CLADDING DEGRADATION COMPONENT IN WASTE FORM DEGRADATION MODEL IN TSPA-SR

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The U.S. Department of Energy (DOE) has prepared a total system performance assessment for a site recommendation (TSPA-SR), if suitable, on Yucca Mountain for disposal of radioactive waste. Discussed here is the Cladding Degradation Component of the Waste Form Degradation Model (WF Model), of the TSPA-SR. The Cladding Degradation Component determines the degradation rate of the Zircaloy cladding on commercial spent nuclear fuel (CSNF) and, thereby, the CSNF matrix exposed and radioisotopes available for dissolution in any water present. Since the 1950s, most CSNF has been clad with less than 1 mm (usually between 600 and 900 {micro}m) of Zircaloy, ... continued below

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Siegmann, E. & Rechard, R.P. January 19, 2001.

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The U.S. Department of Energy (DOE) has prepared a total system performance assessment for a site recommendation (TSPA-SR), if suitable, on Yucca Mountain for disposal of radioactive waste. Discussed here is the Cladding Degradation Component of the Waste Form Degradation Model (WF Model), of the TSPA-SR. The Cladding Degradation Component determines the degradation rate of the Zircaloy cladding on commercial spent nuclear fuel (CSNF) and, thereby, the CSNF matrix exposed and radioisotopes available for dissolution in any water present. Since the 1950s, most CSNF has been clad with less than 1 mm (usually between 600 and 900 {micro}m) of Zircaloy, a zirconium alloy. Zircaloy cladding is not a designed engineered barrier of the Yucca Mountain disposal system, but rather is an existing characteristic of the CSNF that is important to determining the release rate of radioisotopes once the waste package (WP) has breached. Although studies of cladding degradation from fluoride [F] began at Lawrence Livermore National Laboratory as early as 1984, cladding as a characteristic of the waste was not considered in TSPAs, conducted in the early 1990s. However, enough information on cladding performance has accumulated in the literature such that cladding was considered in 1993 when examining the performance of DOE spent nuclear (DSNF) and most recently in TSPA for the viability assessment (TSPA-VA). The Nuclear Regulatory Commission (NRC) currently uses cladding data as the basis for extending the period of wet storage, for licensing dry storage facilities, and for licensing shipping casks for CNSF.

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  • Report No.: NA
  • Grant Number: NA
  • DOI: 10.2172/860279 | External Link
  • Office of Scientific & Technical Information Report Number: 860279
  • Archival Resource Key: ark:/67531/metadc781417

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 19, 2001

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

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  • Nov. 22, 2016, 10:27 p.m.

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Siegmann, E. & Rechard, R.P. CLADDING DEGRADATION COMPONENT IN WASTE FORM DEGRADATION MODEL IN TSPA-SR, report, January 19, 2001; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc781417/: accessed October 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.