Self-consistent modeling of CFETR baseline scenarios for steady-state operation

Chen, Jiale; Xiang, Jian; Chan, V. S.; Li, Zeyu; Deng, Zhao; Li, Guoqiang; Guo, Wenfeng; Shi, Nan; Chen, Xi; Team, Cfetr Physics

doi:10.1088/1361-6587/aa6d20

Cited by 62 publications

(64 citation statements)

References 54 publications

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“…However, while nonlocal effects could exist in certain regimes, such a strong and robust response of the plasma core being driven by nonlocal phenomena would mean that the fundamental assumptions of turbulent transport models would need to be revisited [14,15]. Such models, like TGLF [16] and QuaLiKiz [17], among others, are widely used to predict plasma performance and profiles in ITER and future reactors [18,19,20,21,22,23], and have been extensively validated against experiments [18,24,25,26,27]. Turbulent heat transport, as provided by these models, may be driven by plasma parameters other than temperature gradients, exhibit critical-gradient behavior and may be strongly nonlinear (e.g.…”

Section: Introductionmentioning

confidence: 99%

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

et al. 2019

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Cold pulses are introduced in Ohmic DIII-D tokamak plasmas, revealing for the first time in this machine a quick increase of core electron temperature shortly after the edge cold-pulse injection at low collisionality.The experimental results are consistent with predict-first simulations enabled by the Trapped Gyro-Landau-Fluid (TGLF) transport model. Measurements of electron density evolution during the cold-pulse propagation are enabled by a high time resolution density profile reflectometer. The density evolution reveals the quick propagation of a pulse from edge to core, which is a mechanism to transiently increase core temperature in low-collisionality plasmas. Local transport simulations with measured density evolution demonstrate that the core temperature response can indeed be explained by the stabilization of Trapped Electron Mode (TEM) turbulence at low collisionality, thus providing confidence that local transport modeling is enough to explain cold-pulse propagation and associated phenomenology.

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Section: Introductionmentioning

confidence: 99%

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

et al. 2019

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“…To achieve the mission goal of fusion power production of 1GW , the self-consistent steady-state scenarios for CFETR with fully sustained non-inductive current drive and as well hybrid mode scenarios are developed using a multi-dimensional code suite with physics-based models as shown in [15,16]. The equilibrium profiles for the steady-state and hybrid scenarios presented in Figs.…”

Section: Steady-state Scenarios and Hybrid Scenarios For Cfetrmentioning

confidence: 99%

MHD analysis on the physical designs of CFETR and HFRC

Zhu

Li²,

Fang³

et al. 2021

Preprint

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The China Fusion Engineering Test Reactor (CFETR) and the Huazhong Field Reversed Configuration (HFRC), currently both under intensive physical and engineering designs in China, are the two major projects representative of the lowdensity steady-state and high-density pulsed pathways to fusion. One of the primary tasks of the physics designs for both CFETR and HFRC is the assessment and analysis of the magnetohydrodynamic (MHD) stability of the proposed design schemes. Comprehensive efforts on the assessment of MHD stability of CFETR and HFRC baseline scenarios have led to preliminary progresses that may further benefit engineering designs. For CFETR, the ECCD power and current for full stabilization on NTM have been predicted in this work, as well as the corresponding controlled magnetic island width. A thorough investigation on RWM stability for CFETR is performed. For 80% of the steady state operation scenarios, active control methods may be required for RWM stabilization. The process of disruption mitigation with massive neon injection on CFETR is simulated. The time scale of and consequences of plasma disruption on CFETR are estimated, which are found equivalent to ITER. Major MHD instabilities such as NTM and RWM remain challenge to steady state tokamak operation. On this basis, next steps on CFETR MHD study are planned on NTM, RWM, and SPI disruption mitigation. For HFRC, plasma heating due to 2D adiabatic compression has been demonstrated in NIMROD simulations. The tilt and rotational instabilities grow on ideal MHD time scale in single fluid MHD model as shown from NIMROD calculations. Two-fluid MHD calculations using NIMROD find FLR stabilizing effects on both tilt and rotational modes. Energetic-particle stabilization of tilt mode was previously demonstrated in C-2 experiments and NIMROD simulations. With stabilization on major MHD instabilities from two-fluid and energetic particle effects, FRC may promise to be an alternative route to compact magnetic fusion ignition. To explore such a potential, we plan on further perform analyses of the MHD instabilities in HFRC during magnetic compression process.

