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Spent fuel dissolution in Belgian Supercontainer conditions: source term and compatibility

Published online by Cambridge University Press:  23 March 2012

K. Lemmens ,
Th. Mennecart  and
C. Cachoir
K. Lemmens
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
Th. Mennecart
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
C. Cachoir
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
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Abstract

In the frame of the Safety and Feasibility Case 1 development, the Belgian agency for radioactive waste (ONDRAF/NIRAS) has to demonstrate that the geological disposal of spent nuclear fuel in the Boom Clay host rock following the Supercontainer design provides sufficient radiological safety in the long term. This safety relies on the containment of the radionuclides by the overpack, the limitation of radionuclide release from the waste matrix, the diffusion controlled transport of the radionuclides, and their low solubility and sorption on the Boom Clay host rock. This paper presents an evaluation of the main processes considered for the limitation of radionuclide release by the Spent Fuel in Supercontainer conditions, characterized by the presence of a concrete buffer and hyperalkaline pore water. We present a description of the main expected processes with their potential impact on the fuel alteration mechanisms, and potential reference fuel matrix alteration rates and effective fuel surface areas for use in safety and performance assessment models.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-o38
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1. Wickham, S., Evolution of the Near-Field of the ONDRAF/NIRAS repository concept for category B and C wastes, First full draft report, April 2008 Google Scholar
2. Wang, L., report SCK•CEN-ER-17 of the Belgian Nuclear Research Centre (2006)Google Scholar
3. Johnson, L. et al. ., NAGRA Technical Report 04-09 (2005)Google Scholar
4. Grambow, B. et al. ., Final Project Report: MICADO, Model Uncertainty for the mechanism of dissolution of spent fuel in nuclear waste repository, Sixth Framework Programme of the European Commission (2010)Google Scholar
5. Mennecart, Th., Cachoir, C., Lemmens, K., Spent fuel dissolution in Belgian Supercontainer conditions: Source term and compatibility, proceedings of MRS2011 Google Scholar
6. Clacher, A., Berry, J., SERCO/TCS/003623/001/03 report (October 2010)Google Scholar
7. Kursten, B., Uniform corrosion rate data of carbon steel in cementitious environments relevant to the Supercontainer design, second full draft report, SCK•CEN-ER-94 (2011).Google Scholar
8. Johnson, L., Poinssot, C., Ferry, C., Lovera, P., NAGRA Technical report 04-08 (2004)Google Scholar
9. Loida, A., Gens, R., Metz, V., Lemmens, K., Cachoir, C., Mennecart, Th., Kienzler, B., Corrosion behavior of spent nuclear fuel in high pH conditions – Effect of hydrogen, proceedings of MRS2011 Google Scholar
10. Yu, L. and Weetjens, E., report SCK•CEN-ER-162 of the Belgian Nuclear Research Centre (2011)Google Scholar
11. Cachoir, C., Mennecart, Th., First full draft or report SCK•CEN-ER-142 of the Belgian Nuclear Research Centre (2011)Google Scholar