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Comparative studies of core and edge transport barrier dynamics of DIII-D and TFTR tokamak plasmas

机译:DIII-D和TFTR托卡马克等离子体核心和边缘传输势垒动力学的比较研究

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The plasma dynamics of enhanced confinement regimes in the TFTR core and the DIII-D core and edge are compared in order to identify a common physics basis. Despite differences in tran- sition timescale and location, as well as the sign of the radial electric field E., observations suggest that E × B shear effects on turbulence induced transport play a dominant role in governing bar- rier dynamics in all cases. Fast confinement bifurcations are observed in the TFTR core enhanced reverse shear (ERS) regime and in the edge DIII-D H mode. Both show spontaneous E_r shear layer formation prior to the confinement change and a negative E_r well that persists as steep gradients form. These dynamics differ from those of DIII-D negative central shear (NCS) plasmas. There, slow transitions are observed when the applied torque from unidirectional beam injection is small, while faster development and more dramatic confinement improvements occur at higher applied torques. Unlike the H mode and ERS cases, the NCS core generally has a positive E_r hill and no strong E_r shear precursor. However, similarity experiments performed on TFTR indicate that ERS, L mode and NCS-like regimes can all be accessed in a continuous fashion by varying the E × B shear through changes in the applied torque at constant power. As in the DIII-D NCS case, core confinement in TFTR reverse shear plasmas improves slowly as co-rotation begins to dominate the determination of E_r, no strong E_r shear layer develops prior to that improvement, and the plasma possesses a positive E_r hill. Reductions in transport with E_r gradients of either sign are consistent with the picture of E × B shear suppression and decorrelation of turbulence. At fixed input power, intermediate levels of confinement improvement are achieved by varying the E × B shear with changes in the applied neutral beam torque. The data suggest that control over the plasma pressure profile in a reactor may be possible if an external source of E × B shear, such as might be applied with RF techniques, is used to modify the shear which otherwise occurs.
机译:比较了TFTR核心,DIII-D核心和边缘中增强约束机制的等离子体动力学,以便确定通用的物理基础。尽管过渡时间尺度和位置以及径向电场E.的符号存在差异,但观察结果表明,在所有情况下,E×B剪切作用对湍流诱导的输运起着主导屏障动态的作用。在TFTR核心增强的反向剪切(ERS)方案和边缘DIII-D H模式下,观察到快速限制分叉。两者都显示出在约束变化之前自发的E_r剪切层的形成,以及负E_r井(以陡峭的梯度形式持续存在)。这些动力学不同于DIII-D负中央剪切(NCS)等离子体的动力学。在那里,当单向射束注入施加的扭矩较小时,观察到缓慢的过渡,而在较高的施加扭矩下,会出现更快的显影过程和更显着的密封性改善。与H模式和ERS情况不同,NCS岩心通常具有正E_r斜率且没有强E_r剪切前兆。但是,在TFTR上进行的相似性实验表明,通过以恒定功率改变施加的扭矩来改变E×B剪切,可以连续方式访问ERS,L模式和类似NCS的状态。与DIII-D NCS情况一样,由于同向旋转开始主导E_r的确定,因此TFTR反向剪切等离子体中的纤芯约束缓慢改善,在这种改善之前没有形成坚固的E_r剪切层,并且等离子体具有正E_r斜率。用任一符号的E_r梯度减少输运与E×B剪切抑制和湍流解相关的图一致。在固定输入功率下,通过随着施加的中性梁扭矩的变化而改变E×B剪切,可以实现中等程度的密闭性改善。数据表明,如果使用外部E×B剪切源(例如可能与RF技术一起使用)来修改剪切,否则可能会控制反应堆中的等离子体压力曲线。

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