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


	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:http://dx.doi.org/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 E_n = 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,g) 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	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:http://dx.doi.org/10.1051/epjconf/20122110005
	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
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.
	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, Journal of ASTM International 9 (4) (2012) JAI104095 doi:10.1520/JAI104095
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,g)⁵⁶Mn [Abstract]	R. Capote, D.L. Smith, A. Trkov, M. Meghzifene, Journal of ASTM International 9 (3) (2012) JAI104115 doi:10.1520/JAI104115
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.
	Updating and extending the IRDF-2002 dosimetry library [Abstract]	R. Capote, K.I. Zolotarev, V.G. Pronyaev, A. Trkov, Journal of ASTM International 9 (4) (2012) JAI104119 doi:10.1520/JAI104119
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.
	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	C. Guerrero, R. Capote, et al., (n_TOF collaboration), Physical Review C 85 (4) (2012) 044616 doi:10.1103/PhysRevC.85.044616
	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,g) 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
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[Abstract]	F. Belloni, R. Capote, et al., (n_TOF collaboration), Physica Scripta, 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 , pp. 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 , pp. 141-161 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 , pp. 179-197 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)	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 , pp. 2690
	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, pp. 293-302
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]	Thomas R. Preston, Sam M. Vinko, Orlando Ciricosta, Hyun-Kyung Chung, Richard W. Lee and Justin S. Wark doi:http://dx.doi.org/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,46,47,48}Sc 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 vol.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 vol. 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. C85(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)⁶⁸Cu^m, ⁶⁸Zn(n,p)⁶⁸Cu^m, ^natMo(n,x)⁹⁷Nb^g, ⁹⁷Mo(n,p)⁹⁷Nb^g, ^natMo(n,x)⁹⁷Nb^m, ⁹⁷Mo(n,p)⁹⁷Nb^m, ^natSn(n,x)¹¹⁶In^m1+m2, ¹¹⁶Sn(n,p)¹¹⁶In^m1+m2, ^natSn(n,x)¹¹⁷In^g, ¹¹⁷Sn(n,p)¹¹⁷In^g, ^natSn(n,x)¹¹⁸In^m1+m2,¹¹⁸Sn(n,p)¹¹⁸In^m1+m2, ^natSn(n,x)¹²⁰In^x , ¹²⁰Sn(n,p)¹²⁰In^x , ^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 (also to be published in Proceedings).
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, presented at 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA 2011), June 6-9, 2011, Ghent, Belgium, also to be published in IEEE Conference Proceedings.
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]	Abriola, D.; Gurbich, A. F.; Kokkoris, M.; Lagoyannis, A.; Paneta, V. J. Nucl. Instrum. Methods in Phys. Res., B269 (2011) pp. 2011-2016. doi:10.1016/j.nimb.2011.06.002
Abstract Nuclear Instruments and Methods in Physics Research B, Volume 269, Issue 18, p. 2011-2016. 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	M.B. Chadwick, R. Capote, et. al., Nucl. Data Sheets 112 (2011) 2887-2996. doi:10.1016/j.nds.2011.11.002
	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, ^{180,182,183,184,186}W and ⁵⁵Mn [Abstract]	A. Trkov, R. Capote, E.Sh. Soukhovitskii, L.C. Leal, M. Sin, I. Kodeli, D.W. Muir, Nucl. 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, ^{180,182,183,184,186}W 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, ^{180,182,183,184,186}W 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, 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,88g}Y, ^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,88g}Y, ^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,88g}Y, ^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 (2011). 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 identied 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)¹⁷⁷Lu^g, ¹⁷⁸Hf(n,x)¹⁷⁷Lu^g, ¹⁸⁰Hf(n,p)¹⁸⁰Lu, ¹⁸⁰Hf(n,n'γ)¹⁸⁰Hf^m, 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 E_d = 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 S_n 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 k_eff 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 k_eff 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 k_eff 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 45^o 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	S.P. Simakov, J. Li, U. Fischer, Fusion Eng. Design, 85 (2010) 1924-1927.
	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	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.
	Astrophysics at n_TOF facility	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.
	Elastic Scattering of 7Li + 27Al at Several Angles in the 7 - 11 MeV Energy Range	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.
	Radiative recombination rate coefficients for highly-charged tungsten ions	M.B. Trzhaskovskayaa, V.K. Nikulin, R.E.H. Clark, Atomic Data and Nuclear Data Tables 96 (2010) 1-25.
	Measurements of emission spectra from hot, dense germanium plasma in short pulse laser experiments	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.
	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	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.
	Nuclear Data Sheets for A = 72	D. Abriola and A.A. Sonzogni, Nucl. Data Sheets 111 (2010) pp. 1-140.
	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+m}Rh 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+m}Rh 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	V. Semkova, E. Bauge, A.J.M. Plompen, D.L. Smith , Nucl. Phys. A832 (2010) pp.149 169.
	High resolution measurements of the 241Am(n,2n) reaction cross section	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.
	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	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.
	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. 79-81.
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	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.
	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) p.510. 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) p. 2885. 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. Dâ€™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	I. Sirakov, R. Capote, F. Gunsing, P. Schillebeeckx and A. Trkov, Annals Nucl. Energy 35 (2008) pp. 1223-1231.
	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	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).
	Evaluation of the covariance matrix of the U-235 neutron induced prompt fission spectrum	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).
	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	A. Trkov, R. Capote, I. Kodeli, L. Leal, Nucl. Data Sheets 109 (12) (2008) pp. 2905-2909.
	Covariances of Prompt Fission Neutron Spectra	I. Kodeli, R. Capote and A. Trkov, Nucl. Data Sheets 109 (12) (2008) pp. 2840-2845.
	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) p. 195. 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	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.
	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	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.
	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	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).
	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	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.
	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	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.
	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	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.
	Improvement of the fission channel in the EMPIRE code	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.
	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	A. Trkov (invited paper), Nucl. Eng. Technol. 37 (2005) pp. 11-24.
	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.