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Technical Bases for the Dwpf Testing Program

Published online by Cambridge University Press:  28 February 2011

M. J. Plodinec
M. J. Plodinec*
Affiliation:
Westinghouse Savannah River CompanySavannah River LaboratoryAiken, South Carolina 29802
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Abstract

The Defense Waste Prsocessing Facility (DWPF) at the Savannah River Site (SRS) will be the first production facility in the United States for the immobilization of high-level nuclear waste. Production of DWPF canistered wasteforms will begin prior to repository licensing, so decisions on facility startup will have to be made before the final decisions on repository design are made. The Department of Energy’s Office of Civilian Radioactive Waste Management (RW) has addressed this discrepancy by defining a Waste Acceptance Process. This process provides assurance that the borosilicate-glass wasteform, in a stainless-steel canister, produced by the DWPF will be acceptable for permanent storage in a federal repository. As part of this process, detailed technical specifications have been developed for the DWPF product.

SRS has developed detailed strategies for demonstrating compliance with each of the Waste Acceptance Process specifications. An important part of the compliance is the testing which will be carried out in the DWPF. In this paper, the bases for each of the tests to be performed in the DWPF to establish compliance with the specifications are described, and the tests are detailed. The results of initial tests relating to characterization of sealed canisters are reported.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 212: Symposium P – Scientific Basis for Nuclear Waste Management XIV , 1990 , 159
Copyright
Copyright © Materials Research Society 1991

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References

REFERENCES

1. Boersma, M.D., American Nuclear Society - Fuel Reprocessing and Waste Management, 1, 131–47 (1984)Google Scholar
2. Weisman, A.F., Papouchado, L.M., Knight, J.R., and Mcintosh, D.L., Waste Management 88, 2, Post, Roy G. (ed.), 203–10 (1988)Google Scholar
3. Mcintosh, D.L. and Papouchade, L.M., High-Level Radioactive Waste Management, Proceedings of the International Topical Meetine, Shipler, D.B. (ed.), USDOE, Washington, DC, 794–801 (1990)Google Scholar
4. Gentilucci, J.A., Waste Management 89, 1, Post, Roy G. (ed.), 723–8 (1989)Google Scholar
5. Plodinec, M.J., Jantsen, C.M., and Wicks, G.G., Advances in Ceramics -Nuclear Waste Management, 8, Ross, W.A. and Wicks, G.G. (eds.), 491–95 (1984)Google Scholar
6. Jantsen, C.M. and Plodinec, M.J., J. Non-Cryst. Solids, 67, 207–23 (1984)CrossRefGoogle Scholar
7. Carter, J.T., Brown, K.G., and Bickford, D.F., Proceedings - First International Conference on Advances in the Fusion of Glass, Bickford, D.F., etal. (ed.), American Ceramic Society, Westerville, OH, Chapter 20 (1988)Google Scholar
8. Bibler, N.E. and Jantsen, C.M., Waste Management 89, 1, Post, Roy G. (ed.), 743–9 (1989)Google Scholar
9. Bibler, N.E., and Bates, J.K., Scientific Basis for Nuclear Waste Management, XIII, Oversby, V.M. (ed.), Materials Research Society, Pittsburgh, PA, 327–38 (1990)Google Scholar
10. Eberhard, B.J., and Kelker, J.W., Welding Journal, 62, 662–3 (1982)Google Scholar
11. Kelker, J.W., Development of the DWPF Canister Temporary Shrink-Fit Seal, USDOE Report DP-1720, Savannah River Laboratory, Aiken, SC 29802 (1986)Google Scholar