HTGR Knowledge Base
Conference Article: Structural graphite for high-temperature gas-cooled reactors
Virgiliev, Yu.S.; Avramenko, P.Ya.; Grebennik, V.N.; Kalyagina, I.P.; Lebedev, I.G.; Filimonov, V.A.; Shurshakova, T.NAbstract
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key words: graphite; htgr type reactors; mechanical properties; mechanical tests; neutron flux; radiation effects; reactor components; tensile properties; thermal testing
- Reference:
- Technical committee meeting on gas-cooled reactor technology safety and siting Dimitrovgrad (Russian Federation) 21-23 Jun 1989
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TC--389.26, pp:711-724
- International Atomic Energy Agency, Vienna (Austria)