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Title: Reusable fuel test assembly for the FFTF

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 constructingmore » entire test assemblies.« less
Authors:
;  [1]
  1. (Westinghouse Hanford Co., Richland, WA (United States))
Publication Date:
OSTI Identifier:
7057704
Report Number(s):
CONF-920606--
Journal ID: ISSN 0003-018X; CODEN: TANSA
Resource Type:
Conference
Resource Relation:
Journal Name: Transactions of the American Nuclear Society; (United States); Journal Volume: 65; Conference: American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; FUEL ELEMENTS; PERFORMANCE TESTING; SAMPLE HOLDERS; ALLOY-HT-9; CONTAMINATION; FABRICATION; FAST NEUTRONS; FUEL ASSEMBLIES; FUEL CANS; IMPLEMENTATION; IRRADIATION; POST-IRRADIATION EXAMINATION; SHIELDS; SODIUM; STAINLESS STEEL-316; STRESS CORROSION; SWELLING; ALKALI METALS; ALLOYS; AUSTENITIC STEELS; BARYONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTARY PARTICLES; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FERMIONS; HADRONS; HEAT RESIS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MARTENSITIC STEELS; MATERIALS; METALS; MOLYBDEN; MOLYBDENUM ADDITIONS; MOLYBDENUM ALLOYS; NEUTRONS; NICKEL ALLOYS; NUCLEONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR12MOV; STEEL-CR17NI12MO3; STEELS; TEST REACTORS; TESTING 210500* -- Power Reactors, Breeding