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Conference Article: Specific behavior of reflector and matrix graphite under high temperature irradiation

Platonov, P.A.; Karpukhin, V.I.; Shtrombakh, Ya.I.; Alekseev, V.M.; Chugunov, O.K.; Gurovich, B.A.; Trofimchuk, E.I. (I.V. Kurchatov Inst. of Atomic Energy, Moscow (Russian Federation). Dept. of Research Reactors and Technology)

Abstract

Physical properties for reflector and matrix graphite for the VG-400 VGM reactors being developed in the USSR are reported. Three types of graphite have been investigated. These are: the graphite based on uncalcinated coke - KPG and MPC. The graphite based on the special coke - GR1. And the graphite for spherical fuel elements - molded graphite (KPD) and graphite binded by pyrocarbon (GSP). Specimens of these graphites have been irradiated up to a neutron fluence of 0.5 to 2.5x1022 neutron/cm2. The dependence of the following on fluence is reported: relative volume change, Young's modulus, dimensional change, elastic modulus, electrical resistivity, thermal conductivity and the coefficient of thermal expansion.

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key words: coke; dimensions; elasticity; electric conductivity; neutron fluence; neutron reflectors; physical radiation effects; reactor cores; thermal conductivity; thermal expansion; variations; vg-400 reactor; volume; young modulus; electrical properties; enriched uranium reactors; expansion; gas cooled reactors; graphite moderated reactors; helium cooled reactors; homogeneous reactors; htgr type reactors; mechanical properties; pebble bed reactors; physical properties; power reactors; radiation effects; reactor components; solid homogeneous reactors; thermal reactors; thermodynamic properties
Reference:
Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--690, pp:205-209