Instabilities of ideal magnetohydrodynamics mode and neoclassical tearing mode stabilization by electron cyclotron current drive for EHL-2 spherical torus

被引：0

作者：

Dong, Lili ^{[1
,2
]}

Li, Li ^{[3
]}

Liu, Wenjun

Liu, Tong ^{[4
]}

Liang, Yunfeng ^{[1
,5
]}

Dong, Jiaqi ^{[1
,2
,6
]}

Xie, Huasheng

Shi, Yuejiang ^{[1
,2
]}

机构：

[1] Hebei Key Lab Compact Fus, Langfang 065001, Peoples R China

[2] ENN Sci & Technol Dev Co Ltd, Langfang 065001, Peoples R China

[3] Donghua Univ, Coll Sci, Shanghai 201620, Peoples R China

[4] Dalian Univ Technol, Sch Phys, Key Lab Mat Modificat Laser Ion & Electron Beams, Minist Educ, Dalian 116024, Peoples R China

[5] Forschungszentrum Julich, Inst Fus Energy & Nucl Waste Management Plasma Phy, Partner Trilateral Euregio Cluster TEC, Julich, Germany

[6] Southwestern Inst Phys, Chengdu 610041, Peoples R China

来源：

PLASMA SCIENCE & TECHNOLOGY | 2025年 / 27卷 / 02期

关键词：

MHD; magnetic fusion; macro-instability; COMPLETE SUPPRESSION; MAGNETIC ISLANDS; MHD-LIMITS; PLASMA; FREQUENCY; TOKAMAKS;

D O I：

10.1088/2058-6272/ada421

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：

The next generation fusion device listed on ENN's fusion roadmap, named as (ENN He-Long) EHL-2, is under both physics and engineering designs. The instabilities of ideal magnetohydrodynamics (MHD) mode and neoclassical tearing mode (NTM) stabilized by electron cyclotron current drive (ECCD) for EHL-2's two typical operation scenarios are analyzed. For high-ion-temperature operating (HITO) scenario, the vertical displacement event (VDE) could be a big challenge to the device safety. For the steady-state operating (SSO) scenario, the limitation may rise from the ideal MHD mode, NTM, etc. This suggests that the MHD analysis of both operation scenarios should be done with different focusing. Preliminary analysis based on the current physics and engineering design of both two scenarios is given in this paper. Based on the analysis result of above, the future assessments might target at active control method and the effect of boron on MHD activities.

引用

页数：11

共 44 条

[1] Resistive Wall Mode Instability at Intermediate Plasma Rotation [J].

Berkery, J. W. ;

Sabbagh, S. A. ;

Betti, R. ;

Hu, B. ;

Bell, R. E. ;

Gerhardt, S. P. ;

Manickam, J. ;

Tritz, K. .

PHYSICAL REVIEW LETTERS, 2010, 104 (03)

[2] STABILIZATION OF EXTERNAL-MODES IN TOKAMAKS BY RESISTIVE WALLS AND PLASMA ROTATION [J].

BONDESON, A ;

WARD, DJ .

PHYSICAL REVIEW LETTERS, 1994, 72 (17) :2709-2712

[3] High beta plasmas and internal barrier dynamics in JET discharges with optimized shear [J].

Buratti, P .

NUCLEAR FUSION, 2001, 41 (12) :1809-1814

[4] Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes [J].

Chan, V. S. ;

Costley, A. E. ;

Wan, B. N. ;

Garofalo, A. M. ;

Leuer, J. A. .

NUCLEAR FUSION, 2015, 55 (02)

[5] Survey of disruption causes at JET [J].

de Vries, P. C. ;

Johnson, M. F. ;

Alper, B. ;

Buratti, P. ;

Hender, T. C. ;

Koslowski, H. R. ;

Riccardo, V. .

NUCLEAR FUSION, 2011, 51 (05)

[6] CONFINING A TOKAMAK PLASMA WITH RF-DRIVEN CURRENTS [J].

FISCH, NJ .

PHYSICAL REVIEW LETTERS, 1978, 41 (13) :873-876

[7] Complete suppression of neoclassical tearing modes with current drive at the electron-cyclotron-resonance frequency in ASDEX upgrade tokamak [J].

Gantenbein, G ;

Zohm, H ;

Giruzzi, G ;

Günter, S ;

Leuterer, F ;

Maraschek, M ;

Meskat, J ;

Yu, Q .

PHYSICAL REVIEW LETTERS, 2000, 85 (06) :1242-1245

[8]

Gu X, 2025, Plasma Sci. Technol., DOI [10.1088/2058-6272/adae72, DOI 10.1088/2058-6272/ADAE72]

[9]

Helzl, 2012, J. Phys. Conf. Ser, V401, P012010, DOI [10.1088/1742-6596/401/1/012010, DOI 10.1088/1742-6596/401/1/012010]

[10] Linear and nonlinear effect of sheared plasma flow on resistive tearing modes [J].

Hu, Qiming ;

Yu, Q. ;

Hu, Xiwei .

PHYSICS OF PLASMAS, 2014, 21 (12)

← 1 2 3 4 5 →