceedings).

    Highlights from the coordinated research project on the thorium-uranium fuel cycle A. Trkov and R. Capote, 3rd Workshop on Neutron Measurements, Evaluations and Applications, NEMEA-3, 25-28 October 2006, Borovets, Bulgaria, EUR22794EN(2006), pp. 43-48. Ed: A.J.M. Plompen, Luxembourg, ISBN 978-92-79-06158-5.

    Modelling of nuclear data in the fast neutron region R. Capote, M. Sin and A. Trkov, 3rd Workshop on Neutron Measurements, Evaluations and Applications, NEMEA-3, 25-28 October 2006, Borovets, Bulgaria, EUR22794EN(2006), pp. 13-18. Ed: A.J.M. Plompen, Luxembourg, ISBN 978-92-79-06158-5.

    Achievements of and perspectives for the n_TOF facility at CERN A. Mengoni,3rd Workshop on Neutron Measurements, Evaluations and Applications, NEMEA-3, 25-28 October 2006, Borovets, Bulgaria, EUR22794EN(2006), Ed: A.J.M. Plompen, Luxembourg, ISBN 978-92-79-06158-5.

    International Efforts to Improve Atomic and Nuclear Databases for Energy and Non-Energy Applications A.L. Nichols (invited paper), presented at the BARC Golden Jubilee DAE-BRNS National Workshop on Nuclear Data for Advanced Nuclear Systems, 8-11 November 2006, Mangalore, India, also published in Current Science 93 (2007) pp. 26-34.

    IAEA Co-ordinated Research Project: Update of X-ray and gamma-ray decay data standards for detector calibration and other applications A.L. Nichols, presented at 14th Int. Conf. on Radionuclide Metrology and its Applications (ICRM 2003), 2-6 June 2003, Dublin, Ireland; also published in Appl. Radiat. Isot.60 (2004) pp. 247-256.

    IAEA Nuclear Data Section: Provision of atomic and nuclear databases for user applications D.P. Humbert, A.L. Nichols and O. Schwerer, presented at 14 th Int. Conf. on Radionuclide Metrology and its Applications (ICRM 2003), 2-6 June 2003, Dublin, Ireland; also published in Appl. Radiat. Isot.60 (2004) pp. 311-316.

    Table of radionuclides, Vol. 1 – A = 1 to 150 M.-M. Bé, V. Chisté, C. Dulieu, E. Browne, V. Chechev, N. Kuzmanko, R. Helmer, A. Nichols, E. Schönfeld and R. Dersch, Monographie BIPM-5 (2004) Bureau International des Poids et Mesures.

    Table of radionuclides, Vol. 2 – A = 151 to 242 M.-M. Bé, V. Chisté, C. Dulieu, E. Browne, V. Chechev, N. Kuzmanko, R. Helmer, A. Nichols, E. Schönfeld and R. Dersch, Monographie BIPM-5 (2004) Bureau International des Poids et Mesures.

    Microionization chamber for reference dosimetry in IMRT verification: clinical implications on OAR dosimetric errors F. Sánchez-Doblado, R. Capote, A. Leal, J.V. Roselló, J.I. Lagares, R. Arráns and G.H. Hartmann, presented at Advanced Workshop on Current Topics in Monte Carlo Treatment Planning, 3-5 May 2004, McGill University, Medical Physics Unit, Montréal, Québec, Canada; published in Phys. Med. Biol. 50 (2005) pp. 959-970.

    An EGSnrc photon cross section sensitivity study in low energy photon transport R. Capote, R. Linares and F. Sánchez-Doblado, presented at Advanced Workshop on Current Topics in Monte Carlo Treatment Planning, 3-5 May 2004, McGill University, Medical Physics Unit, Montréal, Québec, Canada.

    On the thermal scattering law data for reactor lattice calculations
    [Abstract]
    A. Trkov and M. Mattes, Eds.: I. Jencic and M. Tkavc, Proc. Int. Conf. Nuclear Energy for New Europe 2004, Portorož, Slovenia, 6-9 September 2004, pp. 201.1-201.8, Nuclear Society of Slovenia (2004).

