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Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating

  • Published:2019-08 Issue:5 Volume:51 Page:1390-1397
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

He Zhao,Song Jinliang,Lian PengfeiORCID,Zhang Dongqing,Liu Zhanjun

Funder

National Natural Science Foundation of China

Natural Science Foundation of Shanghai

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference43 articles.

1. Generation-IV nuclear power: a review of the state of the science;Abram;Energy Policy,2008

2. Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties;Sohal,2010

3. An Overview of Liquid-Fluoride-Salt Heat Transport Systems;Holcomb,2010

4. Thermodynamic assessment of the LiF-NaF-BeF2-ThF4-UF4 system;Capelli;J. Nucl. Mater.,2014

5. Thermal conductivity of high temperature fluoride molten salt determined by laser flash technique;An;Int. J. Heat Mass Transf.,2015

Cited by 13 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. Dynamics of an Excess Electron in Molten LiF, KF, MgF2, and BeF2;Inorganic Chemistry;2024-02-19

2. Morphological and microstructural evolutions of chemical vapor reaction-fabricated SiC under argon ion irradiation;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2023-08

3. Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment;Journal of Nuclear Materials;2023-08

4. Theoretical insight into the structure of molten LiF, BF2, YF3 and ThF4;Journal of Radioanalytical and Nuclear Chemistry;2023-01-28

5. Evaluating the Effects of Molten Salt on Graphite Properties: Gaps, Challenges, and Opportunities;Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments;2022-12-01
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