Numerical Simulation and Experimental Research of Flow Resistance Characteristics of East Lower Tungsten Divertor Module

Abstract

During long-pulse plasma operation with high power in tokamak, excessive heat load on divertor may lead to material melting or erosion of the first wall material, which enhances impurity radiation and degrades plasma performance. As an important component of the first wall, divertor cooling system is important for the high power and stable operation of the device. The Experimental Advanced Superconducting Tokamak (EAST) is committed to achieving more than 400 s long-pulse H-mode operations, which is equipped with a first wall of full metal. The 10 MW/m2 heat load on divertor means a big challenge for the continuous operation of the system, but the current divertor cannot meet the conditions, so it needs to be upgraded. In order to check whether the cooling water system of the new divertor in EAST can meet the requirements, a fluid test was built to measure the flow rate and flow drop of the divertor. The results show that the difference between the test results and the results of ANSYS-based simulation is 9 %, and the maximum difference between the results of the comparison of two different model parts is 3 %. It is concluded that the cooling water system of the divertor in EAST can achieve the heat load and safety requirements.