1 Analysis of isotopic assay data from the MALIBU program

Acquisition and analysis of experimental isotopic assay data are essential for validating computer code predictions of isotopic composition for spent nuclear fuel in order to establish the uncertainty and bias associated with code predictions. Recently available experimental data for uranium oxide spent fuel, acquired through the MALIBU international program, are analyzed in this paper. The analyzed measurements include extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Analysis of the measurements was performed using the two-dimensional depletion module TRITON in the SCALE computer code system