Skip to main content Accessibility help
×
Home
Hostname: page-component-684899dbb8-bjz6k Total loading time: 0.343 Render date: 2022-05-23T03:41:38.090Z Has data issue: true Feature Flags: { "shouldUseShareProductTool": true, "shouldUseHypothesis": true, "isUnsiloEnabled": true, "useRatesEcommerce": false, "useNewApi": true }

SR 97: Spent Fuel Alteration/Dissolution and the Influence of Near Field Hydrogen

Published online by Cambridge University Press:  21 March 2011

Kastriot Spahiu
Affiliation:
Swedish Nuclear Fuel and Waste Management Co. (SKB), Box 5864, S-102 40, Stockholm, Sweden
Patrik Sellin
Affiliation:
Swedish Nuclear Fuel and Waste Management Co. (SKB), Box 5864, S-102 40, Stockholm, Sweden
Get access

Abstract

A discussion of the evaluation of the source term in the SR 97 safety assessment of a deep repository for spent nuclear fuel is presented. Since the majority of the radionuclides are embedded in the uranium dioxide fuel matrix, they will be released only after the alteration/dissolution of the matrix. Therefore a description of the process of alteration/dissolution of the spent fuel matrix is needed in a safety assessment.

Under normal repository conditions, i.e. reducing environment and neutral to alkaline pH, uranium dioxide has a very low solubility in water. If solubility is assumed to be the limiting factor, the dissolution of the fuel matrix will proceed very slowly due to the low water exchange in the defective canister. On this basis, a solubility-limited model for the release of the radionuclides from the fuel may be formulated.

The reducing conditions can be upset by the radioactivity of the spent fuel, which generates oxidizing products through water radiolysis. This causes the oxidative alteration/dissolution of the UO2(s) matrix. A model for fuel matrix conversion resulting from radiolytic oxidative dissolution is discussed, as well as parameter variations and the associated uncertainties.

In a repository the spent fuel will come in contact with groundwater after the copper canister has breached. Large amounts of hydrogen are then produced through the anoxic corrosion of the cast iron insert. Recent data on spent fuel leaching in presence of repository relevant hydrogen pressures and the implications on the actual and future spent fuel dissolution modeling will also be discussed.

