HTGR Knowledge Base

Conference Article: Russian graphite nuclear application. History, state of the art, future

Platonov, P.; Shtrombakh, Ya.; Chugunov, O.; Kaprukhin, V.; Manevski, V.; Alexeev, V. (Russian Research Centre Kurchatov Inst., Moscow (Russian Federation))

Abstract

Near 40 nuclear reactors based on graphite moderator were built in Russia during 50 years. They are: RBMK, AMB, production reactors. Reactor graphites grades GR-220, GR-280, EGP-6, GR-94, GRP-2-125 were used for this reactors construction. Some grades of new graphites were developed on the Russian HTGR program such as GR-1 showing best radiation stability. About 20 reactors were stopped due to exhaust of cladding recourses and/or metalwork structures and other reactor systems. Production reactors (AI, AD, AV types) graphite claddings must be dismounting but at the present time this work is in preliminary study stage. These reactors will not be demolished during 30 years. The waste recovery program is developing now. There are two possible ways to reclaim graphite products: to burn in special furnaces. To keep them in containers under special preserve compound. At the same time it is very important to define the impurities in graphite claddings half-life in order to determine minimal period before its processing and conservation.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Technical committee meeting on technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. Juelich (Germany) 8-10 Sep 1997
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1043, pp:269-274