A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

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Description

From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.

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33 p. : ill. ; 28 cm.

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Henrie, J. O. & Weisner, E. F. February 1, 1954.

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Description

From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.

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33 p. : ill. ; 28 cm.

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  • OCLC: 902730513
  • Report No.: NAA-SR-283
  • Grant Number: AT-11-1-GEN-8
  • Archival Resource Key: ark:/67531/metadc303801

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Technical Report Archive and Image Library

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Creation Date

  • February 1, 1954

Added to The UNT Digital Library

  • July 8, 2016, 8:07 p.m.

Description Last Updated

  • Aug. 5, 2016, 9:39 a.m.

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Henrie, J. O. & Weisner, E. F. A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor, report, February 1, 1954; Downey, California. (https://digital.library.unt.edu/ark:/67531/metadc303801/: accessed October 3, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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