Design Study And Preliminary Feasibility Analysis Of Divertor With Iter-Like Pfu For Advanced Tokamak

The divertor is one of the key plasma facing components (PFCs) in fusion device and shall exhaust high heat flux coming from the plasma. The paper presents an engineering design solution accommodating the physical requirements and the removal of 10 MW/m 2 steady heat flux. The proposed divertor design employs reliable PFCs structure which can be manufactured by proven mature technologies. There are effective measures to ensure assembly and installation accuracy in this design concept. The convenient maintenance is guaranteed by small modular design. Preliminary feasibility analysis has been carried out with respect to thermal and hydraulic, which verifies that the design successfully meets the requirements for the plasma operation of advanced tokamak.