Impurity transport and access studies in high-βp plasmas at low toroidal rotation
2025 Research Campaign, Task Force: Integrated High beta-p Scenario
Purpose of Experiment
The main goal of this experiment is investigation of the core high-Z impurities transport and control through decreasing the toroidal rotation and increasing the electron heating in high poloidal beta (βP) scenario with density ITB. The key hypothesis to be tested is that the high-Z impurities neoclassical transport will be decreased even dominated by turbulence, then the high-Z impurities content and density peaking factor will reduce compared the previous high βP scenario to achieve more robust discharges and improve the plasma performance. In addition, the question of whether it is possible to access to high βP plasmas at low toroidal rotation will be validated. This experiment will provide important insight in the compatibility of the W which is the material of plasma facing components (divertor and wall) in ITER with density ITB in high βP scenario. It will also provide some effective and practical solutions, e.g. lower rotation and higher electron heating that should be required in the future fusion power plants, for high-Z impurities exhaust in high βP scenario with density ITB. These methods will be crucial to control high-Z impurities and achieve efficient, long-term fusion operation in future reactors. Additional scientific goals or piggy-back studies: Use early ECCD to form reversed q to reproduced high Ti and Ti gradient (high fusion performance with high ion temperature and high poloidal βP); Add KSTAR constraints to study the core high-Z impurities transport in high 훽푃 scenario.