z-logo
open-access-imgOpen Access
THE 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

The content you want is available to Zendy users.

Already have an account? Click here to sign in.
Having issues? You can contact us here
Accelerating Research

Address

John Eccles House
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom