Processing math: 100%
Advanced Search+
Lingke MOU, Zhongyong CHEN, Wei YAN, You LI, Weikang ZHANG, Jiangang FANG, Yingzhou JIANG, Xiaobo ZHANG, Yu ZHONG, Feng LI, Guinan ZOU, Fanxi LIU, Zhipeng CHEN, Zhoujun YANG, Nengchao WANG, Yonghua DING, Yuan PAN, J-TEXT Team. Suppression of runaway current by electrode biasing and limiter biasing on J-TEXT[J]. Plasma Science and Technology, 2022, 24(12): 124001. DOI: 10.1088/2058-6272/ac85a2
Citation: Lingke MOU, Zhongyong CHEN, Wei YAN, You LI, Weikang ZHANG, Jiangang FANG, Yingzhou JIANG, Xiaobo ZHANG, Yu ZHONG, Feng LI, Guinan ZOU, Fanxi LIU, Zhipeng CHEN, Zhoujun YANG, Nengchao WANG, Yonghua DING, Yuan PAN, J-TEXT Team. Suppression of runaway current by electrode biasing and limiter biasing on J-TEXT[J]. Plasma Science and Technology, 2022, 24(12): 124001. DOI: 10.1088/2058-6272/ac85a2

Suppression of runaway current by electrode biasing and limiter biasing on J-TEXT

More Information
  • Corresponding author:

    Zhongyong CHEN, E-mail: zychen@hust.edu.cn

  • 1 See the author list of Liang et al 2019 Overview of the Recent Experimental Research on the J-TEXT Tokamak, Nucl. Fusion 59 112016.

  • Received Date: April 15, 2022
  • Revised Date: July 19, 2022
  • Accepted Date: July 28, 2022
  • Available Online: December 05, 2023
  • Published Date: October 11, 2022
  • The avoidance of runaway electrons (REs) generated during plasma disruption is of great concern for the safe operation of tokamak devices. Experimental study on the suppression of runaway current by electrode biasing (EB) and limiter biasing (LB) has been performed on the J-TEXT tokamak, which could be an alternative way to suppress the runaway current. The experimental results show that the higher the voltage value, the smaller the runaway current in both EB and LB experiments. The runaway current can be completely suppressed at an electrode biased voltage of +450 V and a limiter biased voltage of +300 V. The comparison of the energy spectra during the runaway plateau phase shows that the maximum energy max (ERE) and radiation temperature THXR of hard x-rays (HXRs) are significantly reduced after the application of +200 V limiter biased voltage. The electric field generated by the biased voltage may be the key factor to suppress the runaway current, and the measured radial electric field increases obviously after the voltage is applied. This may result in an increase in the loss of REs to realize the suppression of runaway current.

  • Coaxial plasma guns (CPG) are the ion sources in the plasma opening switches that generate the plasma using the insulator’s surface breakdown. These CPGs come under the erosional type of plasma generators in which material enters the regime of ionization and acceleration, resulting in the evaporation of insulators [1, 2] or electrode material [3, 4]. These CPGs have the advantage of obtaining high-energy plasmas eliminating the pulsed gas vents that require the accurate operation of electromagnetic valves involved in gas supply lines [5] and laser-produced plasma systems [6] without compromising the requirements of plasma source parameters. The requirements include (i) minimization of background plasma perturbations, (ii) reduction in the interference due to high voltage breakdown on insulators, (iii) plasma cloud formation in the background plasma for the reproduction of space conditions [2], (iv) reproducibility, i.e., production of same plasma parameters for the shot to shot and (v) long life span to be used for laboratory experiments and in many applications. The insulators used in CPGs include polyethylene [2], plexiglas [7], etc. The CPGs that meet the above requirements and are simple in construction are usually made of coaxial cables with an insulator as low-density polyethylene (LDPE) and provide high-voltage insulation between the electrodes. In this work, the CPG is made using RG-218 coaxial cable with polyethylene (PE) insulation.

