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

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A design study is presented for a sodium cooled, 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 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg ... continued below

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Pages: 138

Creation Information

Weisner, E. F. September 15, 1954.

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Description

A design study is presented for a sodium cooled, 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 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)

Physical Description

Pages: 138

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NTIS

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  • Other Information: Decl. Mar. 4, 1957. Orig. Receipt Date: 31-DEC-58

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  • Report No.: NAA-SR-1028
  • Grant Number: AT-11-1-GEN-8
  • DOI: 10.2172/4350786 | External Link
  • Office of Scientific & Technical Information Report Number: 4350786
  • Archival Resource Key: ark:/67531/metadc1016014

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • September 15, 1954

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 22, 2018, 11:36 a.m.

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Weisner, E. F. A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power, report, September 15, 1954; Downey, California. (digital.library.unt.edu/ark:/67531/metadc1016014/: accessed September 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.