    Abstract
    Thermal scattering law data for hydrogen bound in water, hydrogen bound in zirconium hydride and deuterium bound in heavy water have been re-evaluated. The influence of the thermal scattering law data on critical lattices has been studied with detailed Monte Carlo calculations and a summary of results is presented for a numerical benchmark and for the TRIGA reactor benchmark. Systematics for a large sequence of benchmarks analysed with the WIMS-D lattice code are also presented.
    Nuclear Reaction Data Centre Network: A success story O. Schwerer, V. McLane, H. Henriksson and S. Maev, presented at International Conference on Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 83-86, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    NEA Working Party on International Nuclear Data Cooperation – Recent achievements and plans P. Obložinský, J. Katakura, A.J. Koning, A.L. Nichols and C. Nordborg, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 128-131, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Nuclear decay data: On-going studies to address and improve radionuclide decay characteristics A.L. Nichols (invited paper), presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 242-251, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Neutron cross-section evaluations for Ge-70,72,73,74,76
    [Abstract]
    O. Iwamoto, M. Herman, S.F. Mughabghab, P. Obložinský and A. Trkov, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 434-437, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Abstract
    Entirely new evaluations have been performed for neutrons on all isotopes of Ge, from a thermal energy up to 20 MeV, with a focus on photon production. The resonance parameters were considerably improved compared to earlier evaluations. The fast-neutron region has been evaluated using the EMPIRE-2.19 code. The results were validated against photon data on Fe and Nb. Isotopic evaluations for Ge were summed up and compared with available measurements on natural Ge. Various quantities related to photon production, showing strong dependence on neutron incident energy, are discussed
    Review of neutron cross-section evaluations for fission products P. Obložinský, M. Herman, S. Mughabghab, I. Sirakov, J. Chang, T. Nakagawa, K. Shibata, M. Kawai, A. V. Ignatyuk, V. G. Pronyaev, V. Zerkin, S. Qingbiao and Z. Youxiang, presented at International Conference on Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 438-441, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    SIGACE code for generating high-temperature ACE files; validation and benchmarking
    [Abstract]
    A.R. Sharma, S. Ganesan and A. Trkov, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 499-502, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Abstract
    A code named SIGACE has been developed as a tool for MCNP users within the scope of a research contract awarded by the Nuclear Data Section of the International Atomic Energy Agency (IAEA) (Ref: 302-F4-IND-11566 B5- IND-29641). A new recipe has been evolved for generating high-temperature ACE files for use with the MCNP code. Under this scheme the low-temperature ACE file is first converted to an ENDF formatted file using the ACELST code and then Doppler broadened, essentially limited to the data in the resolved resonance region, to any desired higher temperature using SIGMA1. The SIGACE code then generates a high-temperature ACE file for use with the MCNP code. A thinning routine has also been introduced in the SIGACE code for reducing the size of the ACE files. The SIGACE code and the recipe for generating ACE files at higher temperatures has been applied to the SEFOR fast reactor benchmark problem (sodium-cooled fast reactor benchmark described in ENDF-202/BNL-19302, 1974 document). The calculated Doppler coefficient is in good agreement with the experimental value. A similar calculation using ACE files generated directly with the NJOY system also agrees with our SIGACE computed results. The SIGACE code and the recipe is further applied to study the numerical benchmark configuration of selected idealized PWR pin cell configurations with five different fuel enrichments as reported by Mosteller and Eisenhart. The SIGACE code that has been tested with several FENDL/MC files will be available, free of cost, upon request, from the Nuclear Data Section of the IAEA
    Data dissemination and international collaboration T. Fukahori, A.V. Ignatyuk, F.G. Kondev, K.-L. Kratz, V. McLane, A.L. Nichols, A. Nouri, O. Schwerer, A.A. Sonzogni and D.F. Winchell, presented at International Conference on Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 539-544, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    EXFOR-CINDA-ENDF: Migration of databases to give higher quality nuclear data services V.V. Zerkin, V. McLane, M.W. Herman and C.L. Dunford, presented at International Conference on Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Editors: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 586-589, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Status of the international neutron cross-section standards file V.G. Pronyaev, S.A. Badikov, C. Zhenpeng, A.D. Carlson, E.V. Gai, G.M. Hale, F.J. Hambsch, H.M. Hofmann, N.M. Larson, D.L. Smith. S.Y. Oh, S. Tagesen and H. Vonach, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 1 (2005) pp. 808-815, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Recent developments of the nuclear reaction model code EMPIRE
    [Abstract]
    M. Herman, P. Obložinský, R. Capote, M. Sin, A. Trkov, A. Ventura and V. Zerkin, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 2 (2005) pp. 1184-1187, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Abstract
    Recent extensions and improvements of the EMPIRE code system are outlined. They add to the code new capabilities such as fission of actinides, preequilibrium emission of clusters, photo-nuclear reactions, and reactions on excited targets. These features, along with improved ENDF formatting, exclusive spectra, and recoils make the forthcoming 2.19 release a complete tool for evaluation of nuclear data at incident energies above the resonance region
    Improvement of the fission channel in the EMPIRE code
    [Abstract]
    M. Sin, R. Capote, M. Herman, P. Obložinský, A. Ventura and A. Trkov, presented at International Conference on Nuclear Data for Science and Technology, 27 September – 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Eds.: R.C. Haight, M.B. Chadwick,T. Kawano and P. Talou, Vol. 769, Part 2 (2005) pp. 1249-1252, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    Abstract
    The new fission formalism implemented in EMPIRE-2.19 is presented along with several examples of applications to neutron- and photon-induced fission.
    Review of experimental data on alpha-induced reactions on some nuclei (Mg-24, Si-28, S-32, Ar-36, Ca-40) in terms of astrophysical applications S.A. Dunaeva, V. McLane, M. Savin and S. Taova, presented at International Conference on Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fé, USA; also published in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Editors: R.C. Haight, M.B. Chadwick, T. Kawano and P. Talou, Vol. 769, Part 2 (2005) pp. 1386-1389, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X.