    Figure 1(a) shows the electrical schematic of experimental setup of the capacitor discharge circuit for firing the plasma gun, and figure 1(b) shows the schematic of the plasma gun used in experiments. The electrical circuit consists of a capacitor 1 μF, 25 kV, a triggered spark gap (SG) switch [8, 9], and a resistance of 20 kΩ parallel to the CPG. The coaxial cable has an inner copper conductor with a diameter of 4.95 mm, a PE insulator thickness of 6.16 mm, and the gun nozzle used is 120° opening angle. The acceleration gap between the inner conductor and outer CPG nozzle is 7.5 mm. The plasma is ejected and accelerated with the self-generated Lorentz force, i.e., J×B force from the electrodes, where J is the current density, and B is the magnetic field produced due to the current. The experiments are carried out in vacuum chamber evacuated to 4×104 mbar. The plasma chamber used in the experiments has diameter of 250 mm and height 220 mm. The parameters that are more important for the characterization of CPGs are plasma density (ni), temperature (Te), and plasma velocity. These parameters are measured using the triple Langmuir probe and Faraday cup methods discussed in sections 3 and 4, respectively.

    Figure  1.  (a) Schematic of firing circuit. (b) CPG (not to the scale).

    For the characterization of a plasma gun, a triple Langmuir probe (TLP) was used against the plasma source for measuring plasma density (ni) and temperature (Te). This measurement method directly exhibits the plasma parameters using the microsecond intrinsic response time of the probe and avoids the difficulties of obtaining the I-V curve by the fast sweeping of bias voltage. The probe electrodes have different profiles, including cylindrical, spherical, and planar [10]. Using various combinations of electrode profiles for probe design gives the asymmetric arrangement [11, 12], and using of same electrode profiles gives the symmetric arrangement [13]. In the present experimental study, the probe is designed with cylindrical electrodes with a symmetric arrangement. A cylindrical probe is a piece of wire that should have a high melting point and mechanical strength. The materials reported in the literature for probe design are tantalum, molybdenum, graphite, and tungsten [14]. In the symmetric arrangement, the two adjacent probes are negatively DC-biased, and the third probe is in floating mode. The voltage signal across the biased probes is proportional to the density (ni), and the voltage signal between the high potential probe and the floating probe is proportional to the temperature (Te). The ion saturation current (Is) is obtained for the strong negatively biased potential that gives ion density (ni), and the potential in which the current drawn is zero, known as floating potential and indicates the electron temperature (Te). Depending on the electrical circuit connections, the TLP can be operated in (i) current and (ii) voltage mode [15]. The voltage mode TLP requires two DC power supplies, and the current mode TLP requires a single DC power supply, reducing the complexity of biasing the circuit and directly displaying the Te and ni. The theoretical considerations of the Langmuir probe are: (i) the plasma is in Maxwellian distribution, (ii) the probe dimension (r) is much larger than Debye length (λd), and (iii) the surface area of the probe must be small to minimize the perturbations due to plasma [1618].

    Figure 2(a) shows the electrical circuit of the current mode operation of TLP, which is used in the present experimental work. The plasma from the CPG hits the TLP in which two probe tips are biased at some potential. The potential attracts the unlike charges and repels the like-charged particles. These particles form a thin sheath on the surface of the probe tips. As per the theoretical considerations of the Langmuir probe, rλd defines the surface area of the probe exposed to plasma as the measuring area of the probe. When the charge particles are collected on the probe, the current flows through the circuit, and the ion current density is assumed to remain constant at all probe potentials; using the following equation, one may determine the plasma temperature [19, 20] as

    Figure  2.  (a) Electrical schematic of TLP, and (b) experimental setup of the biasing circuit (left) and probe installed in a vacuum chamber (right).
    kTe=eV32ln(2), (1)

    where kTe is the electron temperature in eV, e is the charge of an electron, and V32 is the voltage measured between positively biased probe T2 and floating probe T3. The temperature measurement is independent of the type of ions in the plasma. The bias voltage across the probes T1 and T2 must be sufficiently high so that more ions are collected at the probe to get the ion saturation current such that kTeeV12 [21] is satisfied. Using the values of Is=V12R (R is the resistance connected between probes T1 and T2) and kTe, the plasma density can be estimated using the equation [16, 19]

    ni=exp(0.5)(mikTe)0.5IseAp, (2)

    where mi is the mass of the ion and Ap=2πrl is the surface area of the tungsten probe exposed to plasma, r and l are the radius and length of the tungsten probe.

