Radionuclide release behavior of light water reactor spent fuel under hydrothermal conditions
The Basalt Waste Isolation Project has performed initial characterization of the release behavior of radionuclides from ATM-101 spent fuel reacted under hydrothermal conditions. Results to date indicate that (1) /sup 14/C, /sup 90/Sr, /sup 129/I, and /sup 137/Cs exhibit preferential release to solution relative to the actinides, (2) /sup 239+240/Pu, /sup 241/Am, and /sup 244/Cm ratios in solution are consistent with stoichiometric dissolution of the spent fuel matrix, whereas uranium concentrations are higher than those predicted for stoichiometric dissolution, (3) /sup 137/Cs release varies as a function of the fluid to solid mass ratio, and (4) /sup 14/C, /sup 129/I, and /sup 137/Cs release is affected by fuel particle size and/or fuel washing.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 7243915
- Report Number(s):
- WHC-SA-0183; CONF-871124-102; ON: DE88011949; TRN: 88-023098
- Resource Relation:
- Conference: Fall meeting of the Materials Research Society, Boston, MA, USA, 30 Nov 1987; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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HYDROTHERMAL ALTERATION
STRONTIUM 90
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052002* - Nuclear Fuels- Waste Disposal & Storage