ADVANCED PLUTONIUM FUELS PROGRAM. Quarterly Status Report, April 1--June 30, 1968, and Second Annual Report, FY 1968

Technical Report · Tue Dec 31 00:00:00 EST 1968

DOI:https://doi.org/10.2172/4904472· OSTI ID:4904472

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: Sponsor not identified
• DOE Contract Number: W-7405-ENG-36.
• NSA Number: NSA-22-050841
• OSTI ID: 4904472
• Report Number(s): LA-3993
• Resource Relation: Other Information: UNCL
• Country of Publication: United States
• Language: English

Related Subjects

N38700* -Reactor Components
Fuels &
Accessories
BREEDING
EBR-2
FAST NEUTRONS
FAST REACTORS
FFTF
FUEL ELEMENTS
FUELS
REACTORS
RESEARCH REACTORS BEHAVIOR
CESIUM 137
CONFIGURATION
FABRICATION
IMPURITIES
OPENINGS
ORIFICES
PERFORMANCE
PLUTONIUM CARBIDES
SODIUM
STANDARDS
TESTING
URANIUM CARBIDES
MELTING
CORROSION
STAINLESS STEEL-316
STAINLESS STEELS
PLUTONIUM OXIDES
THERMAL CONDUCTIVITY
URANIUM DIOXIDE
ORIFICES/operation characteristics of plugging meter
for liquid sodium systems
SODIUM/technology for liquid
analysis of Los Alamos Scientific Laboratory 1968
URANIUM CARBIDES/PuC-UC
fabrication of pellet- shaped
effects of techniques on quality
PLUTONIUM CARBIDES/PuC-UC
thermal properties of
analysis at 1600 to 2500$sup 0$C of
URANIUM CARBIDES/PuC-UC
thermal properties of
analysis at 1600 to 2500$sup 0$C of
PLUTONIUM CARBIDES/ melting behavior of
analysis up to 1660$sup 0$C of
PLUTONIUM OXIDES PuO$sub 2$/ PuO$sub 2$-UO$sub 2$
heat of fission of
analysis of
URANIUM OXIDES UO$sub 2$/ PuO$sub 2$-UO$sub 2$
heat of fission of
analysis of
PLUTONIUM CARBIDES/PuC- UC
compatibility with Type 316 stainless steel-cladding of sodium bonded
evaluation of
URANIUM CARBIDES/PuC-UC
compatibility with Type 316 stainless steel-cladding of sodium bonded
evaluation of
PLUTONIUM NITRIDES/PuN-UN
compatibility with Type 316 stainless steel-cladding of sodium bonded
evaluation of
URANIUM NITRIDES/PuN-UN
compatibility with Type 316 stainless steel- cladding of sodium bonded
evaluation of
STAINLESS STEEL/compatibility of cladding of Type 316
with plutonium carbide-uranium carbide and plutonium nitride-uranium nitride sodium bonded fuels
SODIUM/compatibility of Type 316 stainless steel-clad plutonium carbide (PuC)-uranium carbide (UC) and plutonium nitride (PuN)- uranium nitride (UN) fuel elements bonded with
EXPERIMENTAL BREEDER REACTOR-II/fission product distribution in fuel pins of
$gamma$ scan analysis of
REACTORS
FAST/physics measurements for breeder
computer programs for calculation of
REACTORS
BREEDER/physics measurements for fast
computer programs for calculation of
EXPERIMENTAL BREEDER REACTOR-II/radiation effects on PuC-UC fuel elements in
analysis of neutron
URANIUM CARBIDES/PuC-UC
radiation effects on EBR-2 driver fuel elements
analysis of neutron
SODIUM/ behavior of liquid
effects of impurities on
NEUTRONS/effects on plutonium carbide (PuC)-uranium carbide (UC) EBR-2 fuel elements
analysis of
PLUTONIUM CARBIDES/PuC-UC
radiation effects on EBR-2 driver fuel elements
analysis of neutron
CESIUM ISOTOPES Cs-137/effects on behavior of liquid sodium
FAST FLUX TEST FACILITY/fuel development for
evaluation of technology for
PLUTONIUM CARBIDES/PuC-UC
fabrication of pellet-shaped
effects of techniques on quality
N38700* -Reactor Components
Fuels & Accessories