REPROCESSING URANIUM-MOLYBDENUM ALLOY FUELS-DISSOLUTION IN CONCENTRATED NITRIC ACID
Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO/sub 3/ solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO/sub 3/. Plutonium and uranium values in washed precipitates can be recovered by successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-14-021572
- OSTI ID:
- 4171897
- Report Number(s):
- HW-64432
- Country of Publication:
- United States
- Language:
- English
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