    The TLP was designed in-house using three pieces of 480 μm diameter tungsten wire and a length of 10 mm exposure to plasma. These are connected to Teflon wires on other sides for signal collection and biasing the TLP. The tungsten wires are made rigid inside the Teflon rod of 20 mm diameter and length of 35 mm with 2.8 mm spacing between them. The whole assembly of TLP is passed through a plastic pipe and shielded with metal foil till the Teflon wires are connected to the three BNC feed-throughs inside the vacuum chamber. The RG58 coaxial cables connect the biasing circuit and the TLP. The biasing circuit used in the experiments is a capacitor-based circuit. The electrical schematic circuit of TLP is shown in figure 2(a), and the experimental setup is shown in figure 2(b). The capacitance C is 1 mF, 140 V rated charged using the stabilized power supply, and the circuit’s series resistance, R, is 0.38 Ω. Electromagnetic noises during the discharge are more likely to affect these circuits, so the biasing circuit is covered with aluminium foil and is installed in a metal box. When the TLP is unbiased, there will be no current flowing in the biased path, and when the TLP is biased, probe T2 will have a potential less than T3, and due to the flow of ions, the current Is passes through the resistor R. The potential drop across R is measured using the oscilloscope with which the Is can be calculated. During the measurements, the oscilloscope is isolated from the metal box such that high voltage ground is isolated from the oscilloscope.

    Faraday cups (FCs) are charge collector devices that collect the charged particles in a vacuum and are used to give the time histories of the particles when kept against the plasma source. Optimized design of FC is a challenging task for specific applications, even if it is simple in construction and a reliable technique for measuring beam current and the plasma density of the source [22, 23]. Different types of FC designs are reported in the literature depending on the application [24, 25]. Care must be taken in designing the FC because the back-scattered and secondary emission electrons (SEE) are emitted from the surface of the collector when the charged particles impact electrodes, and these secondary electrons may escape from the FC aperture for high-energy plasma sources. The escape of electrons results in the underestimation of beam current for negative ions or electrons and the overestimation of beam current for positively charged particles [22]. The reduction in the loss probability of secondary capture electrons is made by optimizing the dimensions of FC and using low Z material can be considered while designing the FC [26, 27]. The schematic of the electrical circuit of FC is shown in figure 3. The ion density using FC can be estimated by equation

    Figure  3.  Electrical circuit of biasing circuit of FC.
    niFC=IFCAFCviZe, (3)

    where IFC=VFCRt is the current flowing through terminating resistance Rt, VFC is the voltage measured by oscilloscope across Rt, AFC is the input hole area, vi is the velocity of ions obtained using plasma transit times, Z is the charge state of respective ion and e is charge of the electron.

    The Faraday cup consists of two electrodes arranged concentrically and isolated electrically by a Kepton insulator, shown in figure 3. The inner electrode (collector) is 4.8 mm in diameter, the insulator is 0.1 mm thick, and the metal casing is 20 mm in diameter and 25 mm in length. The electrodes are made of brass. The collector is negatively biased using a capacitor-based circuit through 5 MΩ resistance and the capacitor (C) is charged using stabilized power supply. Geometrically low aperture-to-length ratio, i.e., the deep cup-shaped electrode arrangement, minimizes the loss of secondary electrons emitted from the collector when ions impact the inner electrode.