    IAEA nuclear data for applications: cross section standards and the reference input parameter library (RIPL) R. Capote Noy, A.L. Nichols and V.G. Pronyaev, presented at Enlargement Workshop on Neutron Measurements, Evaluations and Applications, NEMEA-2, Bucharest, Romania, 20-23 October 2004, EUR 22136 EN (2005), pp. 7-16, Ed.: A.J.M. Plompen, Luxembourg, ISBN 92-894-8618-X.

    Fission of thorium isotopes M. Sin, R. Capote Noy, M. Herman, P. Obložinský, A. Trkov and A. Ventura, presented at Enlargement Workshop on Neutron Measurements, Evaluations and Applications, NEMEA-2, Bucharest, Romania, 20-23 October 2004, EUR 22136 EN (2005), pp. 153-156, Ed.: A.J.M. Plompen, Luxembourg, ISBN 92-984-8618-X.

    Neutron activation cross section measurements from threshold to 20 MeV for the validation of nuclear models and their parameters A.J.M. Plompen, D.L. Smith, R. Capote et al., A report by the Working Party on International Evaluation Co‑operation of the NEANuclear Science Committee (WPEC-19), NEA/WPEC-19, OECD, Paris, 2005, ISBN 92-64-01070.

    Nuclear data services of the International Atomic Energy Agency: an overview A.L. Nichols, L. Costello and V.V. Zerkin (invited paper), presented at DAE-BRNS National Workshop on Nuclear Data for Reactor Technology and Fuel Cycle, 7-10 March 2005, Bhabha Atomic Research Centre (BARC), Trombay, Mumbai, India.

    Nuclear databases for energy applications: an IAEA perspective R. Capote-Noy, A.L. Nichols and A. Trkov, presented at Int. Workshop on Nuclear Data Needs for Generation IV Nuclear Energy Systems, Antwerp, Belgium, 5-7 April 2005; pp. 244-252 in Proc. Int. Workshop on Nuclear Data Needs for Generation IV Nuclear Energy Systems, Ed. P. Rullhusen (2006), World Scientific, Singapore, ISBN 981-256-830-1.

    IAEA Coordinated Research Project on fission product yield data for minor actinides up to 150 MeV M. Lammer and A.L. Nichols, presented at 3rd International Workshop on Nuclear Fission and Fission-product Spectroscopy, Fission 2005, 11-14 May 2005, Cadarache, France; also published in AIP Conf. Proc. – 3rd Int. Workshop on Nuclear Fission and Fission-product Spectroscopy, Eds.: H. Goutte, H. Faust, G. Fioni and D. Goutte, Vol. 798 (2005) pp. 285-293, AIP, Melville, New York, ISBN 0-7354-0288-4, ISSN 0094-243X.

    Nuclear decay data: observations and reflections A.L. Nichols (invited paper), presented at 15th Int. Conf. on Radionuclide Metrology and its Applications (ICRM 2005), 5-9 September 2005, Oxford, UK; also published in Appl. Radiat. Isot., 64 (2006) pp. 1384-1391.

