Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation--ARIANE and REBUS Programs (UO2 Fuel)

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 % 23WUw, hich 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.