托卡马克
磁流体驱动
自举电流
磁流体力学
安全系数
等离子体
机械
物理
大气压等离子体
BETA(编程语言)
电流(流体)
联轴节(管道)
剪切(地质)
横截面(物理)
撕裂
材料科学
热力学
核物理学
计算机科学
量子力学
复合材料
冶金
程序设计语言
作者
A. D. Turnbull,T. S. Taylor,M. S. Chu,R. Miller,Y. R. Lin‐Liu
出处
期刊:Nuclear Fusion
[IOP Publishing]
日期:1998-10-01
卷期号:38 (10): 1467-1486
被引量:84
标识
DOI:10.1088/0029-5515/38/10/305
摘要
Systematic stability studies of the negative central shear (NCS) configuration reveal a synergistic relationship between the gains in the ideal n = 1 magnetohydrodynamic (MHD) β limit from optimizing the profiles and from optimizing the shape. For a circular cross-section with highly peaked pressure profiles, βN = β/(I/aB) is limited to βN∼2% (mT/MA). Small to moderate improvements in βN result either from broadening the pressure or from strong cross-section shaping. At fixed safety factor the latter translates to a much larger increase in β and the root mean square β denoted as β*. With both optimal profiles and strong shaping, however, the gain in all the relevant fusion performance parameters is dramatic, and β and β* can be increased by a factor of 5. The calculations show that stabilization from a nearby conducting wall greatly contributes to this large improvement, since coupling of the plasma to the wall is increased for the optimum profiles and cross-section. Moreover, the alignment of the bootstrap current density profile with the total current density profile is also optimized with broad pressure, strong cross-section shaping and high βN, thus minimizing steady state current drive requirements. Sensitivity studies using other profiles show some variation in the actual β limits, but the general trends remain robustly invariant.
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