Preliminary neutronics and thermal analysis of a heat pipe cooled traveling wave reactor
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
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Cited by 1 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems;Frontiers in Energy Research;2023-12-04
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