TY - GEN
T1 - UO2 dissolution in high pH conditions of the Belgian Supercontainer
AU - Mennecart, Thierry
AU - Cachoir, Christelle
AU - Lemmens, Karel
N1 - © 2012 Materials Research Society.
PY - 2012
Y1 - 2012
N2 - 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 a-activity threshold below which radiolytical fuel oxidation becomes negligible, seems to be close to the threshold reported for anoxic media at neutral pH.
AB - 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 a-activity threshold below which radiolytical fuel oxidation becomes negligible, seems to be close to the threshold reported for anoxic media at neutral pH.
KW - Radioactive waste
KW - Waste Management
UR - http://www.scopus.com/inward/record.url?scp=84875522073&partnerID=8YFLogxK
U2 - 10.1557/opl.2012.589
DO - 10.1557/opl.2012.589
M3 - In-proceedings paper
AN - SCOPUS:84875522073
SN - 9781605114521
VL - 1475
T3 - Materials Research Society Symposium Proceedings
SP - 293
EP - 298
BT - Scientific Basis for Nuclear Waste Management XXXV
T2 - 2012 MRS Spring Meeting
Y2 - 9 April 2012 through 13 April 2012
ER -