FFTF metal fuel pin fabrication

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5228255

Dittmer, J O; Benecke, M W; Feigenbutz, L V

A major new initiative to develop, irradiate, and qualify a binary uranium/zirconium metal-fuel system in the Fast Flux Test Facility (FFTF) has been implemented by the Westinghouse Hanford Company for the US Department of Energy. Metal-fuel test assemblies have been designed and fabricated, and are now being irradiated in FFTF to provide the data needed to support the potential use of binary metal fuels in FFTF and other liquid-metal reactors. These development efforts support licensing activities for metal-fuel use in near-term advanced liquid-metal reactors.

• OSTI ID: 5228255
• Report Number(s): CONF-890604--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
ALKALI METALS
ALLOYS
AUSTENITIC STEELS
CARBON ADDITIONS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ELEMENTS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
HEAT RESIS
HIGH ALLOY STEELS
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
LOADING
MARTENSITE
MATERIALS HANDLING
MATERIALS TESTING
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONDESTRUCTIVE TESTING
OXIDATION
PERFORMANCE
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
TEST REACTORS
TESTING
TRANSITION ELEMENTS
URANIUM
ZIRCONIUM