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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
E. Greenspan, Y. Karni
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1605-1610
Solid Breeder Blanket | doi.org/10.13182/FST86-A24961
Articles are hosted by Taylor and Francis Online.
Possibilities for maximizing the tritium breeding ratio (TBR) and for minimizing the major radius of the Next European Torus (NET) fusion device are investigated using the nucleonic optimization code SWAN. It is found that a NET like device can be designed to be tritium self-sufficient even when tritium breeding is restricted to the outboard blanket, while enabling a 25 cm reduction in the major radius of the device, Additional 20 cm major radius reduction is expected from replacing the conventional steel-water inboard shield by an optimized shield based on a tungsten-copper composite material and titanium-hydride.