LWR spent fuel characteristics relevant to performance as a wasteform in a potential tuff repository
Conference
·
OSTI ID:59764
A testing program has been initiated to determine the probable condition of spent fuel during the post-containment period under NNWSI site specific conditions, and to determine relevant radionuclide release rates for spent fuel. The current testing program is focused on three subject areas: (1) spent fuel leaching/dissolution behavior, (2) spent fuel oxidation, and (3) cladding corrosion. Results are presented. 3 refs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 59764
- Report Number(s):
- UCRL-92891; CONF-851115-10; ON: DE85016285
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA (United States), 10-15 Nov 1985; Other Information: PBD: Jun 1985
- Country of Publication:
- United States
- Language:
- English
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