Fission Product Removal From Molten Salt Using Zeolite

The Minerals, Metals and Materials Society
C. Pereira
Organization:
The Minerals, Metals and Materials Society
Pages:
13
File Size:
584 KB
Publication Date:
Jan 1, 1996

Abstract

Spent nuclear fuel (SNF) can be treated in a molten salt electro refiner for conversion into metal and mineral waste fonns for geologic disposal. The fuel is dissolved in molten chloride salt. Non-transuranic fission products in the molten salt are ion-exchanged into zeolite A, which is subsequently mixed with glass and consolidated. Zeolite was found to be effective in removing fission product cations from the molten salt. Breakthrough of cesium and the alkaline earths occurred more rapidly than was observed for the rare earths. The effluent composition as a function of time is presented, as well as results for the distribution of fission products along the length of the column. Effects of temperature and salt flow rate are also discussed.
Citation

APA: C. Pereira  (1996)  Fission Product Removal From Molten Salt Using Zeolite

MLA: C. Pereira Fission Product Removal From Molten Salt Using Zeolite. The Minerals, Metals and Materials Society, 1996.

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