Evaluation of CFETR key parameters with different scenarios using system analysis code

Shi, Nan; Chan, V. S.; Wan, Yuanxi; Li, J.G.; Gao, Xiang; Ye, M.Y.

doi:10.1016/j.fusengdes.2016.07.017

Cited by 28 publications

(24 citation statements)

References 19 publications

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“…The electron density, electron temperature and Z eff is shown in Fig. 1 as a function of the square root of the normalized toroidal flux, q [21]. The main operating parameters are listed as: major radius R = 6.6 m, minor radius a = 1.8 m, toroidal magnetic field B T = 6 T, plasma current I p = 7.6 MA, plasma center electron density n e = 7.84 9 10 19 m -3 , deuterium ion density in plasma center n D = 3.27 9 10 19 m -3 , tritium ion density in plasma center n T = 3.27 9 10 19 m -3 , helium ion density in plasma center n He = 0.39 9 10 19 m -3 , inert gas n Ar = 0.0023 9 10 19 m -3 , center electron temperature in plasma center T e = 25.37 keV, center ion temperature in plasma center T i = 18.98 keV.…”

Section: Wave Frequencymentioning

confidence: 99%

Off-Axis Current Drive with Helicon Waves for CFETR

et al. 2020

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Off-axis current drive is necessary for Tokamak to maintain and regulate the current profile. Helicon wave is the high order harmonic fast wave and helicon wave current drive (HCD) is one of the key issues in the China Fusion Engineering Test Reactor (CFETR). The theory of HCD is briefly introduced and the simulation results are listed. Helicon waves can realize off-axis current drive under CFETR plasma parameters when the frequency is greater than 1 GHz and drive current is insensitive to the launched value of the parallel index of refraction n||, so wave accessibility issues can be reduced. Travelling Wave Antenna was analyzed by the commercial software package-CST. Near the resonant frequency of the antenna, the Voltage Standing Wave Ratio < 1.2 is obtained for the antenna in the bandwidth of 50 MHz, which means that the antenna does not require a matching system.

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Section: Wave Frequencymentioning

confidence: 99%

Off-Axis Current Drive with Helicon Waves for CFETR

et al. 2020

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“…In 2014-15, different 0-D system codes were employed to provide initial phases of design with relatively smaller size plasma and more conservative target of fusion power as a starting point [2,5]. Later, more advanced scenarios have been designed for more optimized parameters including plasma size, normalized beta, projected fusion power gain and bootstrap power drive fraction [6]. Besides 0-D calculation, 1.5D integrated modeling has been used to explore these scenarios as described in recent article [7].…”

Section: Cfetr Upgrade Phase-i Equilibriummentioning

confidence: 99%

MHD stability analysis of ideal wall modes for CFETR upgrade phase-I scenario using NIMROD

Cheng,

Zhu,

Banerjee

et al. 2017

Preprint

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Ideal MHD stability of China Fusion Engineering Test Reactor (CFETR) upgrade phase-I baseline scenario has been evaluated using the initial value code NIMROD. The toroidal mode numbers for n=1-30 have been considered for stability analysis both in single-fluid and two-fluid MHD models. Our calculation rusults show that all modes are found to be unstable with characteristics of edge-localized modes. For n ≤ 13 modes, two-fluid MHD model gives a slightly higher growth rates than single-fluid MHD model, while for n > 13 modes, this trend becomes opposite, which means two-fluid MHD model is needed for high-n mode analysis. In addition, n = 1 − 10 modes are found to be more unstable with increasing wall position and eventually their growth rates approach values in the no-wall limit.

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“…Besides being a partner in International Thermonuclear Experimental Reactor (ITER) [1], China has recently proposed to design and potentially build China Fusion Engineering Test Reactor (CFETR) [2]. The goal is to address the physics and engineering issues essential for bridging the gap between ITER and DEMO (DEMOnstration Power Station), including achieving tritium breeding ratio (TBR) > 1 and explor-ing options for DEMO blanket and divertor solutions [3][4][5]. During the past several years, significant progress has been made in CFETR conceptual physics and engineering design [6,5,7].…”

Section: Abstract Magnetic Fusion • Cfetr • Hfrc • Mhd Instability • Mhd Simulation 1 Introductionmentioning

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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Evaluation of CFETR key parameters with different scenarios using system analysis code

Cited by 28 publications

References 19 publications

Off-Axis Current Drive with Helicon Waves for CFETR

Off-Axis Current Drive with Helicon Waves for CFETR

MHD stability analysis of ideal wall modes for CFETR upgrade phase-I scenario using NIMROD

MHD analysis on the physical designs of CFETR and HFRC

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