Validation of important fission product evaluations through CERES integral benchmarks

Optimization of energy resources suggests increased fuel residence in reactor cores and hence improved fission product evaluations are required. For thermal reactors the fission product cross sections in the JEF2.2 and JEFF3.1 libraries plus new evaluations from WPEC23 are assessed through modelling the CERES experiment in the DIMPLE reactor. The analysis uses the lattice code WIMS10. Cross sections for 12 nuclides are assessed. The thermal cross section and low energy resonance data for 147,152 Sm and 155 Gd are accurate to within 4%. Similar data for 109 Ag, 143 Nd and 149 Sm are within 8% while 95 Mo, 99 Tc, 103 Rh, 133 Cs and 145 Nd are within three benchmark standard deviations at ∼12%. The use of the 172 XMAS group scheme is adequate for all nuclides considered except 153 Eu.