Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954
Description:
Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up …
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Date:
December 1, 1954
Creator:
Siegel, S. & Inman, G.M. eds.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department