Design of the Helium Cooled Molten Lithium TBM for ITER in Korea

One of the main engineering performance goals of International Thermonucler Experimental Reactor (ITER) is to test and validate design concepts of tritium breeding blankets relevant to a power producing reactor. The tests will foresee on modules including the demonstration of a breeding capability that would lead to tritium self heat suitable for electricity generation. The test blanket modules (TBMs) have been proposed by several parties. And the proposed TBMs by each party will be located in the common frame of ITER ports such as port no. 1, 2, and 18 with the thickness of 200 mm. We have been designing the own TBMs such as Helium Cooled Solid Breeder (HCSB) and Helium Cooled Molten Lithium (HCML). In this paper, the latter one is explained with regard to the design procedure and its analysis