Chemical Technology Branch annual report, fiscal year 1967

Technical Report · Sun Oct 01 00:00:00 EDT 1967

DOI:https://doi.org/10.2172/4902083· OSTI ID:4902083

Bower, J. R. ^[1]

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1. ed.

• Research Organization: Idaho Nuclear Corp., Idaho Falls, ID (United States)
• Sponsoring Organization: USAEC
• DOE Contract Number: AT(10-1)-1230
• NSA Number: NSA-22-004231
• OSTI ID: 4902083
• Report Number(s): IN-1087
• Resource Relation: Other Information: UNCL
• Country of Publication: United States
• Language: English

Related Subjects

N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
FUEL ELEMENTS
REACTORS
REPROCESSING
SEPARATION PROCESSES
WASTE PROCESSING AMMONIUM FLUORIDES
EBR-2
HYDROFLUORIC ACID
SODIUM
SOLUBILITY
SOLVENT EXTRACTION
STAINLESS STEELS
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCALOY
ZIRCONIUM OXIDES
CALCIUM NITRATES
COMBUSTION
GRAIN SIZE
HEAT EXCHANGERS
MATHEMATICS
SOLIDIFICATION
WASTE SOLUTIONS
ZIRCONIUM
ALUMINUM
ALUMINUM ALLOYS
CHEMICAL REACTIONS
INTERMETALLIC COMPOUNDS
PRODUCTION
URANYL NITRATES
LABORATORY EQUIPMENT
FLUIDIZATION
FLUIDIZED BED
GRAPHITE
NITRIC ACID
URANIUM
CATALYSIS
COPPER ALLOYS
CORROSION
CRITICALITY
MERCURY
SILICIDES
SILICON
ZIRCONIUM ALLOYS
COATING
CONCRETES
CONTAMINATION
CRACKS
DECONTAMINATION
DIFFUSION
FILTERS
FISSION PRODUCTS- - GLASS
IODINE
LOFT
MELTING
RESEARCH REACTORS
SAMPLING
TEXTILES
COMPUTERS
FINS
HEAT TRANSFER
PROGRAMMING
RADIOISOTOPES
STORAGE
SURFACES
TUBES
VOLATILITY
EXPERIMENTAL BREEDER REACTOR-II/fuel reprocessing for
REACTOR FUEL ELEMENTS/reprocessing of zirconium-containing
corrosion in
REACTOR FUEL ELEMENTS/reprocessing of
criticality of dissolvers for
REACTOR FUEL ELEMENTS/dissolution of
RADIOACTIVE WASTE/processing of
research progress on
COPPER/effects on dissolution of aluminum-silicon-uranium systems
ALUMINUM ALLOYS AND SYSTEMS/Al-Si-U
dissolution of
effects of copper on
ALUMINUM ALLOYS AND SYSTEMS/Al-U
production of intermetallic UAl$sub 3$ from uranyl nitrate and aluminum
ALUMINUM/reactions with uranyl nitrate
URANYL NITRATES/ reactions with aluminum
REACTOR FUEL ELEMENTS/reprocessing of
pilot plants for
DISSOLVERS/criticality of fuel-element
REACTOR FUEL ELEMENTS/combustion- dissolution process for graphite
URANIUM/separation from graphite fuels by combustion-dissolution process
EXPERIMENTAL BREEDER REACTOR-II/fuel reprocessing for
electrolytic dissolver for
DISSOLVERS/design of electrolytic
for fuel reprocessing
ZIRCONIUM OXIDES/UO$sub 2$-ZrO$sub 2$
dissolution of Zircaloy-4- clad
URANIUM OXIDES UO$sub 2$/UO$sub 2$-ZrO$sub 2$
dissolution of Zircaloy-4- clad
RADIOACTIVE WASTE/calcination of aqueous
HEAT EXCHANGERS/performance in waste calcining facility
RADIOACTIVE WASTE/calcination of zirconium-containing
HEAT TRANSFER/rates in fluidized-bed waste calcination facility
RADIOACTIVE WASTE/calcination of
heat transfer in fluidized beds for
RADIOACTIVE WASTE/ storage of
heat transfer in
RADIOACTIVE WASTE/management at ICPP
REACTOR SAFETY EXPERIMENTS/containment shell coatings for LOFT
IODINE/diffusion in containment shell coatings in LOFT
FISSION PRODUCTS/diffusion in containment shell coatings in LOFT
URANIUM ALLOYS AND SYSTEMS/Al-U
production of intermetallic UAl$sub 3$ from uranyl nitrate and aluminum
SILICON SYSTEMS/Al-Si- -U
dissolution of
effects of copper on
URANIUM ALLOYS AND SYSTEMS/Al-Si-U
dissolution of
effects of copper on
REACTOR FUEL ELEMENTS/reprocessing of
research progress on
FISSION PRODUCTS/diffusion from melted irradiated fuels
REACTOR FUEL ELEMENTS/fission product diffusion from melted irradiated
REACTOR SAFETY EXPERIMENTS/containment atmosphere in LOFT
continuous sampler-monitor for sampling
REACTOR FUEL ELEMENTS/meltdown of Zircaloy-clad