Initial report on stress-corrosion-cracking experiments using Zircaloy-4 spent fuel cladding C-rings

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The Nevada Nuclear Waste Storage Investigations (NNWSI) Project is sponsoring C-ring stress corrosion cracking scoping experiments as a first step in evaluating the potential for stress corrosion cracking of spent fuel cladding in a potential tuff repository environment. The objective is to scope the approximate behavior so that more precise pressurized tube testing can be performed over an appropriate range of stress, without expanding the long-term effort needlessly. The experiment consists of stressing, by compression with a dead weight load, C-rings fabricated from spent fuel cladding exposed to an environment of Well J-13 water held at 90{degree}C. The results indicate ... continued below

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Smith, H.D. September 1, 1988.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 97 times , with 6 in the last month . More information about this report can be viewed below.

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  • Westinghouse Hanford Company
    Publisher Info: Westinghouse Hanford Co., Richland, WA (United States)
    Place of Publication: Richland, Washington

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The Nevada Nuclear Waste Storage Investigations (NNWSI) Project is sponsoring C-ring stress corrosion cracking scoping experiments as a first step in evaluating the potential for stress corrosion cracking of spent fuel cladding in a potential tuff repository environment. The objective is to scope the approximate behavior so that more precise pressurized tube testing can be performed over an appropriate range of stress, without expanding the long-term effort needlessly. The experiment consists of stressing, by compression with a dead weight load, C-rings fabricated from spent fuel cladding exposed to an environment of Well J-13 water held at 90{degree}C. The results indicate that stress corrosion cracking occurs at the high stress levels employed in the experiments. The cladding C-rings, tested at 90% of the stress at which elastic behavior is obtained in these specimens, broke in 25 to 64 d when tested in water. This was about one third of the time required for control tests to break in air. This is apparently the first observation of stress corrosion under the test conditions of relatively low temperature, benign environment but very high stress. The 150 ksi test stress could be applied as a result of the particular specimen geometry. By comparison, the uniaxial tensile yield stress is about 100 to 120 ksi and the ultimate stress is about 150 ksi. When a general model that fits the high stress results is extrapolated to lower stress levels, it indicates that the C-rings in experiments now running at {approximately}80% of the yield strength should take 200 to 225 d to break. 21 refs., 24 figs., 5 tabs.

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NTIS, PC A04/MF A01; OSTI as DE89000692

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  • Other Information: PBD: Sep 1988

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  • Other: DE89000692
  • Report No.: WHC-EP--0096
  • Grant Number: AC06-87RL10930
  • DOI: 10.2172/60497 | External Link
  • Office of Scientific & Technical Information Report Number: 60497
  • Archival Resource Key: ark:/67531/metadc691253

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Office of Scientific & Technical Information Technical Reports

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  • September 1, 1988

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  • Aug. 14, 2015, 8:43 a.m.

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  • Feb. 8, 2016, 2:43 p.m.

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Smith, H.D. Initial report on stress-corrosion-cracking experiments using Zircaloy-4 spent fuel cladding C-rings, report, September 1, 1988; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc691253/: accessed May 26, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.