Evaluation Of Calandria Thimble And Canned Moderator Concepts For Sodium Graphite Reactors
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EVALUATION OF CALANDRIA, THIMBLE, AND CANNED-MODERATOR CONCEPTS FOR SODIUM GRAPHITE REACTORS.
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Total Pages | : |
Release | : 1960 |
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In efforts to improve the neutron economy and lower the capital costs of sodium graphite reactors, several methods of separating the sodium and graphite were investigated including the calandria, the thimble, and the canned moderator reactors. An analysis including nuclear, heat transfer, and economic comparisons was made of these SGR concepts. Based upon neutron economy and feasibility of core fabrication, the calandria concept appears to offer the greatest potential for improvement in 8GR design. The thimble concept provides some improvement in neutron economy but introduced numerous problems requiring developmental work. (auth).
Fuel Burnup Studies for a 255 Mwe Advanced Sodium Graphite Reactor
Author | : A. L. Aronson |
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Total Pages | : 74 |
Release | : 1960 |
Genre | : Fuel burnup (Nuclear engineering) |
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Atomic Energy Research Reports for Sale by the U.S. Department of Commerce, Office of Technical Services
Author | : Business and Defense Services Administration |
Publisher | : |
Total Pages | : 68 |
Release | : 1963 |
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