In ITER-similar shape (ISS), low rotation plasmas [1] in DIII-D [=1.5-5×l0~(19)m~(-3), B_t=1.9-2T, I_p=1.5MA, q_(95)~3.6, balanced neutral beam injection (NBI)], the L-H threshold power P_(LH) with applied n=3 Resonant Magnetic Perturbations (RMP) [2,3] is found to increase strongly with decreasing collisionality. This is a concern for H-mode access in primarily ECH-heated ITER plasmas since RMP may be applied before the L-H transition in ITER to safely suppress the first ELM. The L-H power threshold increase with RMP is determined by initially accessing H-mode via applying balanced NBI and increasing steps in ECH power at high RMP field (applied via the DIII-D I-coil system consisting of six internal coils above and six coils below the outboard tokamak midplane [2]). NBI and ECH power are then removed to let the plasma return to L-mode. A second L-H transition is induced later in the same shot by applying NBI and stepping up ECH power again to obtain the threshold power with no applied RMP as a reference. Using this method to bracket P_(LH), a scan of P_(LH) vs. RMP perturbation strength is then obtained via stepping down the I-coil current (RMP perturbation strength) at constant beam and ECH power, as shown in Fig. 1.
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机译:用等离子体约束实现重力场的动态控制热核聚变(TLTS)方法,通过热辐射等离子体绝缘的壁反应堆防止中子辐射并节省磁场和等离子体的混合,使用旋转磁场的异步磁惯性约束反应堆(AMITYAR和HFM)为实施该方法,在该反应器中点燃热核反应的方法,爆炸式等离子发生器(VIP)的实施方法,以及具有HFM的特立普安瓿,以实现D + T反应和具有超高温热度的HFM D +3НЕ和1Н+11В的高温反应