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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Edge plasma modelling for HT-7 superconducting tokamak experiments
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Edge plasma modelling for HT-7 superconducting tokamak experiments

机译:HT-7超导托卡马克实验的边缘等离子体建模

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摘要

HT-7 is a medium-sized superconducting tokamak with limiter and circular cross section configuration and it has become an important target for modelling of experimental plasmas. SOLPS5.0(B2.5) edge plasma transport code is used for modelling the experimental shots in order to match the code results to the experimental temperature and density profiles by varying the perpendicular particle transport coefficient D and heat conductivities chi(e), chi(i) in the code until good agreement between the code results and the measured data. For ohmic heated Deuterium plasma shot with toroidal magnetic field B-t = 1.98 T, plasma current I-p = 140 kA, ohmic heating power P = 180 kW, by matching the modelling results to the experimental profiles of electron density and temperature at the orthogonal plane, the perpendicular particle and heat transport coefficients D, chi(e) and chi(i) are obtained from the modelling results in the edge computation region with the assumption of chi(e) = chi(i). (c) 2007 Elsevier B.V. All rights reserved.
机译:HT-7是具有限制器和圆形横截面构造的中型超导托卡马克,已成为模拟实验血浆的重要目标。 SOLPS5.0(B2.5)边缘等离子体传输代码用于对实验镜头进行建模,以通过改变垂直粒子传输系数D和热导率chi(e),chi将代码结果与实验温度和密度分布进行匹配(i)在代码中,直到代码结果与测量数据之间达成良好协议为止。对于具有环形磁场Bt = 1.98 T的欧姆加热的氘等离子体发射,等离子体电流Ip = 140 kA,欧姆加热功率P = 180 kW,通过将建模结果与正交平面上的电子密度和温度的实验曲线进行匹配,垂直的粒子和热传递系数D,chi(e)和chi(i)是在chi(e)= chi(i)的假设下从边缘计算区域中的建模结果获得的。 (c)2007 Elsevier B.V.保留所有权利。

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