PROCESSING OF POWER REACTOR FUELS. Twenty-Second Quarterly Progress Report, January 1 to April 1, 1963
During the electrolytic dissolution of simulated Hallam reactor fuel in nitric acid at 80 deg C, sodium was dissolved safely at 1.2 grams per minute, which is ten times the rate previously demonstrated. Extrapolating this rate to a 10,000-amp plant dissolver having two baskets in series indicates that a processing rate of 0.5 metric ton of uranium per day is feasible for Hallam fuel and for the blanket assemblies from the Fermi reactor. The development program on electrolytic dissolution at the Savannah River Laboratory is being concluded, and a summary report will be published. Laboratory tests showed that dissolution of zirconium-containing fuel in a 304L stainless steel vessel may be feasible with a mixed dissolvent of hydrofluoric acid, aluminum nitrate, and nitric acid. (auth)
- Research Organization:
- Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.
- DOE Contract Number:
- AT(07-2)-1
- NSA Number:
- NSA-17-032192
- OSTI ID:
- 4692636
- Report Number(s):
- DP-839
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
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