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The Impact of Alpha-Radiolysis on the Release of Radionuclides from Spent Fuel in a Geologic Repository

Published online by Cambridge University Press:  25 February 2011

Ivars Neretnieks
Ivars Neretnieks*
Affiliation:
Department of Chemical EngineeringRoyal Institute of TechnologyS-100 44 Stockholm, Sweden
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Abstract

Spent nuclear fuel buried in deep geologic repositories may eventually be wetted by water. The alfa-radiation will radiolyse the water and produce hydrogen and oxidizing agents, mainly hydrogen peroxide and oxygen. The hydrogen will escape by diffusion and the oxidizing agents may attack the canister materials, oxidize the uranium oxide matrix or diffuse out and oxidize reducing agents in the surrounding rock.

The rate of radiolysis has been computed recently within the Swedish nuclear fuel safety projects KBS. It is strongly influenced by the amount of available water and by the presence of dissolved iron. The movement of the oxidizing agents out from the canister and their reaction with the reducing agents (mainly ferrous iron) in the Swedish crystalline rock has been modelled as well as the movement of the radionuclides within and past the redox front. Some substances such as uranium, neptunium and technetium will precipitate at the redox front and will be withdrawn from the water to a considerable extent.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 1009
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

1. Allard, B, Kipatsi, H, and Torstenfelt, B: Adsorption of Long-Lived Radionuclides in Clay and Rock, Part 2. KBS Technical Report No. 98, Stockholm (1978).Google Scholar
2. Allard, B: Solubilities of Actinides in Neutral or Basic Solutions. Proc. Actinides 81, Asilomar, September 10-15, 1982, Pergamon Press, Oxford (1982).Google Scholar
3. Bengtsson, A, Magnusson, M, Neretnieks, I, Rasmuson, A: Model Calculations of the Migration of Radionuclides from a Repository for Spent Nuclear Fuel. KEMAKTA Consultant Company, Royal Institute of Technology, KBS TR 83 48, May 1983.Google Scholar
4. Bird, R B, Stewart, W E, Lightfoot, E N: Transport phenomena. John Wiley & Sons, N Y, 1960.Google Scholar
5. Christensen, H, Bjergbakke, E: Radiolysis of Ground Water from Spent Fuel. Studsvik Energiteknik AB, KBS TR 82-18, November 1982.Google Scholar
6. Fried, J J, Combarnous, M A: Dispersion in Porous Media. Advances Hydroscience 7 (1971) 170.Google Scholar
7. Curtis, D, Gancarz, A: Radiolysis in Nature: Evidence from the Oklo Natural Reactors. KBS TR 83-10, February 1983.Google Scholar
8. Final storage of spent nuclear fuel. KBS 3, Swedish Nuclear Fuel Supply Co/Division KBS, Stockholm, Sweden, May 1983.Google Scholar
9. Grenthe, I, Puigdomenech, I, Bruno, J: The possible Effects of Alfa and Beta Radiolysis on the Matrix Dissolution of Spent Nuclear Fuel. Royal Institute of Technology, KBS TR 83-02, January 1983.Google Scholar
10. Lapidus, L and Pinder, G S: Numerical solution of partial differential equations in science and engineering. Wiley 1982.Google Scholar
11. Neretnieks, I: Adsorption of components having a saturation isotherm. Chemie Ingenieur-Technik 46, 1974, p. 781.Google Scholar
12. Neretnieks, I: Transport mechanisms and rates of transport of radionuclides in the geosphere as related to the Swedish KBS concept. Proceedings of Symposium. Underground disposal of radioactive wastes IAEA/NEA, Vienna 1980, Vol 2, p. 315.Google Scholar
13. Neretnieks, I: Diffusion in the Rock Matrix: An Important Factor in Radionuclide Retardation? J Geophys Res 85 (1980), 4379.10.1029/JB085iB08p04379Google Scholar
14. Neretnieks, I: Leach Rates of High Level Waste and Spent Fuel – Limiting Rates as Determined by Backfill and Bedrock Conditions. Paper presented at the 5th International Symposium on the Scientific Basis for Nuclear Waste Management. Berlin 1982 June, Proceedings, North-Holland 1982, p. 559–568.Google Scholar
15. Neretnieks, I: The Movement of a Redox Front Downstream from a Repository for Nuclear Waste. Nucl. Techn. 62, July 1983, p. 110.10.13182/NT83-A33238Google Scholar
16. Neretnieks, I, Aslund, B: Two dimensional movement of a redox front downstream from a repository for nuclear waste. Royal Institute of Technology, May 1983, KBS TR 83-68.Google Scholar
17. Neretnieks, I, Aslund, B: The Movement of Radionuclides Past a Redox Front. Royal Institute of Tehcnology, KBS TR 83-66, May 1983.Google Scholar
18. Perry, R H and Chilton, C H: Chemical Engineers' Handbook; 5th ed. 1973, McGraw Hill book company, N Y.Google Scholar
19. Skagius, K, Neretnieks, I: Diffusion in Crystalline Rocks. Paper Presented at the 5th International Symposium on the Scientific Basis for Nuclear Waste Management. Berlin, June 1982. Proceedings, North-Holland 1982, p. 509–518.Google Scholar
20. Torstenfelt, B, Allard, B, Johansson, W, Ittner, T: Iron Content and Reducing Capacity of Granite and Bentonite. Chalmers University of Technology, KBS TR 83-36, April 1983.Google Scholar