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Title: Conference Presentation: Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain.

Abstract

Abstract not provided.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sandia National Laboratories, Las Vegas, NV
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1264076
Report Number(s):
SAND2006-2977C
525702
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the 2006 International High Level Radioactive Waste Management Conference held May 1-5, 2006 in Las Vegas, NV.
Country of Publication:
United States
Language:
English

Citation Formats

Mackinnon, Robert James, Sevougian, S. David, Mattie, Patrick D., Jain, Vivek, and Mon, Kevin G.. Conference Presentation: Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain.. United States: N. p., 2006. Web.
Mackinnon, Robert James, Sevougian, S. David, Mattie, Patrick D., Jain, Vivek, & Mon, Kevin G.. Conference Presentation: Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain.. United States.
Mackinnon, Robert James, Sevougian, S. David, Mattie, Patrick D., Jain, Vivek, and Mon, Kevin G.. Mon . "Conference Presentation: Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain.". United States. doi:. https://www.osti.gov/servlets/purl/1264076.
@article{osti_1264076,
title = {Conference Presentation: Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain.},
author = {Mackinnon, Robert James and Sevougian, S. David and Mattie, Patrick D. and Jain, Vivek and Mon, Kevin G.},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 01 00:00:00 EDT 2006},
month = {Mon May 01 00:00:00 EDT 2006}
}

Conference:
Other availability
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  • A total system performance assessment (TSPA) model has been developed to analyze the ability of the natural and engineered barriers of the Yucca Mountain repository to isolate nuclear waste over the 10,000-year period following repository closure. The principal features of the engineered barrier system (EBS) are emplacement tunnels (or ''drifts'') containing a two-layer waste package (WP) for waste containment and a titanium drip shield to protect the waste package from seeping water and falling rock, The 20-mm-thick outer shell of the WP is composed of Alloy 22, a highly corrosion-resistant nickel-based alloy. The barrier function of the EBS is tomore » isolate the waste from migrating water. The water and its associated chemical conditions eventually lead to degradation of the waste packages and mobilization of the radionuclides within the packages. There are five possible waste package degradation modes of the Alloy 22: general corrosion, microbially influenced corrosion, stress corrosion cracking, early failure due to manufacturing defects, and localized corrosion. This paper specifically examines the incorporation of the Alloy-22 localized corrosion model into the Yucca Mountain TSPA model, particularly the abstraction and modeling methodology, as well as issues dealing with scaling, spatial variability, uncertainty, and coupling to other sub-models that are part of the total system model.« less
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  • Abstract not provided.
  • Improvements have been made to the fracture-flow model being used in the total-system performance assessment of a potential high-level radioactive waste repository at Yucca Mountain, Nevada. The {open_quotes}weeps model{close_quotes} now includes (1) weeps of varied sizes, (2) flow-pattern fluctuations caused by climate change, and (3) flow-pattern perturbations caused by repository heat generation. Comparison with the original weeps model indicates that allowing weeps of varied sizes substantially reduces the number of weeps and the number of containers contacted by weeps. However, flow-pattern perturbations caused by either climate change or repository heat generation greatly increases the number of containers contacted by weeps.more » In preliminary total-system calculations, using a phenomenological container-failure and radionuclide-release model, the weeps model predicts that radionuclide releases from a high-level radioactive waste repository at Yucca Mountain will be below the EPA standard specified in 40 CFR 191, but that the maximum radiation dose to an individual could be significant. Specific data from the site are required to determine the validity of the weep-flow mechanism and to better determine the parameters to which the dose calculation is sensitive.« less