Modeling of Ohmic Disruptive Discharge in J-TEXT Using the Tokamak Simulation Code

被引：3

作者：

Yang, Jinhong ^{[1
]}

Wang, Hui ^{[2
]}

Chu, Delin ^{[1
]}

Shi, Bo ^{[2
]}

Zhang, Qianghua ^{[2
]}

Qi, Junli ^{[2
]}

Zhang, Ming ^{[3
]}

Dong, Haijie ^{[4
]}

Deng, Haifei ^{[2
]}

Wang, Weihua ^{[1
]}

机构：

[1] Anhui Univ, Inst Phys Sci & Informat Technol, Hefei 230031, Anhui, Peoples R China

[2] PLA, Army Officer Acad, Inst Appl Phys, Hefei 230031, Anhui, Peoples R China

[3] Huazhong Univ Sci & Technol, Coll Elect & Elect Engn, Wuhan 430074, Hubei, Peoples R China

[4] Xi An Jiao Tong Univ, State Key Lab Strength & Vibrat Mech Struct, Xian 710049, Shaanxi, Peoples R China

来源：

IEEE TRANSACTIONS ON PLASMA SCIENCE | 2018年 / 46卷 / 06期

关键词：

Disruption; J-TEXT; Tokamak Simulation Code (TSC);

D O I：

10.1109/TPS.2018.2827927

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

A simulation of J-TEXT ohmic disruptive discharge has been achieved by using of the Tokamak Simulation Code (TSC) model. TSC is a numerical model of an axisymmetric free-boundary tokamak plasma and the associated control systems. The anomalous transport coefficient of disruption was adjusted according to heat transport across large magnetic island to mimic a sudden disruption. The simulation result of plasma current, electron temperature, loop voltage, and the disruption is compared with J-TEXT experimental disruptive discharge data. According to the simulation result, the dynamic response of one test plasma-facing module was calculated; the numerical results show that the maximum stress of the test module is in safety range.

引用

页码：2238 / 2241

页数：4

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