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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Fusion Science and Technology
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Latest News
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
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.
