NEUTRONICS AND SHIELDING RESULTS OF THE US INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR BLANKET TRADE-OFF STUDY

Detailed neutronics and shielding analyses have been performed for the different International Thermonuclear Experimental Reactor (ITER) bla nket design options considered in the ITER blanket option trade-off st udy. The options considered included a self-cooled Li/V option, a heli um-cooled Li/V option, ferritic steel designs with helium-cooled first wall and liquid metal (Li or LiPb) cooled blanket, the conceptual des ign activity (CDA) design option, and a water-cooled 316 stainless ste el (SS) non-breeding shield option. Among the tritium breeding blanket design options, the self-cooled Li/V option has the highest breeding potential while the CDA blanket design option has the best shielding p erformance. Additional shielding improvement is achieved by using a no n-breeding SS/H2O shield.