Open AccessTHE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS
Author(s) -
W.B. Cottrell,
C. Copenhaver,
H.N. Culver,
Mario Fontana,
V. J. Kelleghan,
G. Samuels
Publication year - 1959
Language(s) - English
Resource type - Reports
DOI - 10.2172/4265274
Subject(s) - nuclear engineering , graphite , helium , materials science , nuclear reactor , nuclear power , waste management , nuclear physics , physics , engineering , composite material , atomic physics