QUARTERLY STATUS REPORT ON THE ADVANCED PLUTONIUM FUELS PROGRAM, OCTOBER 1-- DECEMBER 31, 1967

Technical Report · Mon Dec 30 19:00:00 EST 1968

DOI:https://doi.org/10.2172/4903344· OSTI ID:4903344

• Research Organization: Los Alamos Scientific Lab., N. Mex.
• Sponsoring Organization: Sponsor not identified; USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• NSA Number: NSA-22-027487
• OSTI ID: 4903344
• Report Number(s): LA--3880
• Country of Publication: United States
• Language: English

Related Subjects

ACTIVATION ANALYSIS
ANALYSIS
Accessories
BONDING
BREEDING
CARBON
CARBON/determination in germanium and stainless steel by helium-3 activation technique
CERAMICS
CONTROL
CORROSION
CRITICALITY- - CROSS SECTIONS
CRYSTALS
DEFECTS
DETERMINATION
DIFFRACTION
DISTRIBUTION
FAST NEUTRONS
FISSION
FISSION PRODUCTS
FISSION PRODUCTS/release and distribution in sodium coolant from plutonium carbide--uranium carbide fuel
FISSION PRODUCTS/yields from fast neutron fission in plutonium
gamma scanning techniques for measurement of
FISSION YIELD
FUEL CANS
FUELS
GAMMA DETECTION
GERMANIUM
HEAT TRANSFER
HELIUM 3
HIGH TEMPERATURE
HYDROGEN
IMPURITIES
IRRADIATION
LATTICES
LIQUID METAL COOLANT
MEASUREMENT
N38700* --Reactor Components
Fuels & Accessories
N38700* --Reactor Components
Fuels &
NEUTRON BEAMS
NEUTRONS
NEUTRONS/effects on fast reactor fuel materials
Nuclear Criticality Safety Program (NCSP)
OXYGEN
OXYGEN/determination in germanium by helium-3 activation technique
OXYGEN/removal from sodium
performance of cold traps for
OXYGEN/solubility in sodium at 125 to 300--C
PERFORMANCE
PLUTONIUM
PLUTONIUM CARBIDES
PLUTONIUM CARBIDES/ crystal structure of room temperature Pusub2sub2Csub3sub3
neutron diffraction determination of
PLUTONIUM CARBIDES/PuC--UC
compatibility of sodium-bonded
with cladding materials
PLUTONIUM CARBIDES/PuC--UC
high temperature properties of
PLUTONIUM CARBIDES/PuC--UC
preparation by hydrogen reduction method
PLUTONIUM NITRIDES
PLUTONIUM NITRIDES/PuN--UN
compatibility of sodium-bonded
with cladding materials
PLUTONIUM NITRIDES/thermodynamic properties measurements on PuN
PLUTONIUM OXIDES
PLUTONIUM OXIDES PuOsub2sub2/PuOsub2sub2--UOsub2sub2
preparation and high temperature properties of
PREPARATION
RADIATION EFFECTS
REACTIVITY
REACTOR FUEL ELEMENTS/heat transfer properties of sodium-bonded
effects of bond defects on
REACTOR FUELS/compatibility of sodium-bonded carbide and nitride
with cladding materials
REACTOR FUELS/preparation of ceramic plutonium
REACTOR FUELS/properties of ceramic plutonium
determination of high temperature
REACTOR FUELS/radiation effects on fast
determination of neutron
REACTORS
REACTORS
BREEDER/physics analysis of
evaluation of nuclear data for
REACTORS
FAST/ physics analysis of
evaluation of nuclear data for
REACTORS
FAST/fuels for
neutron irradiation effects on
REDUCTION
SODIUM
SODIUM/analysis for impurities
development of techniques for
SODIUM/corrosive effects on fuel cladding materials at 650--C
SODIUM/fission product distribution in
from plutonium carbide--uranium carbide fuel
SODIUM/quality control in
performance of cold traps for
SODIUM/solvent properties for oxygen at 125 to 300--C
SOLUBILITY
STAINLESS STEEL-316
STAINLESS STEEL/analysis of carburized
for carbon by helium-3 activation technique
STAINLESS STEEL/corrosion of Type 316
by sodium
STAINLESS STEELS
STANDARDS
THERMODYNAMICS
TRANSPORT
TRAPS
TRAPS/performance of cold
for impurity control in sodium
URANIUM CARBIDES
URANIUM CARBIDES/PuC--UC
compatibility of sodium-bonded
with cladding materials
URANIUM CARBIDES/PuC--UC
high temperature properties of
URANIUM CARBIDES/PuC--UC
preparation by hydrogen reduction method
URANIUM DIOXIDE
URANIUM NITRIDES
URANIUM NITRIDES/PuN--UN
compatibility of sodium- bonded
with cladding materials
URANIUM OXIDES UOsub2sub2/PuOsub2sub2--UOsub2sub2
preparation and high temperature properties of