Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference15 articles.
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3. Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane;Journal of the European Ceramic Society;2018-02
4. Design parameters in an annular, prismatic HTGR for passive decay heat removal;Annals of Nuclear Energy;2018-01
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