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Virgiliev, Yu.S.; Avramenko, P.Ya.; Grebennik, V.N.; Kalyagina, I.P.; Lebedev, I.G.; Filimonov, V.A.; Shurshakova, T.N.
Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material1990
Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material1990
AbstractAbstract
[en] Internal reflector blocks for HTGR type reactors demand high strength requirements because of high operating temperature that should be fulfilled during the whole service life. Since the graphite used in RBMK type reactors does not fulfill these requirements, new materials were created on the basis of non-calcinate petroleum coke and cola-tar pitch as a binder. An experimental-industrial technology of producing graphite having strength properties exceeding 2.0 to 2.5 times those of the conventional graphite has been developed. The irradiation tests of the experimental graphite at 800 to 1400 deg K to the fluence of about 1.3 1022 n/cm2 confirmed the usefulness of that graphite for HTGR
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International Atomic Energy Agency, Vienna (Austria); 724 p; 1990; p. 711-724; Technical committee meeting on gas-cooled reactor technology safety and siting; Dimitrovgrad (Russian Federation); 21-23 Jun 1989; 7 refs, 6 figs, 2 tabs
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Report
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Conference
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