Graphite Materials for Nuclear Reactors

Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a rad...

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Bibliographic Details
Published inTANSO Vol. 1991; no. 150; pp. 338 - 353
Main Author Oku, Tatsuo
Format Journal Article
LanguageEnglish
Published THE CARBON SOCIETY OF JAPAN 1991
Subjects
Fission Reactor
Fusion Reactor
HTGR
Mechanical Properties
Nuclear Graphite
Physical Properties
Radiation Damage
Structural Design
Thermal Shock
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Summary:Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the sur-rounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related pro-perties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described.
ISSN:0371-5345
1884-5495
DOI:10.7209/tanso.1991.338