Published October 2019 | Version v1
Journal article

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

  • 1. Ridge National Laboratory, Oak Ridge, TN (United States)

Description

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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2019.07.001

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2019.07.001;
PII
S0022311518310341;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
524
Journal Page Range
p. 119-134
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Notes
© 2019 Elsevier B.V. All rights reserved.