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Very Long-Term Dry Storage Systems for Spent Nuclear Fuel: Effect of Canister Weld Corrosion on System Integrity

Published online by Cambridge University Press:  23 March 2012

Carlos A. W. Di Bella ,
David J. Duquette  and
Douglas B. Rigby
Carlos A. W. Di Bella
Affiliation:
U.S. Nuclear Waste Technical Review Board, 2300 Clarendon Blvd. Suite 1300, Arlington, VA 22201 U.S.A.
David J. Duquette
Affiliation:
Department of Materials Science & Engineering, Rensselaer Polytechnic Institute, 110 Eighth Street, Troy, NY 12180 U.S.A.
Douglas B. Rigby
Affiliation:
U.S. Nuclear Waste Technical Review Board, 2300 Clarendon Blvd. Suite 1300, Arlington, VA 22201 U.S.A.
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Abstract

Termination of the Yucca Mountain repository program implies that U.S. spent nuclear fuel (SNF) and high-level radioactive waste may be stored for very long periods, i.e., more than 100 years. Many of the storage systems for commercial SNF are large, cylindrical, welded, stainless-steel canisters containing 24-80 SNF assemblies in an inert gas (helium) environment. Each canister is contained in a massive reinforced concrete structure for shielding, safety, and security reasons. Airflow in the annular space between the canister and the concrete structure removes SNF decay heat by natural convection.

Undetected defects in the canister-lid welds and stress corrosion cracking (SCC) in the canister-lid weld area may combine to form pathways for slow escape of the inert fill gas from the canister. SCC may not occur until many decades after SNF is loaded into the canister because SNF decay heat initially would keep the canister surface temperatures above the temperature where liquid water, a prerequisite for SCC, could condense. The period required for inert gas to escape from the canister once pathways have formed and for air subsequently to enter the canister may also be measured in decades, depending on the size and shape of the pathways.

In this paper, the authors explore the limits of weld-flaw detectability; when necessary conditions for SCC could occur in the canister-lid weld area; the period for loss of inert fill gas if through-weld cracks occur; and the possible consequences of fill gas loss. The authors also develop a list of research and study needs to address the possibility of SCC resulting in the loss of fill gas.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-o52
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1 Kessler, J., “ Used Fuel Extended Storage: What the U.S. Industry Wants from DOE,” presentation at the NEI Used Fuel Management Conference , Baltimore, MD, May 4, 2011, available at www.NEI.org.Google Scholar
2 Blue Ribbon Commission on America’s Nuclear Future Draft Report to the Secretary of Energy, July 29, 2011, available at www.brc.gov.Google Scholar
3 NRC file graphic, http://www.nrc.gov/images/reading-rm/photo-gallery/20100907-138.jpg Google Scholar
4 NRC, Division of Spent Fuel Storage and Transportation Interim Staff Guidance – ISG-18, Rev.1, October 3, 2008, downloaded from http://www.nrc.gov/reading-rm/doc-collections/isg/isg-18r1.pdf on August 24, 2011 Google Scholar
5 NRC, Spent Fuel Project Office Interim Staff Guidance – ISG-15, January 10, 2001, downloaded from http://www.nrc.gov/reading-rm/doc-collections/isg/isg-15.pdf on August 24, 2011 Google Scholar
6 Uhlig, H. H., Corrosion and Corrosion Control, John Wiley and Sons, New York, 2 nd Edition, 1971, particularly Chapter 7 Google Scholar
7 Jones, D. A., Principles and Prevention of Corrosion, Prentice-Hall, Inc., Upper Saddle River, NJ, 2 nd edition, 1996, particularly Chapter 8.Google Scholar
8 Caseres, A. L. and Mintz, T.S., Atmospheric Stress Corrosion Cracking Susceptibility of Welded and Unwelded 304, 304L, and 316L Austenitic Stainless Steels Commonly Used for Dry Cask Storage Containers Exposed to Marine Environments, NUREG/CR-7030, October 2010 Google Scholar
9 Gdowski, G.E., “ Waste Package Corrosion Process Components,” presentation to the Nuclear Waste Technical Review Board , Las Vegas, NV, June 21, 2001, available at www.nwtrb.gov Google Scholar
10 Casella, A. M., Modeling of Molecular and Particulate Transport in Dry Spent Nuclear Fuel Canisters, dissertation presented to the faculty of the Graduate School Nuclear Science and Engineering Institute University of Missouri-Columbia, August 2007 Google Scholar
11 Einziger, R. and Kessler, J., Technical Bases for Extended Dry Storage of Spent Nuclear Fuel, Electric Power Research Institute, Palo Alto, CA, 1003416, 2002 Google Scholar
12 See 76 FR 8890, Feb. 16, 2011 Google Scholar
13 See www.ansys.com Google Scholar
14 See Appendix A-1, “Evolution of the Conceptual Description of Atmospheric Dust and the Waste Package Environment,” pp. 87–90 in Technical Advancements and Issues Associated with the Permanent Disposal of High-Activity Wastes Lessons learned from Yucca Mountain and Other Programs, US Nuclear Waste Technical Review Board, June 2011, available at www.nwtrb.gov Google Scholar
15 NWTRB, Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel, US Nuclear Waste Technical Review Board, December 2010, available at www.nwtrb.gov.Google Scholar