REACTOR DEVELOPMENT PROGRAM. Progress Report, October 1967

Technical Report · Sun Dec 31 00:00:00 EST 1967

DOI:https://doi.org/10.2172/4902357· OSTI ID:4902357

• Research Organization: Argonne National Lab., Ill.
• Sponsoring Organization: Sponsor not identified
• DOE Contract Number: W-31-109-ENG-38.
• NSA Number: NSA-22-009988
• OSTI ID: 4902357
• Report Number(s): ANL-7391
• Resource Relation: Other Information: UNCL
• Country of Publication: United States
• Language: English

Related Subjects

N38100* -Power Reactor Development
REACTORS ANALYSIS
BISMUTH
CARBON
CESIUM
CHEMICAL ANALYSIS
CONTROL
CONTROL ELEMENTS
DEFORMATION
DEPOSITS
DETERMINATION
EBR-2
ELEMENTS
EXPANSION
FEEDBACK
FISSION PRODUCTS
FLUID FLOW
FUEL ELEMENTS
FUELS
IRRADIATION
MEASUREMENT
MIXING
OPERATION
POWER
REACTIVITY
REACTOR CORE
RESEARCH REACTORS
SEPARATION PROCESSES
SILICON
SODIUM
SUPERHEATING
SWELLING
TEMPERATURE
TIN
TRACE AMOUNTS
TRANSFER FUNCTIONS
URANIUM ALLOYS
VIBRATIONS
NO KEYWORDS
ANGULAR DISTRIBUTION
ERRORS
FAST NEUTRONS
FISSION
MASS
STATISTICS
TIME
URANIUM 235
ANALYSIS
CRITICAL ASSEMBLIES
CROSS SECTIONS
DETECTION
DOPPLER REACTIVITY
FFTF
FLOWMETERS
FTR
IMPURITIES
LIQUID METAL COOLANT
MAGNETIC MATERIALS
MOCKUP
NEUTRONS
PLUTONIUM
SPECTRAL SHIFT
TESTING
USES
ZPR-3
ALLOYS
BURNUP
CANNING
COATING
CORROSION
CRUCIBLES
GASES
MECHANICAL PROPERTIES
NUMERICALS
PLUTONIUM CARBIDES
URANIUM
URANIUM CARBIDES
ZIRCONIUM
BREEDING
NEUTRON FLUX
RESONANCE
SCATTERING
CERAMICS
DIFFUSION
FLUORINATION
HIGH TEMPERATURE
OXIDES
PELLETS
PLUTONIUM OXIDES
PRESSURE
RUTHENIUM
SINTERED MATERIALS
URANIUM DIOXIDE
AARR
ANALOG SYSTEMS
ACCIDENTS
CONTAINMENT
EQUATIONS
MELTDOWN
PROGRAMMING
REACTOR SAFETY
TREAT
FLOWMETERS/testing of prototype magnetic
REACTOR FUEL ELEMENTS/burnup of uranium-plutonium
CRUCIBLES/materials for containing reactive alloys of uranium-zirconium
development of
CRITICAL ASSEMBLIES/ Doppler coefficient and plutonium systems studies in ZPR-3
summary of
CRITICAL ASSEMBLIES/use of ZPR-3 for FFTF mockup studies
FAST TEST REACTOR/neutron cross sections for
generation of core-averaged
CRITICAL ASSEMBLIES/reactivity worth measurements on FTR mockup in ZPR-3
SODIUM/analysis for impurities
analytical and in-line techniques for
PLUTONIUM CARBIDES/PuC-UC
compatibility with jacketing materials
REACTOR FUEL ELEMENTS/cladding alloys for
mechanical properties of
COATINGS/mechanical properties of fuel element
COATINGS/corrosion of fuel element
effects of sodium on
REACTORS
LIQUID METAL-COOLED/neutron fluxes in
detailed calculation of effects of interfaces between resonance- scattering media on
REACTORS
BREEDER/neutron flux calculations for
effects of interfaces between resonance-scattering media on
URANIUM ISOTOPES U-235/fission fragment values for
mass-angle dependence of
URANIUM CARBIDES/PuC-UC
compatibility with jacketing materials
REACTOR FUELS/diffusion coefficients for pressure sintered ceramic
REACTOR FUELS/mechanical properties of high temperature oxide
REACTOR FUEL ELEMENTS/fluorination of pellets of fission product-plutonium oxide (PuO$sub 2$)-uranium oxide (UO )
URANIUM OXIDES UO$sub 2$/fluorination of fuel pellets of
PLUTONIUM OXIDES PuO$sub 2$/fluorination of fuel pellets of
results of
RUTHENIUM/chemistry of
analysis by fluoride volatility technique
ARGONNE ADVANCED RESEARCH REACTOR/reactivity additions to
analog model for hot-spot development caused by
REACTORS
POWER/accident calculations for 1000 MW(e)
computer code for
REACTOR SAFETY EXPERIMENTS/fuel meltdown studies in TREAT
metallic
REACTOR CONTAINMENT STRUCTURES/safety of
momentum equations in finite difference form for calculation of
EXPERIMENTAL BREEDER REACTOR-II/control rod and driver assemblies for
reactivity worths of
EXPERIMENTAL BREEDER REACTOR-II/power coefficient for
effects of core size on
EXPERIMENTAL BREEDER REACTOR-II/transfer function measurements in
results in terms of feed back of
EXPERIMENTAL BREEDER REACTOR-II/reactivity measurements using rod-drop technique in
EXPERIMENTAL BREEDER REACTOR-II/fuel element bowing of
post irradiation measurements of
REACTOR FUELS/swelling of
effects of trace element impurities on
REACTOR FUELS/analyses of irradiated
determination of trace element amounts by