TY - GEN
T1 - Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions
AU - Loida, A.
AU - Gens, R.
AU - Metz, V.
AU - Lemmens, Karel
AU - Cachoir, Christelle
AU - Mennecart, Thierry
AU - Kienzler, B.
A2 - Ferrand, Karine
N1 - Score = 3
PY - 2009/12
Y1 - 2009/12
N2 - Contact of highly alkaline solution with spent fuel is considered in the Belgian concept for disposal in the Boom Clay formation. According to the “supercontainer design” the fuel will be encapsulated in carbon steel canisters, surrounded by a concrete overpack. After saturation of the engineered barriers by porewater, interactions with the concrete will result in solutions rich in NaOH, KOH and
Ca(OH)2. Using this type of solution at pH 12.5, spent nuclear fuel corrosion experiments were conducted over 378 days. Under anoxic conditions, parallel experiments were performed (a) in the absence of Fe phases and (b) in the presence of solid Fe phases representing container (corrosion) products. Both types of experiments resulted in relatively low matrix dissolution rates, around 10-7 per day, according to the fractional release of Sr. Solution concentrations of actinides are close to or below the detection limit. The observed precipitation of a Ca rich phase onto the surfaces of the corroded fuel samples may be related to the inhibited release of actinides, Sr and other matrix bound radioelements.
AB - Contact of highly alkaline solution with spent fuel is considered in the Belgian concept for disposal in the Boom Clay formation. According to the “supercontainer design” the fuel will be encapsulated in carbon steel canisters, surrounded by a concrete overpack. After saturation of the engineered barriers by porewater, interactions with the concrete will result in solutions rich in NaOH, KOH and
Ca(OH)2. Using this type of solution at pH 12.5, spent nuclear fuel corrosion experiments were conducted over 378 days. Under anoxic conditions, parallel experiments were performed (a) in the absence of Fe phases and (b) in the presence of solid Fe phases representing container (corrosion) products. Both types of experiments resulted in relatively low matrix dissolution rates, around 10-7 per day, according to the fractional release of Sr. Solution concentrations of actinides are close to or below the detection limit. The observed precipitation of a Ca rich phase onto the surfaces of the corroded fuel samples may be related to the inhibited release of actinides, Sr and other matrix bound radioelements.
KW - spent fuel
KW - corrosion
KW - supercontainer
KW - dissolution rate
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_103907
UR - http://knowledgecentre.sckcen.be/so2/bibref/6758
M3 - In-proceedings paper
SN - 978-1-60511-166-7
T3 - Materials Research Society proceedings
SP - 597
EP - 604
BT - Scientific Basis for Nuclear Waste Management XXXIII. Symposium Proceedings. Volume 1193
CY - Warrendale, PA, United States
T2 - 33rd International Symposium "Scientific Basis for Nuclear Waste Management". MRS
Y2 - 24 May 2009 through 29 May 2009
ER -