The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements

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Description

The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.

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36 pages : illustrations

Creation Information

Reynolds, M. B. January 23, 1963.

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The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.

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36 pages : illustrations

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Digitized from microopaque cards (2).

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  • Report No.: GEAP-4135
  • SuDoc Number: Y 3.At 7:22/GEAP-4135
  • Accession or Local Control No: metadc1258022
  • Archival Resource Key: ark:/67531/metadc1258022

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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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The Technical Report Archive & Image Library (TRAIL) identifies, acquires, catalogs, digitizes and provides unrestricted access to U.S. government agency technical reports. The mission of TRAIL is to ensure preservation, discoverability, and persistent open access to government technical publications regardless of form or format.

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  • January 23, 1963

Added to The UNT Digital Library

  • May 24, 2022, 6:15 a.m.

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  • April 23, 2024, 5:03 p.m.

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Reynolds, M. B. The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements, report, January 23, 1963; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1258022/: accessed June 18, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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