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November 9–12, 2025
Washington, DC|Washington Hilton
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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.
Laila A. El-Guebaly, Mohamed E. Sawan
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 881-886
ITER Nuclear Design | doi.org/10.13182/FST89-A39805
Articles are hosted by Taylor and Francis Online.
The shield design of ITER is required to meet both magnet protection requirements and safety-related criteria. Although the W provides excellent magnet protection, its high specific decay heat caused some concern in case of an accident. A trade study was carried out in which W is replaced by steel in the high neutron flux zones of the inboard shield and the sensitivity of the machine size, cost, and magnet damage to such change was determined. Satisfying the 1019 n/cm2 fast fluence limit for the magnet, the direct cost is essentially the same for the steel and W shields, although the steel shield is 0.1 m thicker. The 0.55 m thick inboard shield of ITER is configured in 3 main layers: a 0.05 m Be layer, followed by a 0.18 m steel layer, then a 0.18 m W layer. Five coolant channels, each 0.01 m wide, are properly distributed across the shield. About 0.1 m thick layer of aqueous Li salt solution at the back of the shield was found necessary to minimize the damage in the magnet. This design meets the neutronics, safety, and thermal hydraulics requirements and there appears to be no feasible problems associated with it.