Stress Corrosion Cracking Model for High Level Radioactive-Waste Packages

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A stress corrosion cracking (SCC) model has been adapted for performance prediction of high level radioactive-waste packages to be emplaced in the proposed Yucca Mountain repository. For waste packages of the proposed Yucca Mountain repository, the outer barrier material is the highly corrosion-resistant Alloy UNS-N06022 (Alloy 22), the environment is represented by aqueous brine films present on the surface of the waste package from dripping or deliquescence of soluble salts present in any surface deposits, and the tensile stress is principally from weld induced residual stress. SCC has historically been separated into ''initiation'' and ''propagation'' phases. Initiation of SCC will ... continued below

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13 pages

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Andresen, P.; Gordon, G. & Lu, S. October 5, 2004.

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Description

A stress corrosion cracking (SCC) model has been adapted for performance prediction of high level radioactive-waste packages to be emplaced in the proposed Yucca Mountain repository. For waste packages of the proposed Yucca Mountain repository, the outer barrier material is the highly corrosion-resistant Alloy UNS-N06022 (Alloy 22), the environment is represented by aqueous brine films present on the surface of the waste package from dripping or deliquescence of soluble salts present in any surface deposits, and the tensile stress is principally from weld induced residual stress. SCC has historically been separated into ''initiation'' and ''propagation'' phases. Initiation of SCC will not occur on a smooth surface if the surface stress is below a threshold value defined as the threshold stress. Cracks can also initiate at and propagate from flaws (or defects) resulting from manufacturing processes (such as welding); or that develop from corrosion processes such as pitting or dissolution of inclusions. To account for crack propagation, the slip dissolution/film rupture (SDFR) model is adopted to provide mathematical formulae for prediction of the crack growth rate. Once the crack growth rate at an initiated SCC is determined, it can be used by the performance assessment to determine the time to through-wall penetration for the waste package. This paper presents the development of the SDFR crack growth rate model based on technical information in the literature as well as experimentally determined crack growth rates developed specifically for Alloy UNS-N06022 in environments relevant to high level radioactive-waste packages of the proposed Yucca Mountain radioactive-waste repository. In addition, a seismic damage related SCC crack opening area density model is briefly described.

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13 pages

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INIS; OSTI as DE00837706

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  • Other Information: PBD: 5 Oct 2004

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  • Report No.: NONE
  • Grant Number: NONE
  • DOI: 10.2172/837706 | External Link
  • Office of Scientific & Technical Information Report Number: 837706
  • Archival Resource Key: ark:/67531/metadc776955

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  • October 5, 2004

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  • Dec. 3, 2015, 9:30 a.m.

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  • Feb. 11, 2016, 1:07 p.m.

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Andresen, P.; Gordon, G. & Lu, S. Stress Corrosion Cracking Model for High Level Radioactive-Waste Packages, report, October 5, 2004; Las Vegas, Nevada. (digital.library.unt.edu/ark:/67531/metadc776955/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.