Updating and Extending the IRDF-2002 Dosimetry Library

    Published: Aug 2012

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    The International Reactor Dosimetry File (IRDF)-2002 released in 2004 by the IAEA (see 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+g Co, 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.


    IRDF-2002, reactor dosimetry, nuclear data, spectrum average cross sections

    Author Information:

    Capote, Roberto
    International Atomic Energy Agency, NAPC-Nuclear Data Section, Vienna,

    Zolotarev, Konstantin I.
    Institute of Physics and Power Engineering, Obninsk,

    Pronyaev, Vladimir G.
    Institute of Physics and Power Engineering, Obninsk,

    Trkov, Andrej
    Jozef Stefan Institute, Ljubljana,

    Paper ID: STP155020120015

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120015

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