Hostname: page-component-7479d7b7d-rvbq7 Total loading time: 0 Render date: 2024-07-12T21:17:26.704Z Has data issue: false hasContentIssue false
  • English
  • Français

Integrated Analysis for Long-Term Degradation of Waste Package at the Potential Yucca Mountain Repository for High-Level Nuclear Waste Disposal

Published online by Cambridge University Press:  21 March 2011

Joon H. Lee ,
Kevin G. Mon ,
Dennis E. Longsine ,
Bryan E. Bullard  and
Ahmed M. Moniba
Joon H. Lee
Affiliation:
Sandia National Laboratories, 1180 Town Center Drive, Las Vegas, NV 89144
Kevin G. Mon
Affiliation:
Duke Engineering & Services, 1180 Town Center Drive, Las Vegas, NV 89144
Dennis E. Longsine
Affiliation:
Duke Engineering & Services, 9111 Research Blvd., Austin, TX 78758
Bryan E. Bullard
Affiliation:
Duke Engineering & Services, 1180 Town Center Drive, Las Vegas, NV 89144
Ahmed M. Moniba
Affiliation:
Bechtel-SAIC, 1180 Town Center Drive, Las Vegas, NV 89144
Get access

Abstract

The technical basis for Site Recommendation (SR) of the potential repository for high-level nuclear waste at Yucca Mountain, Nevada has been completed. Long-term containment of the waste and subsequent slow release of radionuclides from the engineered barrier system (EBS) into the geosphere will rely on a robust waste package (WP) design, among other EBS components as well as the natural barrier system. The WP and drip shield (DS) degradation analyses for the total system performance assessment (TSPA) baseline model for the SR have shown that, based on the current corrosion models and assumptions, both the DSs and WPs do not fail within the regulatory compliance time period (10,000 years). From the perspective of initial WP failure time, the analysis results are encouraging because the upper bounds of the baseline case are likely to represent the worst case combination of key corrosion model parameters that significantly affect long-term performance of WPs in the potential repository. The estimated long life-time of the WPs in the current analysis is attributed mostly to the following two factors that delay the onset of stress corrosion cracking (SCC): (1) the stress mitigation to substantial depths from the outer surface in the dual closure-lid weld regions; and (2) the very low general-corrosion rate applied to the closure-lid weld regions to corrode the compressive stress zones. Uncertainties are associated with the current WP SCC analysis. These are stress mitigation on the closure-lid welds, characterization of manufacturing flaws applied to SCC, and general corrosion rate applied to the closurelid weld regions. These uncertainties are expected to be reduced as additional data and analyses are developed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 713: Symposium JJ – Scientific Basis for Nuclear Waste Management XXV , 2002 , JJ1.7
Copyright
Copyright © Materials Research Society 2002

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Lee, J.H., Atkins, J.E., and andrews, R.W., in Scientific Basis for Nuclear Waste Management XIX, edited by Murphy, W.M. and Knecht, D.A., (Mater. Res. Soc. Proc. 412, Pittsburgh, PA, 1996) pp. 603–611.Google Scholar
2. Atkins, J.E., Lee, J.H., and andrews, R.W., in Proc. of 7th International Conference on the High-Level Radioactive Waste Management, Am. Nucl. Soc., LaGrange Park, IL and Am. Soc. of Civil Engrs., New York, NY, pp. 459–461 (1996).Google Scholar
3. Lee, J.H., Atkins, J.E., and Dunlap, B., in Scientific Basis for Nuclear Waste Management XX, edited by Gray, W.J. and Triay, I.R., (Mater. Res. Soc. Proc. 465, Pittsburgh, PA, 1997) pp. 1075–1082.Google Scholar
4. Lee, J.H., Mon, K.G., Longsine, D.E., and Bullard, B.E., in Scientific Basis for Nuclear Waste Management XXII, edited by Wronkiewicz, D.J. and Lee, J.H., (Mater. Res. Soc. Proc. 556, Pittsburgh, PA, 1999) pp. 567–574.Google Scholar
5. Lee, J.H., Mon, K.G., Longsine, D.E., and Bullard, B.E., in Scientific Basis for Nuclear Waste Management XXII, edited by Wronkiewicz, D.J. and Lee, J.H., (Mater. Res. Soc. Proc. 556, Pittsburgh, PA, 1999) pp. 515–523.Google Scholar
6. CRWMS M&O, Total System Performance Assessment-1995: An Evaluation of the Potential Yucca Mountain Repository, B00000000-01717-2200-00136 Rev. 01, Las Vegas, NV (1995).Google Scholar
7. CRWMS M&O, Total System Performance Assessment-Viability Assessment (TSPA-VA) Analyses Technical Basis Document: Chapter 5 Waste Package Degradation Modeling and Abstraction, B0000000001717-430100005 REV 01, Las Vegas, NV (1998).Google Scholar
8. CRWMS M&O, Waste Package Degradation Process Model Report, TDR-WIS-MD-000002 REV 00 ICN 02, Las Vegas, NV (2000).Google Scholar
9. CRWMS M&O, WAPDEG Analysis of Waste Package and Drip Shield Degradation, ANL-EBS-PA-000001 REV 00 ICN 01, Las Vegas, NV (2000).Google Scholar