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Metal Fuel Performance in Sodium-cooled Fast Reactors: Recent Progress on Post Irradiation Examination

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The U.S. Department of Energy (DOE) has a long history of research and development in sodium cooled fast reactor technologies, exemplified by programs such as the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF). These efforts included the use of metal fuels as driver fuel, which were extensively tested under both steady-state and off-normal conditions, demonstrating outstanding performance and a substantial safety margin. To advance understanding of metal fuel behavior under normal and transient conditions—and to meet current industry needs for fuel qualification—the DOE Office of Nuclear Energy’s Advanced Fuel Campaign is conducting post-irradiation examinations (PIE) and detailed characterization of legacy metal fuel specimens from EBR-II and FFTF. This presentation will highlight recent progress in these activities and introduce innovative experimental approaches.
Original languageAmerican English
Title of host publicationGlobal 2026
DOIs
StatePublished - Aug 16 2026

INL Publication Number

  • INL/CON-25-85005
  • 199706

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