skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Clad Degradation- Summary and Abstraction for LA

Abstract

The purpose of this model report is to develop the summary cladding degradation abstraction that will be used in the Total System Performance Assessment for the License Application (TSPA-LA). Most civilian commercial nuclear fuel is encased in Zircaloy cladding. The model addressed in this report is intended to describe the postulated condition of commercial Zircaloy-clad fuel as a function of postclosure time after it is placed in the repository. Earlier total system performance assessments analyzed the waste form as exposed UO{sub 2}, which was available for degradation at the intrinsic dissolution rate. Water in the waste package quickly became saturated with many of the radionuclides, limiting their release rate. In the total system performance assessments for the Viability Assessment and the Site Recommendation, cladding was analyzed as part of the waste form, limiting the amount of fuel available at any time for degradation. The current model is divided into two stages. The first considers predisposal rod failures (most of which occur during reactor operation and associated activities) and postdisposal mechanical failure (from static loading of rocks) as mechanisms for perforating the cladding. Other fuel failure mechanisms including those caused by handling or transportation have been screened out (excluded) or aremore » treated elsewhere. All stainless-steel-clad fuel, which makes up a small percentage of the overall amount of fuel to be stored, is modeled as failed upon placement in the waste packages. The second stage of the degradation model is the splitting of the cladding from the reaction of water or moist air and UO{sub 2}. The splitting has been observed to be rapid in comparison to the total system performance assessment time steps and is modeled to be instantaneous. After the cladding splits, the rind buildup inside the cladding widens the split, increasing the diffusion area from the fuel rind to the waste package interior. This model report summarizes the component models, developed for the two stages noted above, that are used as inputs to TSPA-LA. The model concludes that less than two percent of the fuel, including all of the stainless-steel clad fuel, received at the repository is failed (perforated) upon receipt at the repository. All failed fuel is assumed to axially split upon waste package failure exposing the fuel to oxidation from the in-package environment. TSPA-LA then calculates the release of radionuclides from the exposed volume of oxidized fuel.« less

Authors:
Publication Date:
Research Org.:
Yucca Mountain Project, Las Vegas, NV (United States)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
837708
Report Number(s):
ANL-WIS-MD-000021, REV 01
DOC.20041004.0002, DC#43024; TRN: US0502882
DOE Contract Number:  
AC28-01RW12101
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Oct 2004
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; BUILDUP; DIFFUSION LENGTH; DISSOLUTION; LICENSE APPLICATIONS; NUCLEAR FUELS; OXIDATION; PERFORMANCE; RADIOISOTOPES; REACTOR OPERATION; VIABILITY; WASTE FORMS; WASTES; WATER; ZIRCALOY

Citation Formats

Stahl, D. Clad Degradation- Summary and Abstraction for LA. United States: N. p., 2004. Web. doi:10.2172/837708.
Stahl, D. Clad Degradation- Summary and Abstraction for LA. United States. https://doi.org/10.2172/837708
Stahl, D. 2004. "Clad Degradation- Summary and Abstraction for LA". United States. https://doi.org/10.2172/837708. https://www.osti.gov/servlets/purl/837708.
@article{osti_837708,
title = {Clad Degradation- Summary and Abstraction for LA},
author = {Stahl, D},
abstractNote = {The purpose of this model report is to develop the summary cladding degradation abstraction that will be used in the Total System Performance Assessment for the License Application (TSPA-LA). Most civilian commercial nuclear fuel is encased in Zircaloy cladding. The model addressed in this report is intended to describe the postulated condition of commercial Zircaloy-clad fuel as a function of postclosure time after it is placed in the repository. Earlier total system performance assessments analyzed the waste form as exposed UO{sub 2}, which was available for degradation at the intrinsic dissolution rate. Water in the waste package quickly became saturated with many of the radionuclides, limiting their release rate. In the total system performance assessments for the Viability Assessment and the Site Recommendation, cladding was analyzed as part of the waste form, limiting the amount of fuel available at any time for degradation. The current model is divided into two stages. The first considers predisposal rod failures (most of which occur during reactor operation and associated activities) and postdisposal mechanical failure (from static loading of rocks) as mechanisms for perforating the cladding. Other fuel failure mechanisms including those caused by handling or transportation have been screened out (excluded) or are treated elsewhere. All stainless-steel-clad fuel, which makes up a small percentage of the overall amount of fuel to be stored, is modeled as failed upon placement in the waste packages. The second stage of the degradation model is the splitting of the cladding from the reaction of water or moist air and UO{sub 2}. The splitting has been observed to be rapid in comparison to the total system performance assessment time steps and is modeled to be instantaneous. After the cladding splits, the rind buildup inside the cladding widens the split, increasing the diffusion area from the fuel rind to the waste package interior. This model report summarizes the component models, developed for the two stages noted above, that are used as inputs to TSPA-LA. The model concludes that less than two percent of the fuel, including all of the stainless-steel clad fuel, received at the repository is failed (perforated) upon receipt at the repository. All failed fuel is assumed to axially split upon waste package failure exposing the fuel to oxidation from the in-package environment. TSPA-LA then calculates the release of radionuclides from the exposed volume of oxidized fuel.},
doi = {10.2172/837708},
url = {https://www.osti.gov/biblio/837708}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Oct 01 00:00:00 EDT 2004},
month = {Fri Oct 01 00:00:00 EDT 2004}
}