Hostname: page-component-77c89778f8-7drxs Total loading time: 0 Render date: 2024-07-24T09:57:49.378Z Has data issue: false hasContentIssue false
  • English
  • Français

Initial Results From Dissolution Testing of Spent Fuel Under Acidic Conditions

Published online by Cambridge University Press:  17 March 2011

Brady D. Hanson ,
Judah I. Friese  and
Chuck Z. Soderquist
Brady D. Hanson
Affiliation:
Pacific Northwest National Laboratory, Richland, WA 99352, U.S.A., brady.hanson@pnl.gov
Judah I. Friese
Affiliation:
Pacific Northwest National Laboratory, Richland, WA 99352, U.S.A., brady.hanson@pnl.gov
Chuck Z. Soderquist
Affiliation:
Pacific Northwest National Laboratory, Richland, WA 99352, U.S.A., brady.hanson@pnl.gov
Get access

Abstract

Flowthrough dissolution tests using solutions with pH in the range 2 to 7 have been conducted on a moderate burnup Light Water Reactor spent fuel. Such low pH conditions have been modeled as possibly occurring in a failed waste package at the proposed repository at Yucca Mountain. The release oftotal uranium, 99Tc, 90Sr, 137Cs, and 239&240Pu were measured for up to 90% total reaction of the specimens. The reaction rates, determined both from the cumulative release and the release normalized to surface area, were found to decrease with increasing pH and with increasing extent of reaction. The implications to instantaneous release and long-term behavior ina geologic repository are discussed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC8.6
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

1. Gray, W. J. and Wilson, C. N., Spent Fuel Dissolution Studies FY 1991 to 1994, PNL-10540, Pacific Northwest National Laboratory, December 1995.Google Scholar
2. Röllin, S., Spahiu, K., and Eklund, U.-B., J. Nuc. Mat. 297, 231–243 (2001).Google Scholar
3. Gray, W. J., Spent Fuel Dissolution Rates as a Function of Burnup and Water Chemistry, PNNL-11895, Pacific Northwest National Laboratory, June 1998.Google Scholar
4. Guenther, R. J., Blahnik, D. E., and Wildung, N. J., Radiochemical Analyses of Several Spent Fuel Approved Testing Materials, PNL-10113, Pacific Northwest National Laboratory, September 1994.Google Scholar
5. Brunauer, S., Emmet, P., and Teller, E., J. Am. Chem. Soc. 60, 309 (1938).Google Scholar
6. Guenther, R. J., Blahnik, D. E., Campbell, T. K., Jenquin, U. P., Mendel, J. E., and Thornhill, C. K., Characterization of Spent Fuel Approved Testing Material- ATM-106, PNL-5109-106, Pacific Northwest National Laboratory, 1988.Google Scholar
7. Hanson, B. D., Buck, E. C., Friese, J. I., and Jenson, E. D., presented at the 2004 MRS Spring Meeting, San Francisco, CA, 2004.Google Scholar
8. Grandstaff, D. E., Economic Geology, 71, 1493–1506 (1976).Google Scholar
9. Sunder, S. and Miller, N. H., J. Nuc. Mater. 279, 118–126 (2000).Google Scholar
10. Soderquist, C. Z. (private communication)Google Scholar