    To assess the performance of the FC, numerical simulations have been performed using CST Particle Studio. The 3D CST model of the FC is shown in figure 4. The loss probability using the SE emission model is simulated. When FC is negatively biased, the potential is maximum at the surface of the metal casing and has the minimum value at the center along the axis of the beam. To know the loss probability of SE electrons, particle tracking simulations were run at different energies and by sweeping the voltage from 0 to 250 V. The collector surface is selected as the circular source. The emitted electrons are taken as Nemit = 10200 for every simulation run and emission energy Ee. From the aperture, some of the electrons are diverted to the collector due to the presence of an electric field called captured electrons Ncap, and the remaining electrons have high energy to overcome the potential barrier, which escapes from the aperture, and these electrons are denoted by Nescp = NemitNcap. The loss probability of SEE is given by the equation (4)

    Figure  4.  3D CST model of FC.
    γ=NescpNemit. (4)

    The trajectories of electrons are shown in figure 5(a), and the loss probability of electrons as a function of Ee and bias voltage (Vbias) as γ(Ee,Vbias) is shown in figure 5(b). These simulations show the points from where the electron escape is maximum, and the electron trajectories can be determined. The parameter by which the performance of FC can be decided is the minimum energy Emin that the electron can escape from the aperture. Considering the columbic interaction, the SEE electrons have maximum energy given by equation [28]

    Figure  5.  (a) SEE trajectories at 10 eV, (b) loss probability of SEEs.
    Emax=4memi(me+mi)2Eioncos2ϕ, (5)

    where me and mi are the mass of the electron and the ion, respectively, Eion is the energy of the ion, and ϕ is the angle between incident ions and trajectory of ejected electrons. From equation (5), if the ions incident on the collector and the emitted electrons that are moving with an angle, ϕ = 180°, i.e., opposite to ions, then these electrons may have the maximum energy, and their velocity is entirely in the axial direction. Only these electrons have maximum chances to escape from an aperture that has energy Emin.

    Figure 1(a) shows the CPG firing circuit, and the voltage applied across the insulator produces the plasma, which initiates the temperature and density of the plasma. The vacuum chamber is evacuated to a pressure of 4×104 mbar. The capacitor 1 μF is charged to 17 kV and discharged through a spark-gap switch that ejects plasma through CPG. The ionization of the insulator surface, creation of ions and electrons, henceforth temperature and density depend on the discharge voltage pulse. The discharge current is monitored using the current monitor shown in figure 6(a), which has a peak current of 8 kA with a quarter cycle time period of 2 μs.

    Figure  6.  Experimental waveforms. (a) CPG discharge current, (b) ion density signals using TLP and FC, and (c) temperature measured using TLP at a distance of 50 mm.

    The ion saturation signals are measured using the biasing circuits of TLP and FC shown in figures 2(a) and 3, respectively. The bias voltages for TLP and FC are 40 V and 150 V, respectively, and these voltages are found experimentally such that the saturation in the output is observed. These diagnostics were biased using a 1 mF polarized capacitor during the discharge process and biasing voltage is constant during total measurements. Figure 6(b) shows that the density waveforms measured at a distance of 50 mm from the plasma gun axially, have two peaks that appeared with some delay which indicates the ionization of polyethylene [(C2H4)n] insulator has the hydrogen (H+) and carbon (C+, C++) ions in the plasma as per the spectroscopic and charge collector studies in references [29, 30]. The parameters considered for calculation of density of hydrogen and carbon plasma respectively using TLP and FC are given in table 1. The peak density values of hydrogen and carbon ions at a distance of 25 mm from the plasma gun axially are (1.6±0.5)×1019 m3 and (2.8±0.6)×1019 m3, respectively, and as the plasma propagates, the density dropped with an increase in the distance from the CPG. At 50 mm, the densities of the hydrogen and carbon ions decreased to (3.57±3.22)×1018 m3 and (5.65±5.20)×1018 m3, respectively. The plasma exhaust mean velocity is calculated from the plasma transit times at different distances. The mean velocities of hydrogen and carbon ions measured using transit times of plasma from 25 mm to 50 mm are (4.54±0.25) cm/μs and (1.81±0.18) cm/μs, respectively.

