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Access to sustained high-beta with internal transport barrier and negative central magnetic shear in DIII-D

机译:在DIII-D中获得具有内部传输屏障和负中心磁剪的持续高β值

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High values of normalized beta (beta(N)similar to 4) and safety factor (q(min)similar to 2) have been sustained simultaneously for similar to 2 s in DIII-D [J.L. Luxon, Nucl. Fusion 42, 64 (2002)], suggesting a possible path to high fusion performance, steady-state tokamak scenarios with a large fraction of bootstrap current. The combination of internal transport barrier and negative central magnetic shear at high beta results in high confinement (H-89P > 2.5) and large bootstrap current fraction (f(BS)> 60%) with good alignment. Previously, stability limits in plasmas with core transport barriers have been observed at moderate values of beta(N) (< 3) because of the pressure peaking which normally develops from improved core confinement. In recent DIII-D experiments, the internal transport barrier is clearly observed in the electron density and in the ion temperature and rotation profiles at rho similar to 0.5 but not in the electron temperature profile, which is very broad. The misalignment of T-i and T-e gradients may help to avoid a large local pressure gradient. Furthermore, at low internal inductance similar to 0.6, the current density gradients are close to the vessel and the ideal kink modes are strongly wall-coupled. Simultaneous feedback control of both external and internal sets of n=1 magnetic coils was used to maintain optimal error field correction and resistive wall mode stabilization, allowing operation above the free-boundary beta limit. Large particle orbits at high safety factor in the core help to broaden both the pressure and the beam-driven current profiles, favorable for steady-state operation. At plasma current flat top and beta similar to 5%, a noninductive current fraction of similar to 100% has been observed. Stability modeling shows the possibility for operation up to the ideal-wall limit at beta similar to 6%.
机译:在DIII-D中,标准化贝塔值(beta(N)近似于4)和安全系数(q(min)近似于2)的高值已同时持续了大约2 s。卢克森[Fusion 42,64(2002)],提出了通过大量自举电流实现高融合性能,稳态托卡马克方案的可能途径。内部输运势垒和高β处​​的负中心磁切变的结合导致高约束(H-89P> 2.5)和大自举电流分数(f(BS)> 60%),并具有良好的对准性。以前,由于压力峰值通常是由改善的岩心约束而产生的,因此在中等值的β(N)(<3)时已观察到具有岩心传输屏障的等离子体的稳定性极限。在最近的DIII-D实验中,在电子密度,离子温度和旋转曲线(rho近似于0.5)中清楚地观察到内部传输壁垒,但在电子温度曲线中却观察不到,这非常宽泛。 T-i和T-e梯度的未对准可能有助于避免较大的局部压力梯度。此外,在接近0.6的低内部电感时,电流密度梯度接近容器,并且理想的扭结模式与壁紧密耦合。使用对内部和外部n = 1个电磁线圈组的同时反馈控制来维持最佳的误差场校正和电阻壁模式稳定度,从而允许在自由边界beta极限以上运行。核心中具有高安全系数的大粒子轨道有助于扩大压力和电子束驱动的电流分布,有利于稳态运行。在等离子电流平顶和β接近5%的情况下,观察到的非感应电流分数接近100%。稳定性模型表明,有可能以高达6%的beta达到理想的墙极限。

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