Residual and Fission Gas Release from Uranium Dioxide

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Description

Abstract: Residual and fission gas release from UO2 were studied in the laboratory and in in-reactor experiments. Arc-fused powder and sintered pellets were used to determine the rate of evolution and types of residual gases as a function of temperature. Fission gas release was related to the average UO2 temperature and fission gas release calculations were made using the latest thermal conductivity values, isotopic half lives, and branching ratios available in the literature. The results obtained were compared with those available in the literature, and a satisfactory agreement was found among the groups of comparable data.

Physical Description

v, 36 pages ; illustrations.

Creation Information

Spalaris, C. N. & Megerth, F. H. July 15, 1963.

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Description

Abstract: Residual and fission gas release from UO2 were studied in the laboratory and in in-reactor experiments. Arc-fused powder and sintered pellets were used to determine the rate of evolution and types of residual gases as a function of temperature. Fission gas release was related to the average UO2 temperature and fission gas release calculations were made using the latest thermal conductivity values, isotopic half lives, and branching ratios available in the literature. The results obtained were compared with those available in the literature, and a satisfactory agreement was found among the groups of comparable data.

Physical Description

v, 36 pages ; illustrations.

Notes

Digitized from microopaque cards.

U.S. Atomic Energy Commission Contract AT(04-3)-189 Project Agreement 2.

Includes bibliographic references (pages 35-36).

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  • Report No.: GEAP-4314
  • Grant Number: AT(04-3)-189 PA 2
  • SuDoc Number: Y 3.At 7:22/GEAP-4314
  • Accession or Local Control No: metadc1201373
  • Archival Resource Key: ark:/67531/metadc1201373

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Technical Report Archive and Image Library

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.

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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Creation Date

  • July 15, 1963

Added to The UNT Digital Library

  • Aug. 15, 2019, 10:26 p.m.

Description Last Updated

  • June 4, 2020, 11:05 a.m.

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Spalaris, C. N. & Megerth, F. H. Residual and Fission Gas Release from Uranium Dioxide, report, July 15, 1963; San Jose, California.. (https://digital.library.unt.edu/ark:/67531/metadc1201373/: accessed February 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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