    Table  1.  Parameters of TLP and FC for calculation of density.
    Parameter Value
    Mass of hydrogen ion 1.67×1027 kg
    Mass of carbon ion 20×1027 kg
    Charge state of hydrogen ion (Z) 1
    Charge state of carbon ion (Z) 2
    e 1.602×1019 C
    Ap 15.07 mm2
    AFC 3.14 mm2
     | Show Table
    DownLoad: CSV

    The temperature trace is directly proportional to the voltage signal of the floating probe of the TLP biasing circuit. The Te amplitude is based on the number of energetic electrons hitting the floating probe and will vanish after the plasma is completed. The temperature signal is independent of the ions that hit the floating probe tip. The electromagnetic noises are less prominent on TLP measurements at lower magnitudes of discharge voltages [20]. Figure 6(c) shows the electron temperature waveform measured using TLP, which rises rapidly during the beginning of the pulse because the most energetic electrons emerge from the CPG region [18].

    For the characterization and to study the divergence of CPG, the FC and TLP are placed at different locations, as shown in figure 7. The diagnostics were placed on-axis axially and off-axis radially to study the CPG plasma parameters. The radial and axial directions are denoted as per plasma motion in the chamber. Figures 8(a) and (b) shows the ni and Te peak values as a function of the on-axis distances. As the diagnostic location is moved far away from the gun axially, the temperature and density decrease as expected due to rapid expansion of plasma and the recombination of ion-electron pairs [31]. The peak density values of hydrogen and carbon ions that occurred at different distances are represented in figure 8(a), and the carbon ion density is higher than the hydrogen ions density. These results indicate the propagation of plasma at longer distances. The off-axis measurements of plasma parameters are determined by placing the plasma diagnostics at locations e, f, g, and h, as shown in figure 7. The locations e and g are +10 mm and 10 mm, respectively, and f and h are +20 mm and 20 mm, respectively, at a distance of 25 mm from the gun axially denoted by 0 on the x-axis in figure 9(a). The ni and Te decrease on both sides of off-axis measurements as shown in figures 9(a) and (b). These measurements are more important in maintaining the dependable values of ni and Te as plasma propagates along the on-axis and may contribute to the optimum thrust of plasma. These studies play a significant role in deciding the plasma bridge length in the operation of plasma opening switch experiments.

    Figure  7.  a, b, c, d are the on-axis locations and e, f, g, h are the off-axis locations of plasma diagnostics.
    Figure  8.  Axial (on-axis) variations of (a) ni and (b) Te.
    Figure  9.  Radial (off-axis) variations of (a) ni and (b) Te from the gun.

    The Debye radius (λd) of plasma is an essential parameter in plasma science and is the minimum radius required to satisfy the charge neutrality condition [32]. The values of ni and Te obtained from experimental data are used to determine the Debye radius of the plasma and obtained using the formula

    λd=(ϵ0kTenie2)1/2, (6)

    where k is the Boltzmann constant, ϵ0 is the permittivity of free space, Te is the electron temperature, ni is the charged particle number density, and e is the electron charge. Table 2 gives the data obtained at 17 kV charging voltage and at position ‘a’ in figure 7. The factor r/λd is calculated to be approximately 526, which shows that the Debye radius is much smaller than the probe radius. This indicates that the dimensions employed to fabricate TLP satisfy the thin sheath approximation. So, the surface area of the probe used to expose the plasma can be considered as measurement region of the plasma parameters.

    Table  2.  Estimation of Debye radius using ni and Te.
    Voltage (kV) Plasma density using TLP,
    ni (m3)
    Plasma temperature,
    Te (eV)
    Debye radius,
    λd (μm)
    Radius of TLP probe,
    r (mm)
    r/λd
    Hydrogen plasma Carbon plasma Hydrogen plasma Carbon plasma
    17 1.6×\10 ^{19} $ 2.8×1019 3.02 0.91 0.68 0.48 526.82
     | Show Table
    DownLoad: CSV

