A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

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Description

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees … continued below

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138 p. : ill., tables

Creation Information

Weisner, Edward F. September 15, 1954.

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Description

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."

Physical Description

138 p. : ill., tables

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Digitized from microopaque cards (5).

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  • OCLC: 1061334078
  • SuDoc Number: Y 3.At 7:22/NAA-SR-1028
  • Report No.: NAA-SR-1028
  • Accession or Local Control No: metadc1250157
  • Archival Resource Key: ark:/67531/metadc1250157

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  • September 15, 1954

Added to The UNT Digital Library

  • Aug. 10, 2021, 7:36 a.m.

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  • March 16, 2022, 4:22 p.m.

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Weisner, Edward F. A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power, report, September 15, 1954; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc1250157/: accessed November 9, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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