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“…此外, CFETR装置的相关不稳定性的预研是其投入建设的重要基础, 为了通过先进运行模式实现其最终的目标, 首先基于装置的基准运行模式预研阿尔芬本征模的相关不稳定性, 并且在该装置上已有TAE, RSAE及BAE的相关理论研究工作 [31,32] . 现阶段, CFETR装置的基准稳态运行模式有三个参考方案 [33,34] , 分别由中性束注入(Neutral [35,36] , 本文…”

Section: 引言unclassified

“…等离子体密度和温度剖面密切相关, 外部驱动的电流和自举电流一起决定了安全因子q剖面 [34] , 并且等离子体压强梯度参量α又与自举电流相关 [21] , 下面探究 αTAE与电流密度剖面之间的关联.…”

Section: 在完全非感应电流稳态运行条件下电流密度剖面与unclassified

Discrete Alfvén eigenmodes excited by energetic particles in China Fusion Engineering Test Reactor

Zhao¹,

Hu²,

He³

et al. 2020

Sci. Sin.-Phys. Mech. Astron.

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In burning plasmas, discrete Alfvén eigenmodes (αTAEs, where α denotes a parameter of plasma pressure gradient) can be readily destabilized by energetic particles under the wave-particle resonance condition. In this study, we theoretically analyze the physical features of αTAEs in the China Fusion Engineering Test Reactor (CFETR), which is viewed as the next generation device in the Chinese magnetic confinement fusion program. One of the scientific objectives of the device is to achieve steady-state operation. There are three reference schemes for baseline steady-state operation, namely Case 1: NB+EC, Case 2: NB+EC+LH, and Case 3: EC+LH, where NB, EC, and LH represent neutral beam, electron cyclotron wave, and lower hybrid wave, respectively. Within the ideal magnetohydrodynamic (MHD) description, we focus on the physical characteristics of αTAEs and correlation between the radial profile of total current density and αTAEs for the three scenarios of CFETR operation with the help of a MHD eigenvalue code. The numerical results indicated that multiple branches of αTAEs can be trapped in potential wells of the ballooning drive under the CFETR operation condition. In the inner region, the bootstrap current density is large, and the total current density profile, defined by the peak of the radial profile of total plasma current density is relatively flat. Therefore, there are abundant αTAEs in this region. However, in the outer region, the bootstrap current is relatively small, and the total current density decreases gradually. So, αTAEs are hardly seen in this region. The αTAEs in the inner region are quasi-marginally stable within the ideal MHD description. In the CFETR operations, the energetic particles generated can destablize the MHD αTAEs under the wave-particle resonance conditions. We study the stability features of αTAEs interacting with energetic particles by employing linear gyrokinetic-MHD hybrid eigenvalue codes. The multiple branches of αTAEs are excited under the various resonance conditions. Moreover, the multiple branches of αTAEs can also be excited by energetic particles with virial energy. Furthermore, higher-frequency αTAEs may be destabilized by energetic particles with higher energy. These αTAEs could change the distribution of energetic particles in phase space and cause the loss of a large number of particles, which may affect the plasma confinement.

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Self-consistent modeling of CFETR baseline scenarios for steady-state operation

Cited by 62 publications

References 54 publications

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

MHD analysis on the physical designs of CFETR and HFRC

Discrete Alfvén eigenmodes excited by energetic particles in China Fusion Engineering Test Reactor

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Self-consistent modeling of CFETR baseline scenarios for steady-state operation

Cited by 62 publications

References 54 publications

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak

MHD analysis on the physical designs of CFETR and HFRC

Discrete Alfv&eacute;n eigenmodes excited by energetic particles in China Fusion Engineering Test Reactor

Contact Info

Product

Resources

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Discrete Alfvén eigenmodes excited by energetic particles in China Fusion Engineering Test Reactor