FAST REACTOR MIXED-CARBIDE FUEL ELEMENT DEVELOPMENT PROGRAM. Twelfth Quarterly Progress Report, April--June 1970.
- Research Organization:
- United Nuclear Corp., Elmsford, N. Y. Research and Engineering Center
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(30-1)-3415
- NSA Number:
- NSA-25-004889
- OSTI ID:
- 4097063
- Report Number(s):
- UNC-5263
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-71
- Country of Publication:
- United States
- Language:
- English
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FAST REACTOR MIXED-CARBIDE FUEL ELEMENT DEVELOPMENT PROGRAM. Fourth Quarterly Progress Report, April--June 1968.
Technical Report
·
Mon Jan 01 00:00:00 EST 1968
·
OSTI ID:4097063
FAST REACTOR MIXED-CARBIDE FUEL ELEMENT DEVELOPMENT PROGRAM. Quarterly Progress Report No. 8, April--June 1969.
Technical Report
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Wed Jan 01 00:00:00 EST 1969
·
OSTI ID:4097063
Related Subjects
N30250* -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N38150 -Power Reactor Development-Fuels
EBR-2- FISSION PRODUCTS- FUEL CANS- FUELS- GASES- INCOLOY- IRRADIATION- PLUTONIUM CARBIDES- POWER- PRODUCTION- RADIATION EFFECTS- RODS- STAINLESS STEEL-304- STAINLESS STEEL-316- SWELLING- TESTING- TREAT- URANIUM CARBIDES- VOIDS
FABRICATION
PELLETS DENSITY- EBR-2- IRRADIATION- PLUTONIUM OXIDES- POWDERS- PRESSURE- RADIATION EFFECTS- TESTING- URANIUM OXIDES
URANIUM CARBIDES/PuC-UC
radiation effects on stainless steel-clad fuel pellets of
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on sodium-bonded clad fuels of
in-pile
URANIUM CARBIDES/PuC- UC
radiation effects on sodium-bonded clad fuels of
in-pile
REACTOR FUEL ELEMENTS/radiation effects on rod-type carbide
at 70 to 35 kW/ft
in-pile
URANIUM CARBIDES/PuC-UC
radiation effects on Incoloy 800-clad fuel pellets of
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on stainless steel-clad fuel pellets of
in-pile
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
fabrication of pellets of
for EBR-II irradiation
REACTOR FUEL ELEMENTS/ performance of carbide
in TREAT
REACTOR FUEL ELEMENTS/radiation effects on fission gas release and swelling of unrestrained carbide
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on Incoloy 800-clad fuel pellets of
in-pile
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
fabrication of pellets of
for EBR-II irradiation
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N38150 -Power Reactor Development-Fuels
EBR-2- FISSION PRODUCTS- FUEL CANS- FUELS- GASES- INCOLOY- IRRADIATION- PLUTONIUM CARBIDES- POWER- PRODUCTION- RADIATION EFFECTS- RODS- STAINLESS STEEL-304- STAINLESS STEEL-316- SWELLING- TESTING- TREAT- URANIUM CARBIDES- VOIDS
FABRICATION
PELLETS DENSITY- EBR-2- IRRADIATION- PLUTONIUM OXIDES- POWDERS- PRESSURE- RADIATION EFFECTS- TESTING- URANIUM OXIDES
URANIUM CARBIDES/PuC-UC
radiation effects on stainless steel-clad fuel pellets of
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on sodium-bonded clad fuels of
in-pile
URANIUM CARBIDES/PuC- UC
radiation effects on sodium-bonded clad fuels of
in-pile
REACTOR FUEL ELEMENTS/radiation effects on rod-type carbide
at 70 to 35 kW/ft
in-pile
URANIUM CARBIDES/PuC-UC
radiation effects on Incoloy 800-clad fuel pellets of
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on stainless steel-clad fuel pellets of
in-pile
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-UO$sub 2$
fabrication of pellets of
for EBR-II irradiation
REACTOR FUEL ELEMENTS/ performance of carbide
in TREAT
REACTOR FUEL ELEMENTS/radiation effects on fission gas release and swelling of unrestrained carbide
in-pile
PLUTONIUM CARBIDES/PuC-UC
radiation effects on Incoloy 800-clad fuel pellets of
in-pile
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-UO$sub 2$
fabrication of pellets of
for EBR-II irradiation