ITER SHIELDING ANALYSIS

Radiation transport calculations have been carried out to aid in the d esign of the reference shielding and breeding blankets proposed for th e International Thermonuclear Experimental Reactor (ITER). The results of analyses suggest that both blanket assemblies in combination with the surrounding vacuum vessel provide adequate shielding for the toroi dal field coils and reduce the heating and damage to levels commensura te with design guidelines. The induced activation levels and decay hea t generation in the breeding blanket-vacuum vessel may qualify the ass emblies for disposal as Class C low level waste based on US regulation s. The nuclear performance of the shielding around neutral beam inject ion ducts and in the vicinity of the divertor vacuum pumping ports was also investigated. Preliminary results suggest that the proposed neut ral beam injection and divertor port shielding is satisfactory in both cases.