POTENTIAL FFTF CARBIDE FUELS.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(45-1)-1830
- NSA Number:
- NSA-22-027457
- OSTI ID:
- 4531117
- Report Number(s):
- BNWL-513
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-68
- Country of Publication:
- United States
- Language:
- English
Similar Records
POTENTIAL FFTF ALLOY FUELS.
FFTF DRIVER FUEL: PuO$sub 2$-STAINLESS STEEL CERMET
FFTF FUEL ELEMENT DESIGN.
Technical Report
·
Sun Jan 01 00:00:00 EST 1967
·
OSTI ID:4531117
FFTF DRIVER FUEL: PuO$sub 2$-STAINLESS STEEL CERMET
Technical Report
·
Mon Nov 01 00:00:00 EST 1965
·
OSTI ID:4531117
+1 more
FFTF FUEL ELEMENT DESIGN.
Technical Report
·
Sun Jan 01 00:00:00 EST 1967
·
OSTI ID:4531117
+1 more
Related Subjects
N38550* -Research & Test Reactors & Critical Assemblies- Fuels
ANALYSIS
BURNUP
ECONOMICS
EFFICIENCY
FABRICATION
FTR
FUEL CANS
FUEL ELEMENTS
FUELS
NEUTRON FLUX
OPERATION
PERFORMANCE
PLUTONIUM CARBIDES
RESEARCH REACTORS
SAFETY
STAINLESS STEELS
TESTING
URANIUM CARBIDES
NEUTRONS/flux distribution in FTR stainless steel clad uranium carbide (UC) and plutonium carbide (PuC)-uranium carbide (UC) fuel elements
measurements of
URANIUM CARBIDES/performance of driver fuels of
analysis for FTR optimum
PLUTONIUM CARBIDES/PuC-UC
performance of driver fuels of
analysis for FTR optimum
URANIUM CARBIDES/PuC-UC
performance of driver fuels of
analysis for FTR optimum
FAST TEST REACTOR/fuel for
performance testing of uranium carbide (UC) and plutonium carbide (PuC)-uranium carbide (UC) driver
ANALYSIS
BURNUP
ECONOMICS
EFFICIENCY
FABRICATION
FTR
FUEL CANS
FUEL ELEMENTS
FUELS
NEUTRON FLUX
OPERATION
PERFORMANCE
PLUTONIUM CARBIDES
RESEARCH REACTORS
SAFETY
STAINLESS STEELS
TESTING
URANIUM CARBIDES
NEUTRONS/flux distribution in FTR stainless steel clad uranium carbide (UC) and plutonium carbide (PuC)-uranium carbide (UC) fuel elements
measurements of
URANIUM CARBIDES/performance of driver fuels of
analysis for FTR optimum
PLUTONIUM CARBIDES/PuC-UC
performance of driver fuels of
analysis for FTR optimum
URANIUM CARBIDES/PuC-UC
performance of driver fuels of
analysis for FTR optimum
FAST TEST REACTOR/fuel for
performance testing of uranium carbide (UC) and plutonium carbide (PuC)-uranium carbide (UC) driver