Fuel fabrication processes, design and experimental conditions for the joint US-Swiss mixed carbide test in FFTF (AC-3 test)

Fuels for sodium-cooled fast reactors: US perspective

“…b Based on EBR-II Mark-V driver fuel (which was the Mark-IV design adapted to U-Pu-Zr [13] and the MFF experiment series in FFTF [29,63]). c Based on successful irradiation tests of MC fuel in EBR-II and the FFTF AC-3 test [79,80,82]. d Percent of apparent, as-measured theoretical density of 15.6-15.9 g/cm 3 .…”

“…The program and experience in India would necessarily be considered prior to any significant work in the US with carbide fuels. A set of suggested reference design parameters for mixed carbide fuel is presented in Table 9, reflecting experience with prior US irradiation testing [79,80,82].…”

“…Over 200 MC fuel rods were irradiated in FFTF in two assemblies: the ACN-1 experiments with rods fabricated using Type 316SS and D9 cladding and the FC-1 test, which was a full-size, 91-rod FFTF assembly using Type 316SS and D9 cladding and ducts [5,[79][80][81]. The AC-3 test was composed of 91 full-size, D9-clad rods of which 25 rods contained sphere-pac fuel and 66 rods contained pellet fuel [80][81][82]. That assembly was irradiated to the goal 9 at.% burnup without breach.…”

A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels

“…Carbides are attractive due to high thermal conductivity, less restructuring of the microstructure compared to oxide or metal, and a fissile density that permits superior breeding performance and high specific power operation, which combine to increase Pu production and reduce fuel cycle and power costs [46].…”

“…Over 200 carbide-fueled UC-PuC rods were irradiated in FFTF, including both Na-bonded and He-bonded types [12,[43][44][45][46]. The AC-3 test irradiated both pellet and sphere-pac fuel [45].…”