CHEMICAL ENGINEERING DIVISION FUEL CYCLE TECHNOLOGY QUARTERLY REPORT, JANUARY--MARCH 1971.
- Research Organization:
- Argonne National Lab., Ill.
- DOE Contract Number:
- W-31-109-ENG-38
- NSA Number:
- NSA-25-057507
- OSTI ID:
- 4748093
- Report Number(s):
- ANL-7799
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-71
- Country of Publication:
- United States
- Language:
- English
Similar Records
CHEMICAL ENGINEERING DIVISION, FUEL CYCLE TECHNOLOGY QUARTERLY REPORT, JANUARY--MARCH 1972
Chemical Engineering Division fuel cycle applied technology. Quarterly progress report, January-March 1979
Chemical Engineering Division fuel cycle applied technology. Quarterly progress report, January-March 1981
Technical Report
·
Sun Dec 31 00:00:00 EST 1972
·
OSTI ID:4748093
+4 more
Chemical Engineering Division fuel cycle applied technology. Quarterly progress report, January-March 1979
Technical Report
·
Mon Sep 01 00:00:00 EDT 1980
·
OSTI ID:4748093
+4 more
Chemical Engineering Division fuel cycle applied technology. Quarterly progress report, January-March 1981
Technical Report
·
Mon Feb 01 00:00:00 EST 1982
·
OSTI ID:4748093
+1 more
Related Subjects
N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
FABRICATION
FLUIDIZED BED
FUELS
HEAD END PROCESSES
LIQUID METALS
LMFBR
OXIDATION
OXIDES
PLUTONIUM
PLUTONIUM NITRATES
PLUTONIUM OXIDES
PREPARATION
PUREX PROCESS
QUANTITATIVE ANALYSIS
REDUCTION
REPROCESSING
SEPARATION PROCESSES
URANIUM
URANIUM DIOXIDE
URANYL NITRATES
PLUTONIUM/oxidation and reduction in Purex Process
PLUTONIUM/determination relative to uranium in oxide fuels during fabrication
URANIUM/determination relative to plutonium in oxide fuels during fabrication
URANIUM OXIDES UO$sub 2$/preparation from uranyl nitrate
fluid-bed process for
REACTOR FUELS/reprocessing of oxide
liquid-metal head-end process for
PLUTONIUM OXIDES PuO$sub 2$/preparation from plutonium nitrate
fluid-bed process for
LIQUID METAL FAST BREEDER REACTOR/fuel cycle development for
PLUTONIUM/ separation from spent LMFBR fuels by solvent extraction
performance of centrifugal contactor in
FABRICATION
FLUIDIZED BED
FUELS
HEAD END PROCESSES
LIQUID METALS
LMFBR
OXIDATION
OXIDES
PLUTONIUM
PLUTONIUM NITRATES
PLUTONIUM OXIDES
PREPARATION
PUREX PROCESS
QUANTITATIVE ANALYSIS
REDUCTION
REPROCESSING
SEPARATION PROCESSES
URANIUM
URANIUM DIOXIDE
URANYL NITRATES
PLUTONIUM/oxidation and reduction in Purex Process
PLUTONIUM/determination relative to uranium in oxide fuels during fabrication
URANIUM/determination relative to plutonium in oxide fuels during fabrication
URANIUM OXIDES UO$sub 2$/preparation from uranyl nitrate
fluid-bed process for
REACTOR FUELS/reprocessing of oxide
liquid-metal head-end process for
PLUTONIUM OXIDES PuO$sub 2$/preparation from plutonium nitrate
fluid-bed process for
LIQUID METAL FAST BREEDER REACTOR/fuel cycle development for
PLUTONIUM/ separation from spent LMFBR fuels by solvent extraction
performance of centrifugal contactor in