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An electromagneti@M) analysis of the ITER blanket system at the plasma disruption has been pedormed to investigate eddy current and EM force distributions on the blanket modules, especially with the emphasis on the effect of the toroidal slits on the module side surfaces on the EM force reduction at the centered plasma disruption. As the results, the installation of the toroidal slits on the module side surfaces was found to be effective to the EM force reduction on the module, by about 7 % for a slit, 16 % for 2 slits and 25 % for 3 slits, respectively, compared with that on the module structure without the slits. Maximum stress induced at the module attachment edges under the EM forces also decreased by 5 % for a slit, 14 % for 2 slits and 22 YO for 3 slits, respectively. been extensively studied [2],[4], base on the Detailed Design Report prepared by the JCT[3].Then, the EM analysis of the ITER blanket structure with welded attachment concept has been carried out to quantitatively evaluate EM load distribution on the blanket modules at the plasma disruption and to investigate the effect of toroidal slit module concept on the EM force reduction as a function of number of slits. Furthermore, the structural analysis of the inboard blanket module was also conducted to assess the structural feasibility of the module, with an emphasis on the stress reduction on module attachment edge, due to the EM forces obtained from the EM analysis.

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