Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code
Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code
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DOI：
10.1016/j.anucene.2006.10.004
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发表时间：
2006-11
影响因子：
1.9
通讯作者：
Jaewoon Yoo;Y. Oka;Y. Ishiwatari;Jie Liu
中科院分区：
文献类型：
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作者：
Jaewoon Yoo;Y. Oka;Y. Ishiwatari;Jie Liu