    Revisiting the U-238 thermal capture cross section and gamma-ray emission probabilities from Np-239 decay A. Trkov, G.L. Molnár, Zs. Révay, S.F. Mughabghab, R.B. Firestone, V.G. Pronyaev, A.L. Nichols and M.C. Moxon, Nucl. Sci. Eng. 150 (2005) pp. 336-348.

    Status and perspective of nuclear data production, evaluation and validation
    [Abstract]
    A. Trkov (invited paper), Nucl. Eng. Technol. 37 (2005) pp. 11-24.

    Abstract
    A very important feature in the development of nuclear technology has been and will continue to be the flow of information from nuclear data production to the various applications fields in nuclear technology. Both, nuclear data and this communications flow are defined in this paper. Nuclear data result from specific technical activities including their production, evaluation, processing, verification, validation and applications. These activities are described, focusing on nuclear reactor calculations. Mathematical definitions of different types of nuclear data are introduced, and international forums involved in nuclear data activities are listed. Electronic links to various sources of information available on the web are specified, whenever possible
    Level densities of transitional Sm nuclei R. Capote, A. Ventura, F. Cannata and J. M. Quesada, Phys. Rev. C71 (2005) 064320.

    Dispersive coupled channel analysis of nucleon scattering from Th-232 up to 200 MeV E.Sh. Soukhovitskii, R. Capote, J.M. Quesada and S. Chiba, Phys. Rev. C72 (2005) 024604.

    Micro ionization chamber dosimetry in IMRT verification: clinical implications of dosimetric errors in the PTV F. Sánchez-Doblado, R. Capote, J.V. Roselló, A. Leal,J.I. Lagares, R. Arráns and G.H. Hartmann, Radiother. Oncol. 75 (2005) pp. 342-348.

    Nuclear reaction and structure data services of the National Nuclear Data Center B. Pritychenko, A.A. Sonzogni, D.F. Winchell, V.V. Zerkin, R. Arcilla, T.W. Burrows, C.L. Dunford, M.W. Herman, V. McLane, P. Obložinský, Y. Sunborn and J.K. Tuli, Ann. Nucl. Energy 33 (2006) pp. 390-399.

    Simulation of an end-of cycle trip transient with the LOADF code package M. Božič and A. Trkov, Int. Conf. Nuclear Energy for New Europe 2005, Bled, Slovenia, 5-8 September 2005.

    Neutron capture reaction rates for stellar nucleosynthesis A. Mengoni, published in Proc. 20th Int. Conf. on Capture Gamma-ray Spectroscopy and Related Topics, University of Notre Dame, Indiana, USA, 4-9 September 2005.

    Is a global coupled-channel dispersive optical model potential for actinides feasible? R. Capote, E.Sh. Soukhovitski, J.M. Quesada and S. Chiba, Phys. Rev. C72 (2005) 064610.

    Neutron capture cross section measurements for nuclear astrophysics at CERN n-TOF U. Annondanno, R. Capote, A. Mengoni et al., (the n-TOF Collaboration), Nucl. Phys. A758 (2005) pp. 501-504.

    Measurement of the Sm-151(n,γ) cross section at n_TOF S. Marrone, R. Capote, A. Mengoni, et al., (the n-TOF Collaboration), Nucl. Phys. A758 (2005) pp. 533-536.

    Measurement of the Zr-90,91,92,94,96(n,γ) cross sections at n_TOF G. Tagliente, R. Capote, A. Mengoni et al., (the n-TOF Collaboration), Nucl. Phys. A758 (2005) pp. 573-576.

    Stellar neutron capture rates of C-14 R. Reifarth, A. Mengoni et al., Nucl. Phys. A578 (2005) pp. 787-790.

    Nuclear data requirements for decay heat calculations A.L. Nichols, pp. 65-69 in Lecture Notes, Vol. 20, Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety, 25 February – 28 March 2002, The Abdus Salam International Centre for Theoretical Physics, Eds.: M. Herman, N. Paver, ICTP Publ., Trieste, Italy, 2005.

    Higher Landau levels contribution to the energy of interacting electrons in a quantum dot A. Gonzalez, J.D. Serna, R. Capote and G. Avendaño, Physica E30 (2005) pp. 134-137.

    Laser-generated nanosecond pulsed neutron sources: scaling from VULCAN to table-top T. Zagar, J. Galy, J. Magill and M. Kellett, New J. Phys.7 (2005) pp. 2-13.