Open AccessGraphite for helium-cooled reactors. A review
Author(s) -
G.L. Tingey,
W.C. Morgan
Publication year - 1972
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4441496
Subject(s) - nuclear engineering , backup , containment (computer programming) , waste management , breeder (animal) , environmental science , engineering , materials science , blanket , mechanical engineering , computer science , programming language , composite material
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