Hostname: page-component-76fb5796d-r6qrq Total loading time: 0 Render date: 2024-04-25T12:30:43.267Z Has data issue: false hasContentIssue false
  • English
  • Français

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
Get access

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

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Werme, L., Sellin, P., and Kjellbert, N.: Copper Canisters for Nuclear High Level Waste Disposal. Corrosion Aspects, SKB TR 92–26 (1992).Google Scholar
2. KBS-3, Final Storage of Spent Nuclear Fuel, Report by the Swedish Nuclear Fuel Supply Co. Stockholm, Sweden (1983).Google Scholar
3. Forsyth, R. S. and Werme, L. O., J. Nucl. Mater. 190 2–19 (1992).Google Scholar
4. Forsyth, R. S., Werme, L. O., Bruno, J.. J. Nucl. Mater. 138 1–15 (1986).Google Scholar
5. Werme, L.O. and Spahiu, K., J. Alloys and Compounds, 271–273 194 (1998)Google Scholar
6. Eriksen, T., Eklund, U-B, Werme, L., Bruno, J., J. Nucl. Mater. 227 76 (1995).Google Scholar
7. Gu, B., Liang, L., Dickey, J. and Dai, S.,: J. Environ. Sci. Technol. 32, 3366–3373 (1998).Google Scholar
8. Loida, L., Grambow, B., Geckeis, H., Dressler, P.: Processes Controlling Radionuclide Release from Spent Fuel, Mat. Res. Soc. Symp. Proc 353, 577–585 (1995).Google Scholar
9. Smart, N. R., Blackwood, D. J. and Werme, L., Corrosion, 58 547–559 (2002).Google Scholar
10. Cui, D., and Spahiu, K., Radiochimica Acta 90, p. 623–628, (2002).Google Scholar
11. Gran, G., Acta Chem. Scand. 4 559 (1950).Google Scholar
12. Spahiu, K., Werme, L., Low, J., Eklund, U-B, Mat. Res. Society Symp. Proc, 608 55–60 (1999).Google Scholar
13. Cui, D., Eriksen, T., Eklund, U. B.. Mat. Res. Society Symp. Proc Vol 663, 427–434 (2001).Google Scholar
14. Forsyth, R. S., Eklund, U.B. and Werme, L. O., Mat. Res. Soc. Symp. Proc 333 385–390 (1994).Google Scholar
15. Cui, D., and Spahiu, K., J. Nucl. Sc. And Tech, supplement 3, pp. 500–503 (2001).Google Scholar
16. Albinsson, Y., Nilsson, H., Jacobsson, A-M., Mat. Res. Soc. Symp. Proc. 663 1109 (2001).Google Scholar
17. Cui, D. and Devoy, J., The surface precipitation during UO2 leaching process, presented at Sci. Basis Nucl. Waste Management (2002), to be published in Mat. Res. Soc. Symp. Proc.Google Scholar