Fabrication of core demonstration experiments for irradiation in FFTF (Fast Flux Test Facility)
Conference
·
OSTI ID:6909345
- Westinghouse Hanford Co., Richland, WA (USA)
- Oak Ridge National Lab., TN (USA)
A major initiative to develop and irradiate a long-life, mixed-oxide fuel system in the Fast Flux Test Facility (FFTF) has been implemented by Westinghouse Hanford Company for the US Department of Energy. The FFTF, shown in Figures 1 and 2, is a 400 megawatt thermal, fast liquid metal reactor that tests liquid metal, space and fusion fuels and materials. The new fuel system, called the Core Demonstration Experiment (CDE) demonstrates the capability of achieving a three- to four-year life in a prototypic heterogeneous reactor environment under prototypic power and temperature conditions. This fuel system will greatly increase fuel performance and lifetime from the current standard FFTF driver fuel. New design features, fabrication development, CDE assembly fabrication, and irradiation status have been described.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6909345
- Report Number(s):
- WHC-SA-0470; CONF-900608--29; ON: DE90012642
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALLOY-HT-9
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
DEMONSTRATION PROGRAMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
FUELS
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
LIQUID METAL COOLED REACTORS
MARTENSITIC STEELS
MATERIALS
MIXED OXIDE FUELS
MOLYBDEN
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PELLETS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SERVICE LIFE
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR12MOV
STEEL-CR17NI12MO3
STEELS
TEST REACTORS
WELDED JOINTS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALLOY-HT-9
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
DEMONSTRATION PROGRAMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL PELLETS
FUEL PINS
FUELS
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
LIQUID METAL COOLED REACTORS
MARTENSITIC STEELS
MATERIALS
MIXED OXIDE FUELS
MOLYBDEN
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PELLETS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SERVICE LIFE
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR12MOV
STEEL-CR17NI12MO3
STEELS
TEST REACTORS
WELDED JOINTS