Open Access
ND 2007
Article Number 213
Number of page(s) 4
Section Benchmarking for fission applications
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07231

Benchmark of evaluated nuclear data libraries using post-irradiation experimental data on fuel composition changes of the fast reactor JOYO

K. Yokoyama1 and T. Jin2

1  Japan Atomic Energy Agency (JAEA), Reactor Physics Analysis and Evaluation Group, 4002, Narita, O-arai, Ibaraki 311-1393, Japan
2  NESI Incorporation, 4002, Narita, O-arai, Ibaraki 311-1393, Japan

Published online: 21 May 2008

Post irradiation experiment (PIE) data on depleted fuel composition of the experimental fast reactor JOYO MK-II have been accumulated since 1986 by the JNC (the former of JAEA). In the present study, all available PIE data of JOYO MK-II driver fuel were analyzed and integral data concerning 235U depletion and 236U generation were prepared. Both the integral data are sensitive to 235U capture cross section and applicable to nuclear data benchmarks. The recent evaluated nuclear data libraries, JENDL-3.2, -3.3, JEFF-3.1 and ENDF/B-VII, have a tendency to overestimate the generation of 236U. A cross section adjustment demonstrated that re-evaluation of 235U capture cross section improved the overestimation.

© CEA 2008