Type
Research Article
Copyright
Copyright © Materials Research Society 2001

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

1.Final Storage of Spent Nuclear Fuel - KBS-3. Swedish Nuclear Fuel Supply Co/Division KBS, Stockholm 1983.Google Scholar
2.Deep repository for spent nuclear fuel. SR 97 - Post-closure safety, SKB TR 99-06, Stockholm 1999.Google Scholar
3. Sellin, P., SR 97: Hydromechanical evolution in a defective canister, this volume.Google Scholar
4. Kleykamp, H., Nuclear Technology, 80, 412 (1988)CrossRefGoogle Scholar
5. Johnson, L., Tait, J., SKB Technical Report 97-18, Stockholm 1997.Google Scholar
6. Bruno, J., Cera, E., Pablo, J. De, Duro, L., Jordana, S., Savage, D., SKB Technical Report 97-33, Stockholm 1997 Google Scholar
7. Wersin, P., Spahiu, K. and Bruno, J., SKB Technical Report 94-02, Stockholm 1994.Google Scholar
8. , Puigdomenech, Banwart, S., Bateman, K., Milodowski, A., West, J., Grifault, L., Gustafsson, E., Hama, K., Yoshida, H., Kotelnikova, S., Pedersen, K., Lartigue, J-E., Michaud, V., Trotignon, L., Morosini, M., Rivas, J., Tullborg, E-L., SKB International Cooperation Report 99-01, Stockholm 1999.Google Scholar
9. Werme, L., Sellin, P., Forsyth, R., SKB Technical Report 90-08, Stockholm 1990.Google Scholar
10. Garrels, R. M and Christ, C. L, Solutions, Minerals, and Equilibria, Harper & Row, New York 1965, 450 p.Google Scholar
11. Ageskog, L., Jansson, P., SKB Technical Report 99-02, Stockholm 1999.Google Scholar
12. Vieno, T., Hautojärvi, A., Koskinen, L., Nordman, H., TVO-92 Safety analysis of spent fuel disposal, YJT 92-33, Technical Research Centre of Finland, 1992.Google Scholar
13. Vieno, T., Nordman, H., TILA-99. Posiva 99-07, Posiva Oy, Helsinki 1999.Google Scholar
14. SKI SITE-94, SKI Report 96-36, Stockholm, 1994.Google Scholar
15. Eriksen, T., SKB Progress Report U-96-29, Stockholm 1996.Google Scholar
16. Ross, B. et al., NDRL-NIST Solution Kinetics Database, 1992.Google Scholar
17. Draganic, Z. D. et al. Radiat. Phys. Chem., 38, 317 (1991).Google Scholar
18. Torrero, M., Ph.D. Thesis, Universidad Politecnica de Catalunya, Barcelona 1995.Google Scholar
19. Gimenez, L, Ph.D. Thesis, Universidad Politecnica de Catalunya, Barcelona 1996.Google Scholar
20. Shoesmith, D., Sunder, S., J. Nucl. Mater. 190, 20, (1992)CrossRefGoogle Scholar
21. Carver, M., Hanley, D., Chaplin, K., AECL Report 6413, Canada, 1979.Google Scholar
22. Spahiu, K., Werme, L., Eklund, U.B., Radiochimica Acta (2000) in print. Google Scholar
23. Bruno, J., Cera, E., Eklund, U-B, Eriksen, T., Grive, M., SKB Technical Report 99-26, 1999.Google Scholar
24. Kelm, M., The formation of oxidants in NaCl Brines, Spent Fuel Workshop, Toronto, Canada 1999 Google Scholar
25. Christensen, H., Nuclear Technology, 165, 124 (1998).Google Scholar
26. Colmenares, A., Prog. Solid State Chem., 15, 257 (1984)CrossRefGoogle Scholar
27. Hedhilil, M. N., Yakshinskiy, B. V., Madey, T. E., Surface Science, 445, 512 (2000).CrossRefGoogle Scholar
28. , Bunji, Zogovic, B., In: Proceedings of the International Symposium on Peaceful Uses of Atomic Energy, pp. 350355, Stockholm 1958.Google Scholar
29. Baker, M. McD., Less, L. N., and Orman, S., Trans. Faraday Soc., 62, 2525 (1966).CrossRefGoogle Scholar
30. Haschke, J. M., Allen, T. H., Stakebake, J. L., J. Alloys and Compounds, 243, 23 (1996).CrossRefGoogle Scholar
31. King, F., Quinn, M. J., Miller, N. H., SKB Technical Report 99-27, Stockholm 1999.Google Scholar

Save article to Kindle

To save this article to your Kindle, first ensure coreplatform@cambridge.org is added to your Approved Personal Document E-mail List under your Personal Document Settings on the Manage Your Content and Devices page of your Amazon account. Then enter the ‘name’ part of your Kindle email address below. Find out more about saving to your Kindle.

Note you can select to save to either the @free.kindle.com or @kindle.com variations. ‘@free.kindle.com’ emails are free but can only be saved to your device when it is connected to wi-fi. ‘@kindle.com’ emails can be delivered even when you are not connected to wi-fi, but note that service fees apply.

Find out more about the Kindle Personal Document Service.

SR 97: Spent Fuel Alteration/Dissolution and the Influence of Near Field Hydrogen
Available formats
×

Save article to Dropbox

To save this article to your Dropbox account, please select one or more formats and confirm that you agree to abide by our usage policies. If this is the first time you used this feature, you will be asked to authorise Cambridge Core to connect with your Dropbox account. Find out more about saving content to Dropbox.

SR 97: Spent Fuel Alteration/Dissolution and the Influence of Near Field Hydrogen
Available formats
×

Save article to Google Drive

To save this article to your Google Drive account, please select one or more formats and confirm that you agree to abide by our usage policies. If this is the first time you used this feature, you will be asked to authorise Cambridge Core to connect with your Google Drive account. Find out more about saving content to Google Drive.

SR 97: Spent Fuel Alteration/Dissolution and the Influence of Near Field Hydrogen
Available formats
×
×

Reply to: Submit a response

Please enter your response.

Your details

Please enter a valid email address.

Conflicting interests

Do you have any conflicting interests? *