Sodium Graphite Reactor, Quarterly Progress Report, December 1953 - February 1954
Description:
"Engineering pertinent to the development of the sodium-cooled, graphite-moderated type of reactor was continued. This included work on problems related to the zirconium canned moderator, low enrichment uranium fuel, sodium piping, secondary coolant system, shielding, and the control and safety elements. A large fraction of the work was devoted specifically to problems of the proposed Sodium Reactor Experiment (SRE) configuration. In this connection, an integrated effort was initiated to pre…
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Date:
August 1, 1954
Creator:
Inman, G. M.
Partner:
UNT Libraries Government Documents Department