Hostname: page-component-77c89778f8-vpsfw Total loading time: 0 Render date: 2024-07-25T01:44:10.108Z Has data issue: false hasContentIssue false

Experimental study of the Dissolution of spent fuel at 85°C in Natural Ground Water

Published online by Cambridge University Press:  28 February 2011

Charles N. Wilson
Affiliation:
Westinghouse Hanford Company, Richland, WA 99352
Henry F. Shaw
Affiliation:
Lawrence Livermore National Laboratory, Livermore, CA 94550
Get access

Abstract

Semi-static dissolution tests using pressurized water reactor spent fuel rod segments and NNWSI reference J-13 well water in sealed stainless steel vessels at 85°C are being conducted in support of the Waste Package Task of the NNWSI Project. Test specimens include: bare fuel plus the empty cladding hulls, fuel rod segments with artificially induced cladding defects and water-tight end caps, and undefected fuel rod segments with water-tight end caps. The test conditions approximate those expected in the proposed NNWSI Project repository when the waste package has cooled sufficiently to allow water to enter a breached container and contact the fuel rods, some of which may exhibit various degrees of cladding failure. Periodic solution samples (unfiltered and filtered) were analyzed for most radionuclides for which cumulative release limits are listed by the U.S. Environmental Protection Agency. Results from the first six-month cycle of the 85° C tests are presented and are compared with results from the first cycle of a previous test series run at 25° in fused silica test vessels.

Type
Research Article
Copyright
Copyright © Materials Research Society 1987

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. Wilson, C.N. andOversby, V.M., in Waste Management 85, Ed.Post, R.G., vol 1, pp. 497504 (also UCRL-91464, March 1985).Google Scholar
2. Oversby, V.M. andWilson, C.N., in Scientific Basis for Nuclear Waste Management IX, Ed. Werme, L.O. (Materials Research Society, Pittsburgh, PA, 1986) pp. 337346.Google Scholar
3. Wilson, C.N., Results from Cycles 1 and 2 of NNWSI Spent Fuel Dissolution Tests, HEDL-TME 85-22, Hanford Engineering Development Laboratory, Richland, WA (anticipated publication date of February 1987).Google Scholar
4. Davis, R.B. andPasupathi, V., Data Summary Report for the Destructive Examination of Rods G7, G9, J8, 19 and H6 from Turkey Point Fuel Assembly B17, HEDL-TME 80-85, Hanford Engineering Development Laboratory, Richland, WA (April 1981).Google Scholar
5. Barner, J.O., Characterization of LWR Spent Fuel MCC-Approved Testing Material ATM-1OI, PNL-5109, Pacific Northwest Laboratory, Richland, WA, (1984).Google Scholar