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Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel

Published online by Cambridge University Press:  10 February 2011

T.A. Hayes
Affiliation:
Mechanical and Aerospace Engineering Department, Univ of California, San Diego, La Jolla, CA 92093-0411USA
R.S. Rosen
Affiliation:
Lawrence Livermore National Laboratory, Livermore, CA 94550USA
M.E. Kassner
Affiliation:
Mechanical and Aerospace Engineering Department, Univ of California, San Diego, La Jolla, CA 92093-0411USA Mechanical Engineering Department, Oregon State University, Corvallis, OR 97331USA
K.S. Vecchio
Affiliation:
Mechanical and Aerospace Engineering Department, Univ of California, San Diego, La Jolla, CA 92093-0411USA
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Abstract

Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models for defining the maximum allowable initial storage temperature for SNF are based on the diffusion controlled cavity growth (DCCG) failure mechanism proposed by Raj and Ashby. These models may not give conservative temperature limits. Some have suggested using a strain-based failure model to predict the maximum allowable temperatures, but we have shown that this is not applicable to SNF as long as DCCG is the assumed failure mechanism. Although the two accepted models are based on the same fundamental failure theory (DCCG), the researchers who developed the models made different assumptions, including selection of some of the most critical variables in the DCCG failure equation. These inconsistencies are discussed together with recommended modifications to the failure models based on more recent data.

Type
Research Article
Copyright
Copyright © Materials Research Society 2000

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References

REFERENCES

1 U.S. Code of Federal Regulations, Part 72, Title 10, “Energy”Google Scholar
2 Schwartz, M. and Witte, M., Lawrence Livermore National Laboratory, UCID-21181, September 1987 Google Scholar
3 Levy, I., Chin, B., Simonen, E., Beyer, C., Gilbert, E., and Johnson, A. Jr, Pacific Northwest Laboratory, PNL-6189, May 1987 Google Scholar
4 Nix, W., Mech. Behavior of Mater.-V, 2, pp. 13831398 (1988)Google Scholar
5 Peehs, M. and Fleisch, J., J. Nuc. Mater., 137, pp. 190202 (1986)Google Scholar
6 Chin, B., “Final Report, Deformation and Fracture Map Methodology for Predicting Cladding Behavior During Dry Storage,” 872BC 1PNLF, September 15, 1987 Google Scholar
7 Raj, R. and Ashby, M., Acta Met., 23, pp. 653666 (1975)Google Scholar
8 Pescatore, C. and Cowgill, M., Brookhaven National Laboratory, EPRI TR-103949, May 1994 Google Scholar
9 Keusseyan, R., Hu, C. and Li, C., J. Nucl. Mater., 80, pp. 390392 (1979)Google Scholar
10 Cane, B. and Greenwood, G., Met. Sci., 9, pp. 5560 (1975)Google Scholar
11 Chun, R., Witte, M., and Schwartz, M., Lawrence Livermore National Laboratory, UCID-21246, October 20, 1987 Google Scholar
12 Hayes, T., Rosen, R. and Kassner, M., Lawrence Livermore National Laboratory, UCRLID-131098, December 1999 Google Scholar
13 Garde, A., Chung, H. and Kassner, T., Acta Met., 26, pp. 153165 (1978)Google Scholar
14 James, D. and Leak, G., Philos. Mag., 12, pp. 491503 (1965)Google Scholar
15 Vieregge, K. and Herzig, Chr., J. Nuc. Mater., 173, pp. 118129 (1990)Google Scholar
16 Griffiths, M., J. Nuc. Mater., 159, pp. 190218, (1988)Google Scholar
17 Griffiths, M., Styles, R., Woo, C., Phillipp, F. and Frank, W., J. Nuc. Mater., 208, pp. 324334 (1994)Google Scholar
18 McKinnon, M. and Doherty, A., Pacific Northwest National Laboratory, PNNL-111576, June 1997 Google Scholar