Integral nuclear data validation using experimental spent nuclear fuel compositions

Abstract Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. The database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.

[1]  Mark L. Williams,et al.  Development of depletion perturbation theory for coupled neutron/nuclide fields , 1979 .

[2]  J. B. Briggs,et al.  Applications of Integral Benchmark Data , 2014 .

[3]  Kenya Suyama,et al.  Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems , 2011 .

[4]  William A. Wieselquist,et al.  A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN , 2015 .

[5]  N. Soppera,et al.  IDAT: The International Handbook of Evaluated Reactor Physics Benchmark Experiments Database and Analysis Tool , 2014 .

[6]  Dirk Bosbach,et al.  Determination of Bandwidths of PWR-UO2 Spent Fuel Radionuclide Inventory Based on Real Operational History Data , 2016, IEEE Transactions on Nuclear Science.

[7]  Ian C Gauld,et al.  Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE , 2012 .

[8]  C. Grandi,et al.  Nuclear Data for Science and Technology , 1998 .

[9]  Hugo J. Hahn.  ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT, NUCLEAR ENERGY AGENCY , 1983 .

[10]  N. M. Larson,et al.  ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .

[11]  J. B. Briggs,et al.  Identification of Integral Benchmarks for Nuclear Data Testing Using DICE (Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments) , 2011 .