Neutral beam (NI), ion cyclotron resonance (ICRH) and lower hybrid resonance (LHRH) heating on ASDEX are discussed with regard to their effect on plasma confinement. Comparison of NI and ICRH shows that the L and H-regimes are universal confinement modes of auxiliary-heated tokamak plasmas (i.e. independent of the heating method), and that the edge electron temperature (or a related parameter) dictates which mode prevails. In this connection it is noted that carbonization of the vessel walls impedes transition to the H-mode in the case of NI heating. Studies of energy confinement in the intermediate regime from ohmic to NI heating reveal a gradual transition from ohmic ( approximately ne) to neutral injection L-mode ( approximately I) scaling. At the same time a remarkable invariance of electron temperature profile shape with increasing heating power is observed. Changing the NI power deposition profiles from central to off-axis leaves gross energy confinement times unchanged while central confinement is substantially improved.
中性束（NI）、离子回旋共振加热（ICRH）和低杂波加热（LHRH）对ASDEX等离子体约束的影响已得到研究。NI与ICRH的比较表明，L模和H模是辅助加热托卡马克等离子体的普遍约束模式（即与加热方式无关），而边缘电子温度（或相关参数）决定了哪种模式占主导。在此背景下，注意到在NI加热情况下，器壁碳化会阻碍向H模的转变。对从欧姆加热到NI加热的中间区域能量约束的研究揭示了从欧姆定标（约正比于ne）到中性束注入L模定标（约正比于I）的逐渐过渡。同时观察到，随着加热功率增加，电子温度剖面形状保持显著不变。将NI功率沉积从中心改为离轴，总能量约束时间不变，而中心约束显著改善。