Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF)


Coordinated Research Project (CRP) - approved on 30 October 2012, CRP code F41031
duration period: 4 years, mid 2013 (1st RCM) - 2017


Motivation/Purposes

   The Nuclear Data Section of IAEA, in accordance with the recommendation of the International Nuclear Data Committee (INDC(NDS)-0619), has initiated a Coordinated Research Project (CRP) with the main goal to test, validate and improve the IRDFF library.
   The International Reactor Dosimetry and Fusion File (IRDFF) (for more information see IRDFF release page) is an extension of the International Reactor Dosimetry File (IRDF-2002) to cover fission, fusion and accelerator driven applications.
   This extension includes 4 new reactions (67Zn(n,p)67Cu, 113In(n,n')113mIn, 169Tm(n,3n)167Tm, 209Bi(n,3n)207Bi), 32 updated evaluations and increases the end-point energy of the library from 20 to 60 MeV.
   The energy extrapolation has been made in a formal way by using the TENDL-2010 cross sections (and covariance matrices) after matching to the IRDF-2002 cross section values at the extension point (typically 20 MeV).
   In despite of the current IRDFF end-point energy 60 MeV (however already with several exceptions: 186W(n,γ) - 150 MeV; 31P(n,p)31Si, 92Mo(n,p)92mNb, 235,238U(n,f) and (n,γ), 239Pu(n,f) - 200 MeV), CRP will strive to evaluate and eventually add to the library the high threshold reactions with cross section peaks located between 20 and 100 MeV to meet requirements of the higher energy nuclear installations such as ADS. Often this is a set of several reactions (n,3-6n) on one of such isotope: 197Au, 169Tm, 209Bi, 59Co, 63Cu, 89Y, 93Nb. The set of such reactions are very convenient for neutron fluence monitoring and spectrum unfolding at the high energy accelerator driven neutron sources.
   The CRP will strive to stimulate new energy integrated (integral) and point energy (differential) cross section measurements and collect all other experimental information suitable for validation but not used so far, e.g. data missing in EXFOR: Cross Sections, Neutron Sources Spectra or 235U(n,f)PFNS.

Main CRP Output

    Improved, tested and validated International Reactor Dosimetry and Fusion File (IRDFF) with proper decay data and documentation.

Content of IRDFF

   1. IRDFF-1.05 (actual version since Oct 2014) contains 79 dosimetry and 3 absorption (cover materials) cross sections. It also includes total and elastic cross sections for materials or reactions with resonance structure for evaluation of the self-shielding effect.
    IRDFF-1.05 cp. to IRDFF-1.04 has 3 new 28Si(n,p)28Al, 29Si(n,x)28Al, 113In(n,g)114mIn and update of 31P(n,p)31Si reactions (see K.Zolotarev et al. INDC(NDS)-0668)
    Cross sections and uncertainties:
    - List of reactions
    - MAT, Lab, Date, Authors, ENDF zip-files ... of evaluations
    - Retrieval page (use "Quick plot" option for plotting IRDFF or "Universal plot" to include EXFOR data,
                            it also allows automatic correction of cross sections and uncertainties, select example #5)
    - Plots of differences between IRDFF-1.05 and IRDFF-1.04
    - Plots of differences between IRDFF-1.05 and IRDF-2002

   IRDFF-1.05 processed by NJOY-2012.42 (ACE files for 6Li(n,a) and 10B(n,a) were corrected) in ACE format: cross sections (300K) Type1 ASCII or Type2 binary and xsdir Type1 or Type2 (the order of Temperature is corrected as E-08).
   ACE files were verified by comparison of SPA calculated by MCNP5 and RR_UNC codes with IRDFF.ENDF spectra: results for 252Cf(s.f.) and thermal Maxwellian spectra.
   IRDFF-1.05 Cross-Sections and Covariences in the NJOY Plots

   Previous IRDFF cros-sections versions:
   IRDFF-1.04 contained 76 dosimetry and 3 absorption (cover materials) cross sections. It has minor format corrections cp. IRDFF-1.03.
   IRDFF-1.04 processed by NJOY-2012.32 in ACE format: cross sections (300K) Type1 ASCII or Type2 binary and xsdir Type1 or Type2.
    ACE files were verified by comparison of SPA calculated by MCNP5 and RR_UNC codes in IRDFF.ENDF spectra), see results for 252Cf(s.f.) and 235U(nth,f) spectra.
   IRDFF-1.03 includes updates of 54Fe(n,p)54Mn, 58Ni(n,2n)57Ni, 93Nb(n,γ)94Nb, 115In(n,γ)116mIn and new 238U(n,2n)237U reaction (see K.Zolotarev et al. INDC(NDS)-0657).
   IRDFF-1.02 contains 75 dosimetry and 3 absorption (cover materials) cross sections
    - MAT, Lab, Date, Authors, ENDF files ... of evaluations
    - Retrieval page
    IRDFF-1.02 processed by NJOY-99.396 in ACE format: cross sections (300K) Type1 ASCII or Type2 binary and xsdir Type1 or Type2.

   2. Reference Decay data for reaction residuals and Isotope Abundancies:
   - actual (Oct 2014) version includes 82 + new 6 Isotopes/Isomers: Actual status and Needs for updating
   - actual IRDFF Decay Library converted in ENDF format: IRDFF2014.ENDF (source is ENSDF as March 2014 or new DDEP-Chechev evaluations)
   - previous (2012) IRDFF Decay Library in ENDF format: irdf2012.endf (source was ENSDF evaluations as Dec 2011)
   - Abundances of the Stable Isotopes: Table

   3. Standard and Reference Spectra (interactive plots and numerical data in different formats):
    - 252Cf(s.f.): interactive plot for Spectrum/Covariance; original ENDF file and processed in 640 groups
    - 235U(nth,f): interactive plot for Spectrum/Covariance; original ENDF file

   4. Fission Yields data for fissile isotopes used in dosimetry (from JEFF-3.1 as a candidate reference source):
    - Th-232, U-235, U-238, Np-237, Pu-239, Am-241

   5. Photo-induced Reactions which contribute to the production of the same residual isotope as neutrons do:
   - example: g,n+238U
   - Photonuclear Data Libraries: IAEA photonuclear or other photonuclear Libraries

IRDFF: Needs for measurements, updates or new evaluations, data formats ...

Energy domains, typical fields, facilities and data status

In the case of validation of dosimetry cross sections, that should have high accuracy as references, specific attention should be paid to:

Interaction of IRDFF with other neutron reaction data libraries:

  • following IRDFF cross sections were taken from Standards: 6Li(n,t)4He (below 2.8 MeV), 10B(n,α0)7Li and 10B(n,α1)7Li (below 1.0 MeV), 197Au(n,γ)198Au (from 4.8 keV to 2.6 MeV), 235U(n,f) (from 25 keV to 200 MeV) and 238U(n,f) (from 1 MeV to 200 MeV)
  • following IRDFF cross sections were accepted in the Medical database of Theurapeutic Radioisotope Production as clinically established: 90Zr(n,p)90Y and 32S(n,p)32P or emerging: 64Zn(n,p)64Cu
  • following IRDFF cross sections were accepted by ...
  • Web page content by S.Simakov
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