Open AccessMechanical properties of graphite for high-temperature gas-cooled reactors: a review
Author(s) -
R.J. Price
Publication year - 1975
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4166104
Subject(s) - graphite , creep , materials science , irradiation , nuclear engineering , composite material , nuclear physics , engineering , physics
Experimental data on the mechanical properties of reactor graphites (excluding irradiation creep and fatigue) under High-Temperature Gas-Cooled Reactor (HTGR) conditions are reviewed. Based on an assessment of the literature, recommendations are made for design-basis values for the elastic properties and strength of irradiated graphite, and failure criteria are suggested for particular loading conditions. 78 references. (auth
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