    The plasma density and temperature are the essential plasma characteristics to be studied for CPGs. In this work, the plasma parameters are measured using the triple Langmuir probe and Faraday cup methods. The TLP gives the traces of plasma density and temperature; the Faraday cup only provides information about plasma density. The voltage applied across the two electrodes with polyethylene as the insulator ionizes and produces the hydrogen plasma and carbon plasma, and these plasmas do not interact with each other as they appear at different times. These two ions are observed as the peaks appearing in the density profiles verified by TLP and FC. The maximum density and temperature that occur at 25 mm on-axis measurements from CPG and decrease as the plasma propagates, and values are (1.6±0.5)×1019 m3 and (2.8±0.6)×1019 m3 for hydrogen and carbon ions, and the temperature is (3.02±0.5) eV. The mean velocities measured using plasma transit times are (4.54±0.25) cm/μs and (1.81±0.18) cm/μs for hydrogen and carbon ions, respectively. The variation of plasma parameters radially and axially was studied, and hence these measurements afforded an overall view of how CPG plasma expands and the plasma parameters vary with time and distance, which could facilitate further experiments on CPGs. The experiments shows high reproducibility of plasma parameters from shot to shot. CPG method of plasma generation is a low-cost method and also has control over the density and velocity by varying the insulator length and charging voltage and the temperature by increasing the energy. These parameter studies play a critical role in knowing the plasma bridge length on the cathode electrode of plasma opening switches, and these switches can operate for a higher range of currents depending on the optimized parameters of the plasma source.

    This work is supported by National MCF Energy R & D Program of China (No. 2019YFE03010004), National Key R & D Program of China (No. 2018YFE0309100), National Natural Science Foundation of China (Nos. 11775089 and 51821005) and National Magnetic Confinement Fusion Science Program of China (Nos. 2015GB111002 and 2015GB104000).

  • [1]
    Granetz R S et al 2014 Phys. Plasmas 21 072506 doi: 10.1063/1.4886802
    [2]
    Martín-Solís J R, Loarte A and Lehnen M 2017 Nucl. Fusion 57 066025 doi: 10.1088/1741-4326/aa6939
    [3]
    Dreicer H 1959 Phys. Rev. 115 238 doi: 10.1103/PhysRev.115.238
    [4]
    Rosenbluth M N and Putvinski S V 1997 Nucl. Fusion 37 1355 doi: 10.1088/0029-5515/37/10/I03
    [5]
    Besedin N T and Pankratov I M 1986 Nucl. Fusion 26 807 doi: 10.1088/0029-5515/26/6/009
    [6]
    Smith H M et al 2009 Plasma Phys. Control. Fusion 51 124008 doi: 10.1088/0741-3335/51/12/124008
    [7]
    Wei Y N et al 2019 Plasma Phys. Control. Fusion 61 084003 doi: 10.1088/1361-6587/ab210b
    [8]
    Hollmann E M et al 2010 Phys. Plasmas 17 056117 doi: 10.1063/1.3309426
    [9]
    Loarte A et al 2011 Nucl. Fusion 51 073004 doi: 10.1088/0029-5515/51/7/073004
    [10]
    Bozhenkov S A et al 2008 Plasma Phys. Control. Fusion 50 105007 doi: 10.1088/0741-3335/50/10/105007
    [11]
    Granetz R S et al 2007 Nucl. Fusion 47 1086 doi: 10.1088/0029-5515/47/9/003
    [12]
    Gobbin M et al 2018 Plasma Phys. Control. Fusion 60 014036 doi: 10.1088/1361-6587/aa90c4
    [13]
    Mlynar J et al 2019 Plasma Phys. Control. Fusion 61 014010 doi: 10.1088/1361-6587/aae04a
    [14]
    Lin Z F 2019 Plasma Phys. Control. Fusion 61 024005 doi: 10.1088/1361-6587/aaf691
    [15]
    Riccardo V et al 2010 Plasma Phys. Control. Fusion 52 124018 doi: 10.1088/0741-3335/52/12/124018
    [16]
    Castaldo C et al 2016 Nucl. Fusion 57 016003 doi: 10.1088/0029-5515/56/1/016003
    [17]
    Sun Y et al 2014 Plasma Phys. Control. Fusion 56 015001 doi: 10.1088/0741-3335/56/1/015001
    [18]
    Ghanbari M R et al 2011 Phys. Scr. 83 055501 doi: 10.1088/0031-8949/83/05/055501
    [19]
    Silva C et al 2004 Nucl. Fusion 44 799 doi: 10.1088/0029-5515/44/7/012
    [20]
    Liang Y et al 2019 Nucl. Fusion 59 112016 doi: 10.1088/1741-4326/ab1a72
    [21]
    Ding Y H et al 2018 Plasma Sci. Technol. 20 125101 doi: 10.1088/2058-6272/aadcfd
    [22]
    Liu H et al 2018 Plasma Phys. Control. Fusion 60 115012 doi: 10.1088/1361-6587/aae297
    [23]
    Zhuang G et al 2011 Nucl. Fusion 51 094020 doi: 10.1088/0029-5515/51/9/094020
    [24]
    Hu J et al 2020 Plasma Sci. Technol. 22 115102 doi: 10.1088/2058-6272/aba681
    [25]
    Zhu T Z et al 2014 Rev. Sci. Instrum. 85 053504 doi: 10.1063/1.4873320
    [26]
    Sun Y et al 2016 Nucl. Fusion 56 046006 doi: 10.1088/0029-5515/56/4/046006
    [27]
    Lvovskiy A et al 2018 Plasma Phys. Control. Fusion 60 124003 doi: 10.1088/1361-6587/aae95a
    [28]
    Younis J et al 2009 Plasma Phys. Control. Fusion 51 075017 doi: 10.1088/0741-3335/51/7/075017
    [29]
    Younis J et al 2008 Plasma Sci. Technol. 10 529 doi: 10.1088/1009-0630/10/5/02
    [30]
    Jaspers R E 1995 Relativistic runaway electrons in tokamak plasmas PhD thesis Technische University Eindhoven (Eindhoven, Netherlands)
    [31]
    Reux C et al 2015 Nucl. Fusion 55 129501 doi: 10.1088/0029-5515/55/12/129501
  • Related Articles

