Open Access
| Issue |
ND 2007
2007
|
|
|---|---|---|
| Article Number | 213 | |
| Number of page(s) | 4 | |
| Section | Benchmarking for fission applications | |
| DOI | https://doi.org/10.1051/ndata:07231 | |
| Published online | 17 June 2008 | |
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07231
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
.kenji09@jaea.go.jp
Published online: 21 May 2008
© CEA 2008
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. Jin21 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
.kenji09@jaea.go.jp
Published online: 21 May 2008
Abstract
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