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Simulation of Radial Variation of Neutral Atoms on Edge Plasma of Small Size Divertor Tokamak

机译:小型分流器托卡马克边缘等离子体上中性原子径向变化的模拟

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Simulations have been performed to investigate the impact of radial variation of neutral atoms (neutral puff) on the edge plasma of small size divertor tokamak. It was demonstrated that, the variation of neutral atoms (neutral puff) in edge plasma of small size divertor tokamak generates additional large radial electric field and large radial electric field shear near separatrix which can significantly influence global confinement by affecting the transition from low (L) to high (H) confinement. This simulation was performed by using B2SOLPS0.5.2D fluid transport code based on a reduced form of the transport form of transport equations. These transport equations are implemented in B2SOLPS0.5.2D fluid transport code and solved for the parameters of Small Size Divertor tokamak. The results of simulation by fluid transport B2SOLPS0.5.2D code can be summarized as follow: 1) The Plasma Parameters are significantly effect by neutral atoms puffing in the edge plasma of small size divertor tokamak; 2) Contrary to previous expectation [1] of the predominant role of neutral viscosity on toroidal flux, anomalous transport was found to be mainly effect on toroidal flux; 3) Puffing of gas (neutral) in the edge plasma of small size divertor tokamak produce strong ITB; 4) Puffing of gas (neutral) in the edge plasma of small size divertor increase plasma density especially in SOL through charge exchange and ionization processes; 5) Puffing of gas (neutral) in the edge plasma of small size divertor has significant effect on the distribution of plasma heat flux; 6) The radial electric field is affected by gas (neutral) puffing in the edge plasma of small size divertor; 7) Puffing of neutral (atoms) in the edge plasma of small size divertor tokamak produce large radial electric field shear which contribute to L-H transition; 8) The centrifugal effect has no influence on distribution of the radial profile of parallel (toroidal) velocity of edge plasma of small size divertor tokamak during gas (neutral) puffing; 9) The bootstrap current in edge plasma of small size divertor tokamak is significantly affected by gas (neutral) puffing.
机译:已经进行了模拟以研究中性原子的径向变化(中性粉扑)对小尺寸偏滤器托卡马克边缘等离子体的影响。结果表明,小尺寸偏滤器托卡马克边缘等离子体中的中性原子(中性粉扑)的变化会在分离线附近产生额外的大径向电场和大径向电场剪切力,这会通过影响从低(L)的跃迁而显着影响整体约束)到高(H)限制。通过使用B2SOLPS0.5.2D流体传输代码(基于传输方程式的传输形式的简化形式)进行此模拟。这些传输方程在B2SOLPS0.5.2D流体传输代码中实现,并求解了小型分流器托卡马克的参数。通过B2SOLPS0.5.2D代码进行流体传输的模拟结果可总结如下:1)等离子体参数受到中性原子在小尺寸偏滤器托卡马克边缘等离子体中喷吹的显着影响; 2)与先前的预期[1]相反,中性粘度对环形磁通起主要作用,发现异常传输主要影响环形磁通; 3)在小型偏滤器托卡马克的边缘等离子体中吹气(中性)会产生很强的ITB; 4)小型分流器边缘等离子体中的气体(中性)吹气增加了等离子体密度,特别是在SOL中通过电荷交换和电离过程; 5)小型偏滤器边缘等离子体中的气体(中性)吹气对等离子体热通量的分布有显着影响; 6)径向电场受到小型偏滤器边缘等离子体中气体(中性)的膨胀的影响; 7)小型偏滤器托卡马克的边缘等离子体中的中性(原子)膨化产生大的径向电场剪切力,这有助于L-H跃迁; 8)离心作用对气体(中性)膨化过程中小尺寸偏滤器托卡马克边缘等离子体的平行(环形)速度的径向分布没有影响。 9)小尺寸偏滤器托卡马克边缘等离子体中的自举电流受气体(中性)膨化的影响很大。

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