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Spent Fuel Leaching under Anoxic Conditions and the Effect of Canister Materials

Published online by Cambridge University Press:  01 February 2011

Daqing Cui ,
Jeanett Low ,
Max Lundström  and
Kastriot Spahiu
Daqing Cui
Affiliation:
Studsvik Nuclear AB, SE-61182, Nyköping, Sweden
Jeanett Low
Affiliation:
Studsvik Nuclear AB, SE-61182, Nyköping, Sweden
Max Lundström
Affiliation:
Studsvik Nuclear AB, SE-61182, Nyköping, Sweden
Kastriot Spahiu
Affiliation:
SKB, SE-10240, Stockholm, Sweden
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Abstract

The results of a spent fuel leaching experiment in which a fuel pin (17.7 g) was contacted with 380 mL of a 10 mM NaCl, 2 mM NaHCO3 solution by taking special care to minimize atmospheric oxygen contamination are presented. During the first 287 days, the fractions of inventory in the aqueous phase per day (f/d) increased nearly constantly for all nuclides (except for 100Mo), but were higher for fission products f/d(137Cs)=1.210−6, f/d(99Tc)=1.1·10−6 and f/d(90Sr)= 6.7 · 10−7 than for actinides: f/d (238U) =1.0 · 10−7, f/d(237Np)= 2.6 · 10−7 and f/d(239Pu) = 5.1 ·10−9. After adding iron, cast iron and copper foils (of ∼30 mm2 size), the concentrations of 238U, 237Np and 99Tc decreased by 80%, 97% and 88% to relatively stable levels (500ppb, 0.2 ppb and 0.6 ppb respectively). 239Pu concentrations increased from a level around 0.05 ppb to PuO2 solubility level, 0.5 ppb, and stabilized. The leaching process for 137Cs, 100Mo and 90Sr seems not to be influenced by the addition of metal foils. The observations in the present work contribute to an improved understanding of the behavior of spent fuel under near field repository conditions.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 807: Symposium Scientific Basis for Nuclear Waste Management XXVII , 2003 , 89
Copyright
Copyright © Materials Research Society 2004

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References

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