ELECTROLYTIC DISSOLUTION OF POWER REACTOR FUELS IN NITRIC ACID
The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(07-2)-1
- NSA Number:
- NSA-16-017759
- OSTI ID:
- 4833919
- Report Number(s):
- DP-647
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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