Lower hybrid (LH) assisted plasma current ramp-up in ITER is demonstrated using a free-boundary full tokamak discharge simulator which combines the DINA-CH and CRONOS codes. LH applied from the initial phase of the plasma current ramp-up increases the safety margins in operating the superconducting poloidal field coils both by reducing resistive ohmic flux consumption and by providing non-inductively driven plasma current. Loss of vertical control associated with high plasma internal inductance is avoided by tailoring the plasma current density profiles. Effects of early LH application on the plasma shape evolution are identified by the free-boundary plasma simulation.
下部混合（LH）辅助等离子体电流爬升在ITER中的实现，通过结合DINA-CH和CRONOS代码的自由边界全托卡马克放电模拟器进行了演示。从等离子体电流爬升初始阶段施加LH，既通过减少电阻性欧姆磁通消耗，又通过提供非感应驱动电流，增加了超导极向场线圈运行的安全裕度。通过调整等离子体电流密度分布，避免了与高等离子体内部电感相关的垂直控制损失。通过自由边界等离子体模拟，识别了早期施加LH对等离子体形状演化的影响。