First-cycle studies of coprocessing flowsheets
Conference
·
OSTI ID:6273610
Selected portions of two coprocessing flowsheets developed for use at the Barnwell Nuclear Fuel Plant (BNFP) have been tested in the laboratory with uranium, plutonium, and fission products. Processing conditions and stream compositions for first cycle extraction and uranium-plutonium partitioning in an electropulse column were controlled to examine the behavior of nitric acid, uranium, plutonium, and fission products during coprocessing. The ability to adapt coprocessing technology for use in the BNFP reprocessing facility was successful for first cycle extraction and partition. The only process adjustment involved a reduction in nitric acid concentration to attain proper uranium to plutonium ratios.
- Research Organization:
- Allied-General Nuclear Services, Barnwell, SC (USA)
- DOE Contract Number:
- AC09-78ET35900
- OSTI ID:
- 6273610
- Report Number(s):
- AGNS-35900-CONF-130; CONF-811103-12; ON: DE81028761
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
BARNWELL FUEL PROCESSING PLANT
DIAGRAMS
ELEMENTS
EVALUATION
EXTRACTION
FISSION PRODUCTS
FLOWSHEETS
FUEL REPROCESSING PLANTS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
ISOTOPES
MATERIALS
METALS
NITRIC ACID
NUCLEAR FACILITIES
PLUTONIUM
PROLIFERATION
PUREX PROCESS
RADIOACTIVE MATERIALS
RECOVERY
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
TESTING
TRANSURANIUM ELEMENTS
URANIUM
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
BARNWELL FUEL PROCESSING PLANT
DIAGRAMS
ELEMENTS
EVALUATION
EXTRACTION
FISSION PRODUCTS
FLOWSHEETS
FUEL REPROCESSING PLANTS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
ISOTOPES
MATERIALS
METALS
NITRIC ACID
NUCLEAR FACILITIES
PLUTONIUM
PROLIFERATION
PUREX PROCESS
RADIOACTIVE MATERIALS
RECOVERY
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
TESTING
TRANSURANIUM ELEMENTS
URANIUM