Graphite Materials for Nuclear Reactors

• Published in: TANSO Vol. 1991; no. 150; pp. 338 - 353
• Main Author: Oku, Tatsuo
• Format: Journal Article
• Language: English
• 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

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...