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L-H Transition Dynamics in ITER-Similar Plasmas with Applied n=3 Magnetic Perturbations

机译:L-H转换动力学在艾尔相似的等离子体中,应用n = 3磁性扰动

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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.
机译:在类似的形状(ISS)中,DIII-D中的低旋转等离子体[1]在DIII-D [ = 1.5-5×L0〜(19)M〜(-3),B_T = 1.9-2T,I_P = 1.5mA ,Q_(95)〜3.6,平衡中性光束注射(NBI)],LH阈值功率P_(LH)具有施加的n = 3共振磁性扰动(RMP)[2,3],以减少收缩性强烈增加。这是H模式接入主要是Ech-加热的迭代等离子体,因为可以在Iter中的L-H转换之前应用RMP来安全地抑制第一ELM。利用RMP的LH功率阈值增加通过初始通过应用平衡的NBI来通过应用平衡的NBI和高RMP字段中的ZH功率的增加来确定(通过DIII-D I-LIN系统施加在上方的六个内部线圈和下面的六个线圈)中增加舷外托卡马克中间平面[2])。然后移除NBI和EXH电源以使等离子体返回L模式。通过施加NBI并再次施加ech功率以获得第二L-H转换,并再次踩下exHow以获得阈值功率,没有应用RMP作为参考。使用该方法到括号P_(LH),然后通过在恒定光束处的I-C线圈电流(RMP扰动强度)下通过沿恒定光束和ECH功率踩下I-圈电流(RMP扰动强度)来获得P_(LH)与RMP扰动强度的扫描。 1。

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