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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  • 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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  • 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 April 28, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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