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
• NSA Number: NSA-23-013824
• OSTI ID: 4905515
• Report Number(s): IN--1201
• Country of Publication: United States
• Language: English

Related Subjects

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