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UO2 dissolution in high pH conditions of the Belgian Supercontainer

Published online by Cambridge University Press:  27 March 2012

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

To assess the long-term behavior of spent fuel in alkaline conditions representative for the Belgian Supercontainer design, static and dynamic dissolution tests were performed with depleted and Pu-doped UO2 , simulating medium burn-up UOX fuels of different fuel ages. The experiments were performed under argon atmosphere at 25 – 30°C in cement waters in the pH range 11.7 – 13.5 and at different SA/V ratios. This paper presents the observed UO2 matrix dissolution rates based on the (238U or 233U) release, and proposes a selection of reference dissolution rates for performance assessment. We demonstrate that the dissolution rates at high pH are equivalent to the dissolution rates reported in the literature for neutral pH conditions. The α-activity threshold below which radiolytical fuel oxidation becomes negligible, seems to be close to the threshold reported for anoxic media at neutral pH.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-p17
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 categoriy B and C wastes, First full draft report April 2008.Google Scholar
2. Grambow, B. et al. . Report JRC-ITU-SCA-2005/01 (2005).Google Scholar
3. Grambow, B. et al. ., Final Project Report: MICADO final report (2010).Google Scholar
4. Loida, A. et al. ., Mat. Res. Symp. Proc. 1193, 597 (2009).10.1557/PROC-1193-597Google Scholar
5. Loida, A. et al. ., Corrosion behaviour of spent nuclear fuel in high pH solutions- Effect of hydrogen, proceeding of MRS 2011.10.1557/opl.2012.564Google Scholar
6. Salah, S. et al. ., Mat. Res. Symp. Proc. 932, 481 (2006).10.1557/PROC-932-85.1Google Scholar
7. Wang, L., report SCK•CEN-ER-17 of the Belgian Nuclear Research centre (2006).Google Scholar
8. Oversby, V. M., SKB Technical report TR-99-22 (1999).Google Scholar
9. Cachoir, C. et al. ., SCK•CEN-ER-142 of the Belgian Nuclear Research centre, First full draft report ( 2011).Google Scholar
10. Ollila, K.. Deliverable 1.5.11 of NF-PRO, Final activity report for VTT (2007).Google Scholar
11. Lemmens, K. et al. ., Spent fuel dissolution in Belgian Supercontainer conditions: source term and compatibility, proceeding of MRS 2011.10.1557/opl.2012.566Google Scholar