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An Advanced Cold Process Canister Design for Nuclear Waste Disposal

Published online by Cambridge University Press:  28 February 2011

Heikki Raiko  and
Jukka-Pekka Salo
Heikki Raiko
Affiliation:
Technical Research Centre of Finland, Nuclear Engineering Laboratory, Lonnrotinkatu 37, SF-00180 Helsinki, Finland
Jukka-Pekka Salo
Affiliation:
Teollisuuden Voima Oy (TVO), Nuclear Waste Office, Fredrikinkatu 51–53 B, SF-00100 Helsinki, Finland
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Abstract

An advanced cold process canister design, ACPC-design, is introduced in this paper. The cold process canister consists of a steel canister as a load bearing element, with an outer corrosion shield of copper, Fig. 1 - Fig. 4. The canister will be rilled with granular material, such as lead shots, glass beads or quartz sand.

The conditions for the canister design are presented: dimensioning against radiation, allowed heat loads, strains, corrosion and leak tightness etc. The mechanical dimensioning of the copper/steel canister is made according to the Finnish standards (SFS) for pressure vessels.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 212: Symposium P – Scientific Basis for Nuclear Waste Management XIV , 1990 , 351
Copyright
Copyright © Materials Research Society 1991

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References

REFERENCES

1. Salo, J.-P., and Raiko, H., The copper/steel canister design for nuclear waste disposal, TVO/KPA Safety and Technology, work report 90–10 Rev. 1., May 1990, p. 26.Google Scholar
2. Mayer, E., Välimäki, P., and Kukkola, T., TVO-encapsulation plant, preliminary design of cold-process plant, Teollisuuden Voima OY, TVO/KPA Safety and Technology, work report 89–1, January 1989, p. 151.Google Scholar
3. Mayer, E., Spent fuel encapsulation plant, preliminary design, Imatran Voima Oy, TVO/Spent fuel disposal, work report 85–10, (in Finnish), p. 82.Google Scholar
4. Ipatti, A., Lead material tests for cold process encapsulation, Part I, TVO/KPA Safety and Technology, work report 87–25, (in Finnish), September 1987, p. 17.Google Scholar
5. Ipatti, A., Lead material tests for cold process encapsulation, Part II, TVO/KPA Safety and Technology, work report 87–26, (in Finnish), October 1987, p. 4.Google Scholar
6. Hautojärvi, A., Anttila, M., and Taivassalo, V., Effects of fuel burn-up cooling periods on thermal responses in a repository for spent nuclear fuel, Nuclear Waste Commission of Finland, Report YJT-87–21, December 1987, p. 32.Google Scholar
7. Copper and copper alloy data. Permanent file No 1 issued by CDA. Data sheet No. A 4, Cu-OF. 1968 Edition. Copper Development Association, London, UK, p. 10.Google Scholar
8. Ipatti, A., Quartz sand for cold process encapsulation, TVO/KPA Safety and Technology, work report 89–15, (in Finnish), November 1989, p. 18.Google Scholar
9. Sanderson, A., Szluha, T.F., and MacDonald, LA., Assessment of nuclear waste disposal canister design, The Welding Institute, SKB work report 90–13, May 1990, p. 5.Google Scholar
10. Anttila, M., Criticalitv safety of the cold process final disposal canisters, Technical Research Centre of Finland, Nuclear Engineering Laboratory, TVO/Spent fuel safety and technologies, work report 88–02, February 1988, p. 10.Google Scholar