Chemical Engineering Division fuel cycle programs. Quarterly progress report, July-September 1978

Technical Report · Tue Jan 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/5597395· OSTI ID:5597395

Steindler, M J; Ader, M; Barletta, R E

Fuel cycle work included hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, flowsheet for the Aralex process, Ru and Zr extraction in a miniature centrifugal contactor, study of Zr aging in the organic phase and its effect on Zr extraction and hydraulic testing of the 9-cm-ID contactor. Work for predicting accident consequences in LWR fuel processing covered the relation between energy input (to subdivide a solid) and the modes of particle size frequency distribution. In the pyrochemical and dry processing program corrosion-testing materials for containment vessels and equipment for studying carbide reactions in bismuth is under way. Analytical studies have been made of salt-transport processes; efforts to spin tungsten crucibles 13 cm dia continue, and other information on tungsten fabrication is being assembled; the process steps of the chloride volatility process have been demonstrated and the thoria powder product used to produce oxide pellets; solubility of UO/sub 2/, PuO/sub 2/, and fission products in molten alkali nitrates is being investigated; work was continued on reprocessing actinide oxides by extracting the actinides into ammonium chloroaluminate from bismuth; the preparation of thorium-uranium carbide from the oxide is being studied as a means of improving the oxide reactivity; studies are in progress on producing uranium metal and decontaminated ThO/sub 2/ by the reaction of (Th,U)O/sub 2/ solid solution in molten salts containing ThCl/sub 4/ and thorium metal chips. In the molten tin process, no basic thermodynamic or kinetic factors have been found that may limit process development.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5597395
• Report Number(s): ANL-79-6
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
FBR TYPE REACTORS
FUEL CYCLE
RESEARCH PROGRAMS
RADIOACTIVE WASTE DISPOSAL
RADIONUCLIDE MIGRATION
RADIOACTIVE WASTE PROCESSING
ENCAPSULATION
WATER COOLED REACTORS
EXTRACTION APPARATUSES
METALS
PYROCHEMICAL PROCESSES
REPROCESSING
SOLVENT EXTRACTION
BREEDER REACTORS
ELEMENTS
ENVIRONMENTAL TRANSPORT
EPITHERMAL REACTORS
EXTRACTION
FAST REACTORS
MANAGEMENT
MASS TRANSFER
PROCESSING
REACTORS
SEPARATION PROCESSES
WASTE DISPOSAL
WASTE MANAGEMENT
WASTE PROCESSING
050800* - Nuclear Fuels- Spent Fuels Reprocessing
052000 - Nuclear Fuels- Waste Management