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Conference Article: Matrix graphite for HTGR spherical fuel elements some their properties

Chernikov, A.S.; Mozzherin, S.I.; Reshetnikov, V.A. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)

Abstract

The results of investigations on matrix graphites for HTGR spherical fuel elements are presented, with two types of artificial carbon materials (coarse-grain anisotropic graphite 30PG and fine-grain isotropic MPG-6) and coal-tar pitch taken as an example. The data are given on physical-mechanical and thermal-physical characteristics and on the rate of corrosion of matrix materials in the stage of both pre- and post-irradiation (for the material based on graphite 30PG) investigations. The variations in the anisotropy of the main properties of matrix graphites have been determined depending on type of graphite filler. It is concluded that the matrix graphite characteristics attained mainly agree with the requirements for the fuel elements of the VGR-50 and VG-400 reactors under development.

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key words: anisotropy; coated fuel particles; corrosion; electric conductivity; flexural strength; fuel elements; graphite; htgr type reactors; isotropy; matrix materials; physical radiation effects; post-irradiation examination; spherical configuration; thermal conductivity; carbon; chemical reactions; configuration; electrical properties; fuel particles; gas cooled reactors; graphite moderated reactors; materials; mechanical properties; physical properties; radiation effects; reactor components; reactors; thermodynamic properties
Reference:
Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--11, pp:207-212