U.S. ITER Shield and Blanket Design Activities^*

* Work supported by the U.S. Department of Energy/Office of Fusion Energy

Abstract

This paper summarizes nuclear-related work in support of the U.S. effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He³.

Notes

* Work supported by the U.S. Department of Energy/Office of Fusion Energy