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
• NSA Number: NSA-22-004231
• OSTI ID: 4902083
• Report Number(s): IN--1087
• Country of Publication: United States
• Language: English

Related Subjects

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