Modeling and measurement of energetic particle slowing down in Wendelstein 7-X

被引：24

作者：

Lazerson, Samuel A. ^{[1
]}

Pfefferle, David ^{[2
]}

Drevlak, Michael ^{[1
]}

Smith, Hakan ^{[1
]}

Geiger, Joachim ^{[1
]}

Akaslompolo, Simppa ^{[3
]}

Xanthopoulos, Pavlos ^{[1
]}

Dinklage, Andreas ^{[1
]}

Ford, Oliver ^{[1
]}

McNeely, Paul ^{[1
]}

Rust, Norbert ^{[1
]}

Bozhenkov, Sergey ^{[1
]}

Hartmann, Dirk ^{[1
]}

Rahbarnia, Kian ^{[1
]}

Andreeva, Tamara ^{[1
]}

Schilling, Jonathan ^{[1
]}

Brandt, Christian ^{[1
]}

Neuner, Ulrich ^{[1
]}

Thomsen, Henning ^{[1
]}

Wolf, Robert C. ^{[1
]}

机构：

[1] Max Planck Inst Plasma Phys, D-17491 Greifswald, Germany

[2] Univ Western Australia, Crawley 6009, Australia

[3] Aalto Univ, Espoo 02150, Finland

来源：

NUCLEAR FUSION | 2021年 / 61卷 / 09期

关键词：

stellarator; simulation; validation; energetic particles; NBI; heating; current drive; BOOTSTRAP CURRENT;

D O I：

10.1088/1741-4326/ac0771

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 energetic particle slowing down model in the BEAMS3D stellarator neutral beam code is compared to analytic models and experimental data from the Wendelstein 7-X experiment (W7-X). Recently, the first neutral beam experiments were performed in W7-X, providing validation of neutral beam deposition codes (Lazerson S.A. et al 2020 Nucl. Fusion 60 076020). This work builds upon that work, and follows the gyro-center orbits of the neutral-beam-generated fast ions to the plasma boundary. Slowing down times based on measurements of diamagnetic energy changes are compared to simulation data. A discharge solely heated by neutral beam injection is used to compare neoclassical heat flux estimates to neutral beam fueling, heating, and current drive. Experimental estimates of electron heat diffusivity suggest that electron turbulence is destabilized by density peaking in the discharge. Neutral beam current drive dominates over bootstrap current, resulting in a reversal of the toroidal current, as seen experimentally. Particle losses and heat flux through the equilibrium boundary are described. The effects of the magnetic configuration and plasma density on such parameters are also assessed. Benchmarking based on analytic estimates and other energetic particle codes is presented.

引用

页数：16

共 27 条

[21] W7-X neutral-beam-injection: Selection of the NBI source positions for experiment start-up [J].

Rust, Norbert ;

Heinemann, Bernd ;

Mendelevitch, Boris ;

Peacock, Alan ;

Smirnow, Michael .

FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) :728-731

[22] Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime [J].

Sauter, O ;

Angioni, C ;

Lin-Liu, YR .

PHYSICS OF PLASMAS, 1999, 6 (07) :2834-2839

[23]

Stagner Luke, 2020, Zenodo

[24] VARIATIONAL BOUNDS FOR TRANSPORT-COEFFICIENTS IN 3-DIMENSIONAL TOROIDAL PLASMAS [J].

VANRIJ, WI ;

HIRSHMAN, SP .

PHYSICS OF FLUIDS B-PLASMA PHYSICS, 1989, 1 (03) :563-569

[25]

Varje J., 2019, ARXIV190802482

[26] A geometry interface for gyrokinetic microturbulence investigations in toroidal configurations [J].

Xanthopoulos, P. ;

Cooper, W. A. ;

Jenko, F. ;

Turkin, Yu. ;

Runov, A. ;

Geiger, J. .

PHYSICS OF PLASMAS, 2009, 16 (08)

[27]

Zarnstorff M.C., 2004, 20 IAEA FUSION ENERG

← 1 2 3 →