Comparison of burnup calculation results using several evaluated nuclear data files

被引：8
|
作者：
Suyama, K
Katakura, J
Kiyosumi, T
Kaneko, T
Nomura, Y
机构：
[1] Japan Atom Energy Res Inst, Tokai Res Establishment, Dept Fuel Cycle Safety Res, Naka, Ibaraki 3191195, Japan
[2] Japan Atom Energy Res Inst, Tokai Res Establishment, Nucl Data Ctr, Naka, Ibaraki 3191195, Japan
[3] Japan Res Inst, Energy Technol Dept, Chiyoda Ku, Tokyo 1020082, Japan
来源：
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2002年 / 39卷 / 01期
关键词：
JENDL-3.2; ENDF/B-VI; JEF-2.2; burn-up calculations; SWAT; cross section library; calculated amount; fuel cycle; comparison of cross section; chain analysis; comparative evaluations;
D O I：
10.3327/jnst.39.82
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：
BUM-LIP calculation and comparison of the results were carried out to clarify the differences among the following latest evaluated nuclear data libraries: JENDL-3.2. ENDF/B-VI and JEF-2.2. The analyses showed that the differences seen among the current evaluated nuclear data libraries are small for evaluation of the amounts of many uranium and plutonium isotopes. However, several nuclides important for evaluation of nuclear fuel cycle as Pu-238, Cm-244, Sm-149 and Cs-134 showed large differences among used libraries. The chain analyses for the isotopes were conducted and the reasons for the differences were discussed. Based on the discussion. information of important cross section to obtain better agreement with the experimental results for Pu-238, Cm-244, Sm-149 and Cs-134 was shown.
引用
收藏
页码：82 / 89
页数：8
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