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Title: Cadmium transport through molten salts in the reprocessing of spent fuel for the integral fast reactor

Journal Article · · Nuclear Technology; (United States)
OSTI ID:6761056
;  [1];  [2]
  1. Georgia Inst. of Tech., Atlanta (United States)
  2. Argonne National Lab., IL (United States)

The reprocessing of spent fuel from the Integral Fast Reactor is to be accomplished with a pyrochemical process employing molten LiCl-KCl salt covering a pool of cadmium. An examination of this system demonstrates that cadmium metal is soluble to a small extent in this salt and that it diffuses through the salt covering and vaporizes at the surface. The cadmium is soluble in the salt because of either chemical or physical solubility, both of which are dependent on the salt's surface tension. Mixing increases the vaporization rate of the cadmium by increasing its transport to the salt surface. The cadmium vapors can therefore be reduced by decreasing the mixing conditions, by choosing a salt with a higher surface tension so that the cadmium is less soluble, or by decreasing the temperature of the system, thereby lowering the vapor pressure of the cadmium.

OSTI ID:
6761056
Journal Information:
Nuclear Technology; (United States), Vol. 102:3; ISSN 0029-5450
Country of Publication:
United States
Language:
English