JENDL-4.0 Benchmarking for Fission Reactor Applications

被引:49
作者
Chiba, Go [1 ]
Okumura, Keisuke [1 ]
Sugino, Kazuteru [1 ]
Nagaya, Yasunobu [1 ]
Yokoyama, Kenji [1 ]
Kugo, Teruhiko [1 ]
Ishikawa, Makoto [1 ]
Okajima, Shigeaki [1 ]
机构
[1] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan
关键词
nuclear data; integral data; benchmarking; JENDL-4.0; ACTINIDE CROSS-SECTIONS; PROTOTYPE FAST-REACTOR; VALIDATION;
D O I
10.3327/jnst.48.172
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of integral data. Benchmark calculations are performed with a continuous-energy Monte Carlo code and with the deterministic procedure, which has been developed for fast reactor analyses in Japan. Through the present benchmark testing using a wide range of benchmark data, significant improvement in the performance of JENDL-4.0 for fission reactor applications is clearly demonstrated in comparison with the former library JENDL-3.3. Much more accurate and reliable prediction for neutronic parameters for both thermal and fast reactors becomes possible by using the library JENDL-4.0.
引用
收藏
页码:172 / 187
页数:16
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