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Title: Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor

Abstract

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. Furthermore, we survey current research on silicon carbide corrosion in molten fluoride salts and critically evaluate the research and development gaps.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1531263
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 524; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE

Citation Formats

Lee, Jo Jo, Raiman, Stephen S., Katoh, Yutai, Koyanagi, Takaaki, Contescu, Cristian I., Hu, Xunxiang, and Yang, Ying. Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor. United States: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.07.001.
Lee, Jo Jo, Raiman, Stephen S., Katoh, Yutai, Koyanagi, Takaaki, Contescu, Cristian I., Hu, Xunxiang, & Yang, Ying. Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor. United States. doi:10.1016/j.jnucmat.2019.07.001.
Lee, Jo Jo, Raiman, Stephen S., Katoh, Yutai, Koyanagi, Takaaki, Contescu, Cristian I., Hu, Xunxiang, and Yang, Ying. Tue . "Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor". United States. doi:10.1016/j.jnucmat.2019.07.001.
@article{osti_1531263,
title = {Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor},
author = {Lee, Jo Jo and Raiman, Stephen S. and Katoh, Yutai and Koyanagi, Takaaki and Contescu, Cristian I. and Hu, Xunxiang and Yang, Ying},
abstractNote = {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. Furthermore, we survey current research on silicon carbide corrosion in molten fluoride salts and critically evaluate the research and development gaps.},
doi = {10.1016/j.jnucmat.2019.07.001},
journal = {Journal of Nuclear Materials},
number = C,
volume = 524,
place = {United States},
year = {2019},
month = {7}
}

Journal Article:
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This content will become publicly available on July 2, 2020
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