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