Fuel Element Development Program for the Pebble Bed Reactor

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Description

Previous results from the Pebble Bed Reactor Fuel Element Development Program had shown the excellent promise of vapor-deposited Al2O3 doq5intw on UO2 particles as a low permeability high temperature fission product barrier. However, since the matrix material for the PBR fuel element is a graphite sphere, carbonaceous coatings on the dispersed fuel particles might be of more interest because of improved particle coating-matrix compatibility and no displacement of neutron moderating materials. Since a pyrolytic carbon coating also appeared to be low permeability higt temperature material, emphasis was placed on the development of pyrolytic carbon coated UC2 particles dispersed in a … continued below

Physical Description

25 pages : illustrations, tables, photographs

Creation Information

Sanderson & Porter, Inc. 1961.

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Titles

  • Main Title: Fuel Element Development Program for the Pebble Bed Reactor
  • Added Title: Quarterly Progress Report, November 1, 1960 to January 31, 1961
  • Series Title: NYO (Series) (New York)
  • Series Title: Atomic Energy Commission Reports
  • Added Title: Atomic Energy Commission Report NYO-9063

Description

Previous results from the Pebble Bed Reactor Fuel Element Development Program had shown the excellent promise of vapor-deposited Al2O3 doq5intw on UO2 particles as a low permeability high temperature fission product barrier. However, since the matrix material for the PBR fuel element is a graphite sphere, carbonaceous coatings on the dispersed fuel particles might be of more interest because of improved particle coating-matrix compatibility and no displacement of neutron moderating materials. Since a pyrolytic carbon coating also appeared to be low permeability higt temperature material, emphasis was placed on the development of pyrolytic carbon coated UC2 particles dispersed in a graphite sphere as the reference PBR fuel element.

Physical Description

25 pages : illustrations, tables, photographs

Notes

Digitized from microopaque cards (1).

Work performed under AEC contract AT)30-0)-2378.

AEC Research and Development Report UC-25, Metallurgy & Ceramics.

TID 4500, 16th Ed.

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  • OCLC: #
  • SuDoc Number: Y 3.At 7:22/NYO-9063
  • Report No.: NYO-9063
  • Accession or Local Control No: metadc1463129
  • Archival Resource Key: ark:/67531/metadc1463129

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TRAIL Microcard Collection

Imaged from microcard, these technical reports describe research performed for U.S. government agencies from the 1930s to the 1960s. The reports were provided by the Technical Report Archive and Image Library (TRAIL).

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  • 1961

Added to The UNT Digital Library

  • Sept. 2, 2021, 4:26 p.m.

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  • Jan. 5, 2023, 4:42 p.m.

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Sanderson & Porter, Inc. Fuel Element Development Program for the Pebble Bed Reactor, report, 1961; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc1463129/: accessed May 23, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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