    [1]Yue MING (明玥), Deng ZHOU (周登), Wenjia WANG (王文家). Geodesic acoustic modes in tokamak plasmas with anisotropic distribution and a radial equilibrium electric field[J]. Plasma Science and Technology, 2018, 20(8): 85101-085101. DOI: 10.1088/2058-6272/aabc5c
    [2]Zhen ZHENG (郑振), Nong XIANG (项农), Jiale CHEN (陈佳乐), Siye DING (丁斯晔), Hongfei DU (杜红飞), Guoqiang LI (李国强), Yifeng WANG (王一丰), Haiqing LIU (刘海庆), Yingying LI (李颖颖), Bo LYU (吕波), Qing ZANG (臧庆). Kinetic equilibrium reconstruction for the NBI-and ICRH-heated H-mode plasma on EAST tokamak[J]. Plasma Science and Technology, 2018, 20(6): 65103-065103. DOI: 10.1088/2058-6272/aab262
    [3]H R MIRZAEI, R AMROLLAHI. Design, simulation and construction of the Taban tokamak[J]. Plasma Science and Technology, 2018, 20(4): 45103-045103. DOI: 10.1088/2058-6272/aaa669
    [4]Rui MA (马瑞), Fan XIA (夏凡), Fei LING (凌飞), Jiaxian LI (李佳鲜). Acceleration optimization of real-time equilibrium reconstruction for HL-2A tokamak discharge control[J]. Plasma Science and Technology, 2018, 20(2): 25601-025601. DOI: 10.1088/2058-6272/aa9432
    [5]Hailong GAO (高海龙), Tao XU (徐涛), Zhongyong CHEN (陈忠勇), Ge ZHUANG (庄革). Plasma equilibrium calculation in J-TEXT tokamak[J]. Plasma Science and Technology, 2017, 19(11): 115101. DOI: 10.1088/2058-6272/aa7f26
    [6]GAO Hailong (高海龙), XU Tao (徐涛), ZHANG Fan (张帆), JIAN Xiang (简翔), ZHANG Xiaoqing (张晓卿), YANG Zhoujun (杨州军), GAO Li (高丽), JIANG Zhonghe (江中和), ZHUANG Ge (庄革). Equilibrium Reconstruction and Integration of EFIT with Diagnoses in J-TEXT Tokamak[J]. Plasma Science and Technology, 2016, 18(12): 1225-1230. DOI: 10.1088/1009-0630/18/12/14
    [7]LIU Chao(刘超), LIU Yue(刘悦), MA Zhaoshuai(马照帅). Effect of Equilibrium Current Profiles on External Kink Modes in Tokamaks[J]. Plasma Science and Technology, 2014, 16(8): 726-731. DOI: 10.1088/1009-0630/16/8/02
    [8]LI Li(李莉), LIU Yue (刘悦), XU Xinyang(许欣洋), XIA Xinnian(夏新念). The Effect of Equilibrium Current Profiles on MHD Instabilities in Tokamaks[J]. Plasma Science and Technology, 2012, 14(1): 14-19. DOI: 10.1088/1009-0630/14/1/04
    [9]HE Zhixiong, DONG Jiaqi, HE Hongda, JIANG Haibin, GAO Zhe, ZHANG Jinhua. MHD Equilibrium Configuration Reconstructions for HL-2A Tokamak[J]. Plasma Science and Technology, 2011, 13(4): 424-430.
    [10]GUO Wei, WANG Shaojie, LI Jiangang. Vacuum Poloidal Magnetic Field of Tokamak in Alternating-Current Operation[J]. Plasma Science and Technology, 2010, 12(6): 657-660.
  • Cited by

