Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak

The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000 s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses.