Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation – Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968)
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Manuscript Completed: June 2009
Date Published: February 2010
G. Ilas, I.C. Gauld, F.C. Difilippo, M.B. Emmett
Oak Ridge National Laboratory
Managed by UT-Battelle, LLC
Oak Ridge, TN 37831-6170
M. Aissa, NRC Project Manager
NRC Job Code Y6685
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001
This report is part of a report series designed to document benchmark-quality radiochemical isotopic assay data against which computer code accuracy can be quantified to establish the uncertainty and bias associated with the code predictions. The experimental data included in the report series were acquired from domestic and international programs and include spent fuel samples that cover a large burnup range. The measurements analyzed in the current report, for which experimental data is publicly available, include 38 spent fuel samples selected from fuel rods with a 2.6 to 4.7 wt % 235U initial enrichment, which were irradiated in three pressurized water reactors operated in the United States and Japan and achieved burnup values from 14 to 56 GWd/MTU. The analysis of the measurements was performed by employing the two-dimensional depletion sequence of the TRITON module in the SCALE code system.