Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Summary Report, July 1959 - September 1961

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Summary report discussing progress on the Fast Ceramic Reactor Development Program, a project to develop fast reactors employing ceramic fuels, especially mixed plutonium-uranium oxide.

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viii, 142 p. : ill. (some folded) ; 28 cm.

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Leitz, F. J. January 1963.

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Summary report discussing progress on the Fast Ceramic Reactor Development Program, a project to develop fast reactors employing ceramic fuels, especially mixed plutonium-uranium oxide.

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viii, 142 p. : ill. (some folded) ; 28 cm.

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  • OCLC: 853621528
  • Grant Number: AT(04-3)-189 PA #10
  • Report No.: GEAP-3811
  • Archival Resource Key: ark:/67531/metadc101065

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Technical Report Archive and Image Library

The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

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  • January 1963

Added to The UNT Digital Library

  • Feb. 26, 2015, 4:50 p.m.

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  • March 11, 2019, 3:03 p.m.

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Thumbnail image of item number 1 in: 'Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Summary Report, July 1959 - September 1961'.
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Leitz, F. J. Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Summary Report, July 1959 - September 1961, report, January 1963; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101065/: accessed July 21, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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