UWFDM-966 Activation Analyses for the Different Options Considered in the U.S. ITER Blanket Trade-Off Study
نویسندگان
چکیده
Detailed activation analyses have been performed for the different blanket design options considered in the ITER blanket option trade-off study. The options considered included a selfcooled Li/V option, a helium cooled Li/V option, and a water cooled 316 SS non-breeding shield option. A vacuum vessel made of double wall inconel 625 and water cooled 316 SS balls is used with all options. The He-cooled blanket activity is higher than that of the self-cooled blanket due to the larger structure content. Meanwhile, the vacuum vessel activity is lower for the He-cooled blanket option due to the larger neutron attenuation in the blanket. Shield activity and decay heat of the 316 SS/H2O option are higher than those for the Li/V blankets due to the large amount (80%) of 316 SS used. In both Li/V options the blanket qualifies as Class C low level waste. On the other hand, the 316 SS/H2O shield does not qualify for disposal as low level waste. The 316 SS/H2O option produces the highest off-site doses in case of accidental release of 100% of its radioactive inventory. Only remote maintenance would be allowed for all options.
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