Chemical Technology Branch, Annual Report, Fiscal Year 1968

Technical Report · Tue Oct 01 00:00:00 EDT 1968

DOI:https://doi.org/10.2172/4905515· OSTI ID:4905515

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-23-013824
• OSTI ID: 4905515
• Report Number(s): IN-1201
• Resource Relation: Other Information: UNCL
• Country of Publication: United States
• Language: English

Related Subjects

N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
ALUMINUM ALLOYS
FUEL ELEMENTS
NEPTUNIUM
REPROCESSING
SEPARATION PROCESSES
URANIUM
URANIUM ALLOYS
ZIRCONIUM ALLOYS
EBR-2
ELECTROLYTIC CELLS
RESEARCH REACTORS
SOLUBILITY
SOLVENT EXTRACTION
COMBUSTION
FUELS
GRAPHITE
CORROSION
DECONTAMINATION
FLUORIDES
SOLUTIONS
STAINLESS STEELS
FUEL CANS
URANIUM DIOXIDE
VOLATILITY
ZIRCONIUM
ZIRCONIUM OXIDES
FLUIDIZATION
FLUIDIZED BED
PRODUCTION
MELTING
SALTS
URANYL NITRATES
VOLUME
WATER
ANALOG SYSTEMS
ATR
COMPUTERS
PROGRAMMING
CALCINATION
PYROLYSIS
STORAGE
WASTE PROCESSING
EXTRACTION COLUMNS
PULSES
ELECTROCHEMISTRY
MERCURY
WASTE SOLUTIONS
ACCIDENTS
CONTAMINATION
EFFICIENCY
LOFT
PRESSURE
REACTORS
SAFETY
WATER COOLANT
NITRIC ACID
SILICON
HEAT EXCHANGERS
LIQUID METALS
OPERATION
POTASSIUM ALLOYS
SODIUM ALLOYS
HEAT TRANSFER
HEATING
HYDROCARBONS
TUBES
DEPOSITS
FILTERS
RUTHENIUM
VESSELS
EXPERIMENTAL BREEDER REACTOR-II/fuel reprocessing for
uranium recovery from pyrometallurgical process scrap in
SILICON/effects on solubility of aluminum-uranium alloys
ALUMINUM ALLOYS AND SYSTEMS/Al-U
solubility of
effects of silicon on
URANIUM ALLOYS AND SYSTEMS/Al-U
solubility of
effects of silicon on
REACTOR FUEL ELEMENTS/reprocessing of zirconium-containing
materials corrosion resistance in
PULSE COLUMNS/pulse amplitude and liquid level measurements in
URANIUM/separation from EBR-II pyrometallurgical process scrap by solvent extraction
NEPTUNIUM/separation from irradiated aluminum-uranium alloy fuels in ICPP facility
URANIUM/separation from irradiated aluminum-uranium alloy fuels in ICPP facility
URANIUM ALLOYS AND SYSTEMS/Al-U
separation of neptunium and uranium from irradiated
ICPP facility for
ALUMINUM ALLOYS AND SYSTEMS/Al-U
separation of neptunium and uranium from irradiated
ICPP facility for
ZIRCONIUM ALLOYS AND SYSTEMS/U-Zr
separation of uranium from irradiated
URANIUM/separation from uranium-zirconium alloy fuel
MERCURY/separation from waste solutions by electrochemical methods
RADIOACTIVE WASTE/separation of mercury from liquid
by electrochemical methods
REACTORS/containment buildings for
protective coatings for
FISSION PRODUCTS/ reactions in contamination-decontamination experiments
REACTORS
PRESSURIZED- WATER/loss-of-coolant accidents in
research progress on
URANIUM ALLOYS AND SYSTEMS/U-Zr
separation of uranium from irradiated
REACTOR SAFETY EXPERIMENTS/ contamination-decontamination studies on LOFT
DECONTAMINATING AGENTS/efficiency of
effects of application by foam techniques on
ALUMINUM ALLOYS AND SYSTEMS/Al- U
production by fluidized-bed techniques
URANIUM ALLOYS AND SYSTEMS/Al-U
production by fluidized-bed techniques
URANYL NITRATES/melting of hexahydrates of
volume changes in
ADVANCED TEST REACTOR/simulation of
development of analog computer program for
URANIUM/separation from EBR-II fuel by electrolytic dissolution and solvent extraction
REACTOR FUELS/reprocessing of graphite
combustion-dissolution methods for
STAINLESS STEEL/corrosion of Type 304L
in fluoride-bearing plant decontaminating solutions
REACTOR FUEL ELEMENTS/ reprocessing of zirconium-clad uranium dioxide-zirconium dioxide
by fluoride volatility techniques
URANIUM/separation from zirconium-clad uranium dioxide- zirconium dioxide fuels by fluoride volatility process
RADIOACTIVE WASTE/ calcination of
operation of facility for
RADIOACTIVE WASTE/calcination of fluoride-bearing zirconium