Abstract
This report is part of a report series designed to document benchmark-quality radiochemical assay data against which computer code predictions of isotopic composition for spent nuclear fuel can be validated to establish the uncertainty and bias associated with the code predictions. The experimental data analyzed in the present report were acquired from two international programs: (1) ARIANE and (2) REBUS, both coordinated by Belgonucleaire. All measurements include extensive actinide and fission product data of importance to spent fuel safety applications including burnup credit, decay heat, and radiation source terms. The analyzed four spent fuel samples were selected from fuel rods with initial enrichments of 3.5, 3.8, and 4.1 wt % 235U, which were irradiated in two pressurized water reactors operated in Germany and Switzerland to reach burnups in the 30 to 60 GWd/MTU range. Analysis of the measurements was performed by using the two-dimensional depletion sequence of the TRITON module in the SCALE computer code system.
