Plasma transport simulation modelling for helical confinement systems
Plasma transport simulation modelling for helical confinement systems
复制标题
螺旋约束系统的等离子体传输仿真建模
DOI：
10.1088/0029-5515/32/4/i08
复制
发表时间：
1991
期刊：
影响因子：
3.3
通讯作者：
T. Amano
中科院分区：
文献类型：
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作者：
K. Yamazaki;T. Amano
为了详细预测大型螺旋器件(LHD)中的等离子体参数，进行了包括经验波湍流模型和漂移波湍流模型在内的三维平衡/一维输运模拟，结果表明LHD的整体约束时间主要由等离子体边缘区域的电子反常输运决定，而不是由核心区的螺旋波纹输运决定。即使可以消除涟漪损失，全球禁闭的增加也是10%。但是，中心离子温度上升了20%以上。如果反常损耗可以减少到当前定标中所用值的一半，就像托卡马克放电的H模一样，即使在等离子体核中，通过离子通道的新经典波纹损耗也变得重要起来。等离子体柱相对于主半径径向内移5%，通过减少新经典非对称离子输运损失和增大等离子体半径(10%)，改善了等离子体的约束，使聚变产物增加了50%以上。
For a detailed prediction of the plasma parameters in the Large Helical Device (LHD), 3-D equilibrium/1-D transport simulations including empirical or drift wave turbulence models are performed which suggest that the global confinement time of the LHD is determined mainly by the electron anomalous transport in the plasma edge region rather than by the helical ripple transport in the core region. Even if the ripple loss can be eliminated, the increase in global confinement is 10%. However, the rise in the central ion temperature is more than 20%. If the anomalous loss can be reduced to half of the value used in the present scaling, as is the case in the H-mode of tokamak discharges, the neoclassical ripple loss through the ion channel becomes important even in the plasma core. The 5% radial inward shift of the plasma column with respect to the major radius improves the plasma confinement and increases the fusion product by more than 50% by reducing the neoclassical asymmetric ion transport loss and increasing the plasma radius (10%)
影响因子：
3.3
作者：
A. Gibson;T. Sekiguchi;K. Lackner;S. Bodner;R. Hancox
通讯作者：
A. Gibson;T. Sekiguchi;K. Lackner;S. Bodner;R. Hancox
安.职业.Hyg.28-2。
DOI：
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