PUREX PROCESS FOR PLUTONIUM AND URANIUM RECOVERY
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-14-022950
- OSTI ID:
- 4165457
- Report Number(s):
- ORNL-479(Del.)
- Country of Publication:
- United States
- Language:
- English
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