In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

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Description

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.

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iii, 69 p. : ill. ; 28 cm.

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Jenks, G. H. June 10, 1963.

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In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.

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iii, 69 p. : ill. ; 28 cm.

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  • OCLC: 85272069
  • SuDoc Number: Y 3.At 7:22/ORNL-3099
  • Report No.: ORNL-3099
  • Archival Resource Key: ark:/67531/metadc100461

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Technical Report Archive and Image Library

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  • June 10, 1963

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  • Sept. 25, 2014, 8:32 p.m.

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Jenks, G. H. In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C, report, June 10, 1963; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100461/: accessed April 19, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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