Three-Dimensional Neutronics Analysis for the U.S. Magnet Shield of ITER
Fusion Science and Technology / Volume 19 / Number 3P2B / May 1991 / Pages 1469-1474
ITER / Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) / dx.doi.org/10.13182/FST91-A29548
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Detailed three-dimensional neutronics calculations have been performed for the U.S. design of the ITER magnet shield. The total nuclear heating in the TF coils is 35 kW in the technology phase and 42 kW in the physics phase. Using 5 cm thick W back shield layers behind the vacuum vessel in locations with limited shielding space results in acceptable local magnet damage levels. The parts of the TF coils adjacent to the divertor vacuum pumping ducts are well protected against streaming radiation.
