Performance of a zeolite column system in removing fission products from molten salt
Conference
·
OSTI ID:370523
- Argonne National Lab., IL (United States)
Spent nuclear fuel is dissolved in molten chloride salt and treated in a molten salt electrorefiner for conversion into metal and mineral waste forms for geologic disposal. Non-TRU fission products in the molten salt are removed by ion-exchange in a continuous process using a zeolite column system. The salt-loaded zeolite is subsequently mixed with glass and consolidated. The zeolite was effective at removing fission products from the molten salt. Cesium was removed relatively rapidly; alkaline earths and rare earths were more strongly held by the zeolite, but the rate of exchange was much slower. Four parameters were varied during these tests: type of zeolite used, temperature, flow rate, and composition of the salt. The effects of these parameters on the effluent composition and on the distribution of fission products along the length of the column are presented and discussed. Results are used to test a computer model of the system.
- OSTI ID:
- 370523
- Report Number(s):
- CONF-960376--
- Country of Publication:
- United States
- Language:
- English
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