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Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen

Published online by Cambridge University Press:  27 March 2012

A. Loida ,
R. Gens ,
C. Bube ,
K. Lemmens ,
C. Cachoir ,
T. Mennecart  and
B. Kienzler
A. Loida
Affiliation:
Karlsruhe Institute of Technology, Institut für Nukleare Entsorgung, P.O. Box 3640, D-76021 Karlsruhe, Germany
R. Gens
Affiliation:
ONDRAF/NIRAS, Avenue des Arts 14, B-1210 Brussels, Belgium
C. Bube
Affiliation:
Karlsruhe Institute of Technology, Institut für Nukleare Entsorgung, P.O. Box 3640, D-76021 Karlsruhe, Germany
K. Lemmens
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
C. Cachoir
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
T. Mennecart
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
B. Kienzler
Affiliation:
Karlsruhe Institute of Technology, Institut für Nukleare Entsorgung, P.O. Box 3640, D-76021 Karlsruhe, Germany
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Abstract

In accordance with the Belgian “supercontainer design”, spent nuclear fuel (SNF) will be encapsulated in carbon steel canisters, surrounded by a concrete overpack for disposal in poorly-indurated clay. After re-saturation of the barriers by porewater, interactions with the concrete will result in solutions rich in NaOH, KOH and Ca(OH)2. Corrosion studies of SNF in ECW-type solution (Evolved Cement Water) and YCWCa-type solution (Young Cement Water with Ca) were performed under externally applied H2 overpressures over 426 days. Directly after H2 application, Tc concentrations decreased from >10-8 M to concentrations below detection limit. Based on the fractional release of selected fission products, low matrix dissolution rates of ~10-8/day were found in both experiments. U concentrations decreased finally to 1.5•10-9 M (YCWCa) and to 2.1•10-10 M (ECW), respectively. Am, Np and Pu concentrations were found throughout the experiments below their detection limits indicating an effective retention process.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-o27
Copyright
Copyright © Materials Research Society 2012

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References

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