Hostname: page-component-586b7cd67f-tf8b9 Total loading time: 0 Render date: 2024-11-29T07:38:32.146Z Has data issue: false hasContentIssue false

Spent Fuel Reaction: the Behavior of the ε-Phase Over 3.1 Years

Published online by Cambridge University Press:  03 September 2012

P. A. Finn
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
J. C. Hoh
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
S. F. Wolf
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
M. T. Surchik
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
E. C. Buck
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
J. K. Bates
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
Get access

Abstract

The release fractions of the five elements in the ε-phase (99Tc, 97Mo, Ru, Rh, and Pd) as well as that of 238U are reported for the reaction of two oxide fuels (ATM-103 and ATM-106) in unsaturated tests under oxidizing conditions. The 99Tc release fractions provide a lower limit for the magnitude of the spent fuel reaction. The 99Tc release fractions indicate that a surface reaction might be the rate controlling mechanism for fuel reaction under unsaturated conditions and the oxidant is possibly H2O2, a product of alpha radiolysis of water.

Type
Research Article
Copyright
Copyright © Materials Research Society 1997

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. Guenther, R.J. et al. , Characterization of Spent Fuel Approved Testing Material - ATM-103, Pacific Northwest Laboratory Report PNL-5109–103 (1988).Google Scholar
2. Guenther, R.J. et al. , Characterization of Spent Fuel Approved Testing Material - ATM-106, Pacific Northwest Laboratory Report PNL-5109–106 (1988).Google Scholar
3. Gray, W.J., Strachan, D.M., and Wilson, C.N., in Scientific Basis for Nuclear Waste Management XV. ed. by Sombret, C.G. (Mater. Res. Soc. Proc. 257, Strasbourg, France, 1992), pp. 353360.Google Scholar
4. Thomas, L.E. and Guenther, R.J., in Scientific Basis for Nuclear Waste Management XII, ed. by Lutze, W. and Ewing, R.C., (Mater. Res. Soc. Proc. 127, Berlin, Germany, 1989), pp. 293300.Google Scholar
5. Thomas, L.E., Beyer, C.E., and Chariot, L.A., J. Nucl. Mater. 188, 80 (1992).Google Scholar
6. Finn, P.A. et al. , Radiochimica Acta 66/67, 189 (1994).Google Scholar
7. Finn, P.A. et al. , Spent Fuel's Behavior Under Dynamic Drip Tests, Proc. Inti. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, 240 (1995).Google Scholar
8. Forsyth, R.S. and Werme, L.O., Spent Fuel Corrosion and Dissolution, Swedish Nuclear Fuel and Waste Management Report SKB 91–60 (1991).Google Scholar
9. Wilson, C.N., Results from NNWSI Series 3 Spent Fuel Dissolution Tests, Pacific Northwest Laboratory Report PNL7170 (1990).Google Scholar
10. Wasywich, K.M., et al. , Nucl. Tech. 104, 309 (1993).Google Scholar
11. Kleykamp, H., J. Nucl. Mater. 131, 221 (1985).Google Scholar
12. Allen, A.O., The Radiation Chemistry of Water and Aqueous Solutions, (Von Nostrand, Princeton 1961).Google Scholar
13. Shoesmith, D.W., et al. , in Scientific Basis for Nuclear Waste Management IX, ed. by Werme, L.O. (Mater. Res. Soc. Proc. 50, Stockholm, Sweden, 1985) pp. 309316.Google Scholar
14. Brookins, D.G., Eh-pH Diagrams for Geochemistry. (Springer-Verlag, Berlin, 1988).Google Scholar
15. Davies, J.H. and Ewart, F.T., J. Nucl. Mater. 41, 143 (1971).Google Scholar
16. Johnson, L.H. and Shoesmith, D.W., Spent Fuel, Chap. 11, Radioactive Waste Forms for the Future, ed. by Lutze, W. and Ewing, R.C., (Physics Publishing, North Holland, 1988).Google Scholar
17. Curtis, D.B. and Gancarz, A.J., Radiolysis in Nature: Evidence from the Oklo Natural Reactors, KBS Technical Report 83–10 (1983).Google Scholar
18. Grambow, B., et al. , Chemical Reaction of Fabricated and High Burnup Spent UO2Fuel with Saline Brines, Forschungszentrum Karlsruhe Report FZKA 5702 (1996).Google Scholar
19. Grambow, B., et al. , in Scientific Basis for Nuclear Waste Management XII, ed. by Oversby, V.M. and Brown, P.W., (Mater. Res. Soc. Proc. 176, Boston, MA, 1990), pp. 465474.Google Scholar
20. Eriksen, T. E., et al. , J. Nucl. Mater. 227, 76 (1995).Google Scholar