Reusable fuel test assembly for the FFTF

Conference · Tue Dec 31 23:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7057704

Pitner, A L; Dittmer, J O ^[1]

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1. Westinghouse Hanford Co., Richland, WA (United States)

A fuel test assembly that provides re-irradiation capability after interim discharge and reconstitution of the test pin bundle has been developed for use in the Fast Flux Test Facility (FFTF). This test vehicle permits irradiation test data to be obtained at multiple exposures on a few select test pins without the substantial expense of fabricating individual test assemblies as would otherwise be required. A variety of test pin types can be loaded in the reusable test assembly. A reusable test vehicle for irradiation testing in the FFTF has long been desired, but a number of obstacles previously prevented the implementation of such an experimental rig. The MFF-8A test assembly employs a 169-pin bundle using HT-9 alloy for duct and cladding material. The standard driver pins in the fuel bundle are sodium-bonded metal fuel (U-10 wt% Zr). Thirty-seven positions in the bundle are replaceable pin positions. Standard MFF-8A driver pins can be loaded in any test pin location to fill the bundle if necessary. Application of the MFF-8A reusable test assembly in the FFTF constitutes a considerable cost-saving measure with regard to irradiation testing. Only a few well-characterized test pins need be fabricated to conduct a test program rather than constructing entire test assemblies.

• OSTI ID: 7057704
• Report Number(s): CONF-920606--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 65; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALKALI METALS
ALLOY-HT-9
ALLOYS
AUSTENITIC STEELS
BARYONS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CONTAMINATION
CORROSION
CORROSION RESISTANT ALLOYS
ELEMENTARY PARTICLES
ELEMENTS
EPITHERMAL REACTORS
FABRICATION
FAST NEUTRONS
FAST REACTORS
FERMIONS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
HADRONS
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IMPLEMENTATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
MARTENSITIC STEELS
MATERIALS
METALS
MOLYBDEN
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NEUTRONS
NICKEL ALLOYS
NUCLEONS
PERFORMANCE TESTING
POST-IRRADIATION EXAMINATION
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAMPLE HOLDERS
SHIELDS
SODIUM
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR12MOV
STEEL-CR17NI12MO3
STEELS
STRESS CORROSION
SWELLING
TEST REACTORS
TESTING