Process for treating salt waste generated in dry reprocessing of

Details Process for treating salt waste generated in dry reprocessing of Process for treating salt waste generated in dry reprocessing of

1992-09-16

1993-11-23

Walsh, Donald P.

Compositions

Radioactive compositions

252626, 252631, 252633, 588252, G21F 904

Patent

active

052641597

ABSTRACT:
A salt waste composed mainly of chlorides, which is generated from the step of a molten salt electrolytic purification in dry reprocessing of a spent metallic nuclear fuel, is reacted with boric acid at high temperature to convert the chlorides in the salt waste into oxides. The resulting oxides of the salt waste are easily vitrifiable, and a vitrification product is obtained by adding a vitrifying additive to the oxides, heat-melting the mixture to form a molten mixture and cooling the molten mixture.

REFERENCES:
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patent: 4504317 (1985-03-01), Smeltzer et al.
patent: 4800042 (1989-01-01), Kurumada et al.
patent: 4814046 (1989-03-01), Johnson et al.
patent: 5041193 (1991-08-01), Grantham
patent: 5096545 (1992-03-01), Ackerman
patent: 5143653 (1992-09-01), Magnin et al.

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