DocumentCode
2080736
Title
Shielding design options for the TF magnets of ITER
Author
El-Guebaly, Laila A.
Author_Institution
Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
1329
Abstract
Optimization studies performed to design an efficient shield to protect the toroidal-field (TF) magnets of the International Thermonuclear Experimental Reactor (ITER) are described. Several options for the shield design were examined and many shielding materials have been evaluated. The pure stainless steel/H2O shield does not satisfy the magnet radiation limits. When boron carbide, lead, or boron steel is incorporated in the shield, all design limits are met. The midplane of the inner legs and the top and bottom parts of the magnets suffer the greatest damage because of the limited space for the shield. The safety factors associated with the different magnet responses were quantified. These factors account for the increase in damage due to the presence of the assembly gaps between the shield modules and the uncertainties in data, codes, and modeling
Keywords
Tokamak devices; boron compounds; electromagnets; fusion reactor materials; fusion reactor safety; fusion reactor theory and design; lead; shielding; stainless steel; B4C; H2O; ITER; International Thermonuclear Experimental Reactor; Pb; assembly gaps; safety factors; shield; stainless steel; toroidal field magnets; Assembly; Boron; Design optimization; Inductors; Leg; Magnetic materials; Magnets; Protection; Radiation safety; Steel;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102456
Filename
102456
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