    Periodical cited type(6)

    1. Zheng, P.W., Feng, J.L., Lu, L.F. et al. Impact of hot plasma effects on electron cyclotron current drive in tokamak plasmas. Nuclear Fusion, 2024, 64(12): 126059. DOI:10.1088/1741-4326/ad8667
    2. Hu, L., Huang, Q., Zhuo, T. et al. Achieving prolonged continuous operation of a self-designed 28 GHz/50 kW gyrotron | [自研 28 GHz/50 kW 回旋管实现长时间连续运行*]. Qiangjiguang Yu Lizishu/High Power Laser and Particle Beams, 2024. DOI:10.11884/HPLPB202436.240049
    3. Hu, L., Sun, D., Huang, Q. et al. Design and experimental progress of a 105/140 GHz dual-frequency MW-level gyrotron | [105/140 GHz 双频兆瓦级回旋管的设计与实验进展]. Qiangjiguang Yu Lizishu/High Power Laser and Particle Beams, 2023, 35(8): 083004. DOI:10.11884/HPLPB202335.230114
    4. Hu, L., Sun, D., Huang, Q. et al. 1.0 MW pulse power achieved in 105/140 GHz dual-frequency MW-level gyrotron | [105/140 GHz 双频兆瓦回旋管实现 1.0 MW 脉冲输出]. Qiangjiguang Yu Lizishu/High Power Laser and Particle Beams, 2023, 35(2): 023001. DOI:10.11884/HPLPB202335.220388
    5. Sun, D., Huang, Q., Hu, L. et al. Recent Results of a 50 GHz High Power Gyrotron for ECRH at XL-50 Tokamak. 2023. DOI:10.1109/IVEC56627.2023.10156980
    6. Hu, L., Ma, G., Sun, D. et al. Recent Development of a 105/140GHz MW-level Gyrotron at IAE. International Conference on Infrared, Millimeter, and Terahertz Waves, IRMMW-THz, 2022. DOI:10.1109/IRMMW-THz50927.2022.9895711

    Other cited types(0)

Catalog

    Figures(9)

    Article views (111) PDF downloads (84) Cited by(6)

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return