Solvent-extraction studies of coprocessing flowsheets: results from campaigns 1 and 2 of the Solvent-Extraction Test Facility (SETF)

Technical Report · Thu Jul 01 04:00:00 EDT 1982

DOI:https://doi.org/10.2172/708531· OSTI ID:708531

Collins, E D; Benker, D E; Bigelow, J E; Chattin, F R; Lloyd, M H; King, L J; Ross, R G; Savage, H C

The Solvent Extraction Test Facility (SETF) was installed in one of the heavily shielded cells of the Transuranium Processing Plant during 1978. This facility contains dissolution, feed preparation, solvent extraction (three 16-stage mixer-settlers), and plutonium product handling equipment, as well as waste solution tanks. Irradiated fuel from the H.B. Robinson-2 Pressurized Water Reactor was processed in the first two campaigns of experimental work, which were completed in 1979. The objective was to test a variety of coprocessing flowsheets. Areas of the solvent extraction process that received special attention included (1) crud formation, particularly in the extraction contactor; (2) uranium and plutonium losses in the extraction raffinate; (3) fission product decontamination; (4) reduction of tetravalent plutonium, particularly by means of hydroxylamine nitrate or nitrous acid; (5) costripping of uranium and plutonium; (6) partial partitioning; and (7) solvent degradation.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 708531
• Report Number(s): ORNL/TM--7080; ON: TI82019669
• Country of Publication: United States
• Language: English

Related Subjects

05
DECONTAMINATION
EXPERIMENTAL DATA
FLOWSHEETS
HYDROXYLAMINE
LOSSES
NITROUS ACID
PLUTONIUM
REDUCTION
REPROCESSING
ROBINSON-2 REACTOR
SOLVENT EXTRACTION
SPENT FUELS
TEST FACILITIES
URANIUM