In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

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Description

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.

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iii, 43 p. : plates , graphs , tables ; 28 cm.

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Jenks, G. H. May 5, 1962.

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Description

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.

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iii, 43 p. : plates , graphs , tables ; 28 cm.

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  • OCLC: 702208779
  • SuDoc Number: Y 3.At 7:22/ORNL-2962
  • Report No.: ORNL-2962
  • Grant Number: W-7405-eng-26
  • Archival Resource Key: ark:/67531/metadc100456

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Technical Report Archive and Image Library

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  • May 5, 1962

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  • Sept. 25, 2014, 8:32 p.m.

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Jenks, G. H. In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C, report, May 5, 1962; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100456/: accessed May 24, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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