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Search Results - 西安交通大学 核安全与运行实验室 西安 710049
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基于KRUSTY带核实验的热管冷却反应堆瞬态分析程序验证
by
吴攀
,
欧阳泽宇
,
朱煜
,
单建强
Published in
核技术
(2023)
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不同热电转换系统的热管堆反应性引入事故特性研究
by
吴攀
,
朱煜
,
欧阳泽宇
,
单建强
,
闫啸
Published in
核技术
(01.11.2024)
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Journal Article
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engineering
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accident safety
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code validation
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heat pipe cooled reactor
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key words heat pipe cooled reactor
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krusty test
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open breton
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Chinese
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DOAJ Directory of Open Access Journals
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