Flowsheet for coprocessing uranium and plutonium
A coprocessing solvent extraction flowsheet for recovering and purifying LWR fuels has been altered to achieve partial partioning of uranium and plutonium to eliminate streams with pure plutonium. Partial partitioning has been demonstrated in the laboratory with simulated feeds and irradiated LWR fuel solutions. Hydroxylamine nitrate was the reductant in these tests. Plutonium was concentrated by factors of 6 to 27.4. Tests have shown that 1 to 2 plutonium atoms are reduced for each hydroxylamine molecule consumed. Nitrite interferes with the reduction of plutonium, unless the hydroxylamine concentration is increased. 12 tables, 11 figures.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 710122
- Report Number(s):
- DP--1505
- Country of Publication:
- United States
- Language:
- English
Similar Records
Coprocessing solvent extraction studies
Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels
Solvent-extraction studies of coprocessing flowsheets: results from campaigns 1 and 2 of the Solvent-Extraction Test Facility (SETF)
Journal Article
·
Sat Mar 31 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5780482
Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5367406
Solvent-extraction studies of coprocessing flowsheets: results from campaigns 1 and 2 of the Solvent-Extraction Test Facility (SETF)
Technical Report
·
Thu Jul 01 00:00:00 EDT 1982
·
OSTI ID:708531