Sodium Graphite Reactor, Quarterly Progress Report, December 1953 - February 1954

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Description

"Engineering pertinent to the development of the sodium-cooled, graphite-moderated type of reactor was continued. This included work on problems related to the zirconium canned moderator, low enrichment uranium fuel, sodium piping, secondary coolant system, shielding, and the control and safety elements. A large fraction of the work was devoted specifically to problems of the proposed Sodium Reactor Experiment (SRE) configuration. In this connection, an integrated effort was initiated to prepare a complete preliminary design of the SRE by an early date. In addition, two alternate sodium-graphite reactor configurations were studied. One was an intermediate size, 145 thermal megawatt, unit optimized … continued below

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71 p. : ill., tables

Creation Information

Inman, G. M. August 1, 1954.

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This report is part of the collection entitled: TRAIL Microcard Collection and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 15 times, with 9 in the last month. More information about this report can be viewed below.

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"Engineering pertinent to the development of the sodium-cooled, graphite-moderated type of reactor was continued. This included work on problems related to the zirconium canned moderator, low enrichment uranium fuel, sodium piping, secondary coolant system, shielding, and the control and safety elements. A large fraction of the work was devoted specifically to problems of the proposed Sodium Reactor Experiment (SRE) configuration. In this connection, an integrated effort was initiated to prepare a complete preliminary design of the SRE by an early date. In addition, two alternate sodium-graphite reactor configurations were studied. One was an intermediate size, 145 thermal megawatt, unit optimized for the production of low cost plutonium. The second was a low power 10 thermal megawatt intended for power production, but in which sodium circulation through the core was entirely dependent upon thermal convection."

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71 p. : ill., tables

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Digitized from microopaque cards (3).

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  • OCLC: 491171378
  • SuDoc Number: Y 3.At 7:22/NAA-SR-1027
  • Report No.: NAA-SR-1027
  • Accession or Local Control No: metadc1250156
  • Archival Resource Key: ark:/67531/metadc1250156

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  • August 1, 1954

Added to The UNT Digital Library

  • Aug. 10, 2021, 7:36 a.m.

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  • March 16, 2022, 3:40 p.m.

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Inman, G. M. Sodium Graphite Reactor, Quarterly Progress Report, December 1953 - February 1954, report, August 1, 1954; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc1250156/: accessed August 15, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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