Fusion Science and Technology / Volume 64 / Number 2 / August 2013 / Pages 288-292
Divertor and High-Heat-Flux Components / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012
Korean high heat flux test facility for the plasma facing components of nuclear fusion machines will be constructed to evaluate the performance of each component. This facility for plasma facing materials will be equipped with an electron beam gun with a 60 kV acceleration voltage. The system also includes a 300 kW power supply system, a vacuum test chamber, and a beryllium filtration system for the ITER first wall mockups. First, a commissioning test has been scheduled to establish the installation and preliminary performance experiments of the copper hypervapotron mockups and evaluate the thermo-hydraulic specifications. Second, a qualification test will be performed to evaluate the CuCrZr duct liner in the ITER neutral beam injection facility and the ITER first wall small-scale mockups of the semi-prototype, at up to 1.5 and 5 MW/m2 high heat flux, respectively. This electron beam system will be used to qualify the specifications of the plasma facing components in the KSTAR tokamak and other fusion devices.