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

Yokoyama, Kenji ; Jin, Tomoyuki*

Post irradiation experiment (PIE) data on depleted fuel composition of the experimental fast reactor "JOYO" MK-II has been accumulated since 1986 in JNC (the former of JAEA). In the present study, all the available PIE data of JOYO MK-II driver fuel were analyzed and integral data concerning $^{235}$ U depletion and $^{236}$ U generation were prepared. Both the integral data are sensitive to $^{235}$ U 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 $^{236}$ U. A cross section adjustment demonstrated that re-evaluation of $^{235}$ U capture cross section improved the overestimation.

Language	:	English
Journal	:	Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2
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Pages	:	p.807 - 810
Publication Year/Month	:	2008/05
Meeting title	:	International Conference on Nuclear Data for Science and Technology (ND 2007)
Held date	:	2007/04
Location (city)	:	Nice
Location (country)	:	France
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Keywords	:	no keyword
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Registration No. : BB20070314
JAEA Abstracts No. : 36001236
Paper Submission No. : 4539

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