JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0 results for the doppler-defect benchmark suite

Mosteller, R. D.*; Nagaya, Yasunobu

Transactions of the American Nuclear Society, 97(1), p.506 - 508, 2007/11

A suite of computational benchmarks for the Doppler reactivity defect has been recently approved by the Joint Benchmark Committee of the American Nuclear Society. The suite contains subsets of cases with weapons-grade MOX fuel, reactor-recycle MOX fuel, and UO fuel. The UO fuel contains enrichments up 5 wt.%, while the reactor-recycle and weapons-grade MOX fuel contain PuO at levels up to 8 wt.% and 6 wt.%, respectively. In this work, Monte Carlo calculations were performed with three major nuclear data libraries, JENDL-3.3 JEFF-3.1 and ENDF/B-VII.0. For the MOX problems, no differences were observed among Monte Carlo codes and nuclear data libraries, whereas the differences of about 10 % were observed between MCNP and MVP results at the lower enrichments for the UO problems. It is considered that the differences are not caused by the difference of the libraries but the instead by the scheme employed to generate the Monte Carlo cross section data at higher temperatures.