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SP-100 fuel pin performance results from the SP-3RR irradiation test

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6023679
;  [1]
  1. Westinghouse Hanford Company, Richland, WA (United States)
The objective of the SP-100 Program is to verify and validate the design of a compact, fast-spectrum nuclear reactor capable of producing tens to hundreds of kilowatts of electrical power in support of a broad range of space applications. The heat source for thermoelectric power generation in the SP-100 reactor design is fuel pins using high-density uranium nitride (UN) fuel, a refractory alloy liner, and niobium-1 % zirconium (Nb-1Zr) alloy cladding. A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor II (EBR-II) and the Fast Flux Test Facility reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pins are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the SP-3RR fuel pin test and presents the first irradiation data on the performance of wrought rhenium liner material and UN fuel at goal burnup of 6 at.%.
OSTI ID:
6023679
Report Number(s):
CONF-930601--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
Country of Publication:
United States
Language:
English