The shielding analyses of the inboard blanket, the vacuum vessel and the toroidal field coil in ITER were conducted by Monte Carlo and 2- dimensional discrete Sn methods taking the radiation streaming through the gap between the adjacent blanket modules into account, and their nuclear responses were evaluated1'. The nuclear responses of the toroidal field coil could fully satisfy the shielding design targets. On the other hand, the helium production rates at the back of the inboard blanket were about 2 - 3 times higher than the shielding design target at the end of the operation.
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