The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements Page: Front Cover
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Reactors - Power
TID-4500 (14th ed.)
A DESIGN STUDY OF A NUCLEAR POWER STATION
EMPLOYING A HIGH-TEMPERATURE GAS-COOLED REACTOR
WITH GRAPHITE-UO2 FUEL ELEMENTS
W. B. Cottrell
C. M. Copenhaver
H. N. Culver
M. H. Fontana
V. J. Kelleghan
OAK RIDGE NATIONAL LABORATORY
UNION CARBIDE CORPORATION
U.S. ATOMIC ENERGY COMMISSION
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Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G. The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements, report, 1959; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc100279/m1/1/: accessed November 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.