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Chemical Durability of High Burnup Lwr-Spent Fuel in Concentrated Salt Solutions

Published online by Cambridge University Press:  25 February 2011

A. Loida ,
B. Grambow ,
P. Dressier ,
K. Friese ,
H. Geckeis  and
Kernforschungszentrum Karlsruhe
A. Loida
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
B. Grambow
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
P. Dressier
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
K. Friese
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
H. Geckeis
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
Kernforschungszentrum Karlsruhe
Affiliation:
GmbH, Institut fur Nukleare Entsorgungstechnik, Postfach 3640, D-76021 Karlsruhe
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Abstract

High-burnup (<50 MWd/kgU) spent fuel samples of various sizes were exposed to NaCl solutions under static, anaerobic and reducing conditions. The accumulated corrosion time was about 200 days. Gas phase and leach solutions were analyzed. By dissolving mm sized fragments in large volumes of solution, saturation effects were avoided and upper limits for intrinsic dissolution rates of about 5-20 mg/(m2d) were measured. Surface area normalized reaction rates were significantly lower when using fine grained fuel powder (estimated sample surface area to solution volume ratio S/V ca. 3000 m-1), indicating saturation effects. The maximum concentrations of Pu and Am in the tests are close to reported solubility limited concentrations in pure 5m NaCl solutions in the absence of radiolysis effects. The presence of iron effectively reduces the solution concentration of all measured radionuclides (except Cs).

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 417
Copyright
Copyright © Materials Research Society 1994

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References

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