Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel (NUREG/CR-7012, ORNL/TM-2010/41)
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Manuscript Completed: September 2010
Date Published: January 2011
I.C. Gauld, G. Ilas, and G. Radulescu
Oak Ridge National Laboratory
Managed by UT-Battelle, LLC
Oak Ridge, TN 37831-6170
M. Aissa, NRC Project Manager
NRC Job Code N6540
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001
Experimental isotopic assay data for 51 spent fuel samples acquired from domestic and international programs have been compiled to provide a database to validate computational predictions of spent fuel isotopic compositions important to criticality safety (burnup credit), reactor physics, spent fuel storage and transportation, and waste management applications. The data were selected on the basis that they include extensive actinide and fission product isotopic assay measurements. The experimental data were acquired for fuels irradiated in six different pressurized water reactors: the Three Mile Island 1 and Calvert Cliffs 1 reactors operated in the United States, the Takahama-3 reactor in Japan, the Gösgen reactor in Switzerland, the GKN II reactor in Germany, and the Vandellós II reactor in Spain. The fuel samples cover enrichments from 2.6 to 4.7 wt % 235U, and a wide burnup range, from 9 to 78 GWd/MTU. In this report, spent fuel isotopic compositions calculated using two-dimensional isotope depletion models and ENDF/B-V–based cross section libraries in the SCALE 5 code system are benchmarked against the experimental isotopic data to validate the code and nuclear data libraries and provide estimates of isotopic bias and uncertainty for nuclides of highest importance to safety and licensing applications. The procedures used to evaluate the experimental data and assess the results are described.