AHTR Mechanical, Structural, And Neutronic Preconceptual Design
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1. ORNL
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Office of Scientific and Technical Information (OSTI)
Cited by 9 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. Infiltration of molten fluoride salts in graphite: Phenomenology and engineering considerations for reactor operations and waste disposal;Journal of Nuclear Materials;2022-12
2. CFD analysis of a solid pin-fueled small modular fluoride salt-cooled reactor;Nuclear Engineering and Design;2022-02
3. Corrosion Behavior of Pre-Carburized Hastelloy N, Haynes 244, Haynes 230, and Incoloy 800H in Molten FLiNaK;Nuclear Technology;2020-10-15
4. A Stylized 3-D Benchmark Problem Set Based on the Pin-Fueled SmAHTR;Nuclear Technology;2020-07-09
5. Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis;Nuclear Technology;2018-07-17
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