Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor
Autor: | Takaaki Koyanagi, Stephen S. Raiman, Cristian I. Contescu, Jo Jo Lee, Xunxiang Hu, Ying Yang, Yutai Katoh |
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Rok vydání: | 2019 |
Předmět: |
Nuclear and High Energy Physics
Fission products Materials science Metallurgy 02 engineering and technology 021001 nanoscience & nanotechnology Ceramic matrix composite 01 natural sciences 010305 fluids & plasmas Corrosion chemistry.chemical_compound Nuclear Energy and Engineering chemistry Impurity 0103 physical sciences Silicon carbide General Materials Science Tritium 0210 nano-technology Absorption (electromagnetic radiation) Fluoride |
Zdroj: | Journal of Nuclear Materials. 524:119-134 |
ISSN: | 0022-3115 |
DOI: | 10.1016/j.jnucmat.2019.07.001 |
Popis: | Silicon carbide is widely appreciated for its high temperature strength, radiation tolerance and neutronic transparency in applications for fuel particles and core internals of nuclear reactors. In the Fluoride Salt-Cooled High Temperature Reactor, silicon carbide ceramic matrix composites are candidate construction material for regions of higher neutron fluxes. Silicon carbide is wettable and reacts electrochemically with dissolved metals. Metallic impurities, tritium, moisture-based impurities and fission products, as well as thermal gradients can accelerate hot corrosion of silicon carbide in molten fluoride salt. Tritium can become trapped in radiation defects of silicon carbide. Thus, an understanding of the potential for tritium absorption, impurities reactions and thermal gradient-assisted corrosion mechanisms along with tritium recovery and redox control systems are necessary to mitigate silicon carbide corrosion in molten fluoride salt systems. Here, we survey current research on silicon carbide corrosion in molten fluoride salts and critically evaluate the research and development gaps. |
Databáze: | OpenAIRE |
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