Hostname: page-component-586b7cd67f-r5fsc Total loading time: 0 Render date: 2024-11-23T04:29:38.568Z Has data issue: false hasContentIssue false
  • English
  • Français

Retention of Neptunium in Uranyl Alteration Phases Formed During Spent Fuel Corrosion

Published online by Cambridge University Press:  10 February 2011

E. C. Buck ,
R. J. Finch ,
P. A. Finn  and
J. K. Bates
E. C. Buck
Affiliation:
Argonne National Laboratory, Argonne, IL 60439
R. J. Finch
Affiliation:
Argonne National Laboratory, Argonne, IL 60439
P. A. Finn
Affiliation:
Argonne National Laboratory, Argonne, IL 60439
J. K. Bates
Affiliation:
Argonne National Laboratory, Argonne, IL 60439
Get access

Abstract

Uranyl oxide hydrate phases are known to form during contact of oxide spent nuclear fuel with water under oxidizing conditions; however, less is known about the fate of fission and neutron capture products during this alteration. We describe, for the first time, evidence that neptunium can become incorporated into the uranyl secondary phase, dehydrated schoepite (UO3•0.8H2O). Based on the long-term durability of natural schoepite, the retention of neptunium in this alteration phase may be significant during spent fuel corrosion in an unsaturated geologic repository.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 87
Copyright
Copyright © Materials Research Society 1998

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 Triay, I. R., Robinson, B. A., Mitchell, A. J., Overly, C. M., and Lopez, R. M., Mater. Res. Soc. Symp. Proc. 294, 797 (1993).Google Scholar
2 Clark, D. L., Hobart, D. E., and Neu, M. P., Chem. Rev. 95, 25–48 (1995).Google Scholar
3 Wronkiewicz, D. J., Bates, J. K., Wolf, S. F., and Buck, E. C., J. Nucl. Mater. 238, 78 (1996).Google Scholar
4 Finch, R. J. and Ewing, R. C., J. Nucl. Mater. 190, 133 (1992).Google Scholar
5 Pearcy, E. C., Prikryl, J. D., Murphy, W. M., and Leslie, B. W., Appl. Geochem. 9, 713 (1994).Google Scholar
6 Burns, P. C., Ewing, R. C., and Miller, M. L. J. Nucl. Mater. 245, 1 (1997).Google Scholar
7 Thomas, L. E. and Guenther, R. J., Mater. Res. Soc. Symp. Proc. 127, 293 (1989); R. J. Guenther et al., Characterization of Spent Fuel Approved Testing Material-ATM-103 Pacific Northwest Laboratory Report, PNL-5109-103 (1988).Google Scholar
8 Finn, P. A., Buck, E. C., Hoh, J. C., and Bates, J. K., Global 1995, Inter. Conf. Eval. Emerging Nucl. Fuel Cycle Syst., pp. 241 (1995).Google Scholar
9 Leapmann, R. D., and Newbury, D. E., Anal. Chem. 65, 2409 (1993).Google Scholar
10 Buck, E. C. and Fortner, J. A., Ultramicro. 67, 69 (1997).Google Scholar
11 Finch, R. J., and Ewing, R. C., Mater. Res. Soc. Symp. Proc. 333, 625 (1994).Google Scholar
12 Buck, E. C., Wronkiewicz, D. J., Finn, P. A., and Bates, J. K., J. Nucl. Mater. 249, 70 (1997)Google Scholar
13 Finch, R. J., Suksi, J., Rasilaninen, K., and Ewing, R. C., Mater. Res. Soc. Symp. Proc. 412, 823 (1996).Google Scholar