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    15 June 2025, Volume 45 Issue 2
    Nuclear Fusion Engineering
    Progress of plasma control and operation on HL-3
    LI Bo, ZHANG Jun-zhao, CHEN Yi-hang, LIUPan-le, SUN Jiang, YANG Zong-yu, LI Da, CHEN Xiang, MA Rui, ZHU Xiao-bo, XIA Fan, ZHOU Jian, HL- Experimental Team
    2025, 45(2):  125-134.  DOI: 10.16568/j.0254-6086.202502001
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    Since the HL-3 tokamak first plasma commissioning in 2020,it has achieved multiple scientific breakthroughs, with significant enhancements in plasma control and operation performance. The main progress in plasma control and operation during the past several years are summarized in this paper. With the accumulation of operational experience, HL-3 has successfully been increased the plasma current from ~0.1 MA to over 1.5 MA by ohmic heating. Additionally, the transition from circular cross-section limiter to elongated divertor configurations has been successfully achieved, including single-null and various advanced divertor with high elongation and large triangular ties. Furthermore, special control algorithms for high-current soft landing, disruption prediction, and disruption mitigation are developed. These innovative methods have effectively minimized the occurrence of plasma major disruptions, thereby ensuring the safe, efficient and stable operations of the HL-3 device.
    Thermal stress analysis and safety assessment of HL-3 vacuum vessel during baking
    QIN Zi-wei, RAN Hong, TANG Le, HOU Ji-lai, HUANG Yun-cong
    2025, 45(2):  135-141.  DOI: 10.16568/j.0254-6086.202502002
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    In order to meet the plasma discharge requirements, the vacuum vessel needs to be baked before the experiment operation. At present, the baking temperature of HL-3 vacuum vessel has reached 175°C, and the experimental temperature will be gradually increased in future. In order to ensure the safe operation of the HL-3 tokamak, it is necessary to pre-analyze the stress and deformation of the vacuum vessel shell and the supporting structure under high temperature baking. HL-3 vacuum vessel support adopts sliding support trunnion structure, and the limited sliding of the trunnion will affect the safety of the vacuum vessel. The finite element analysis software ANSYS was used to analyze the stress and deformation of the vacuum vessel under normal and abnormal sliding conditions of the support trunnion at 300°C baking. The results show that when the trunnion slide is limited, there will be serious stress concentration on the vacuum vessel, which endangers the structural safety. In order to ensure that the vacuum vessel is in a safe state, the trunnion must slide enough displacement, which should not be less than 7 mm under 300°C baking. This provides a risk warning for baking experiments and guiding significance for future baking experiments at higher temperatures.
    Effect of Ta content on mechanical properties of W-Ta alloy in high energy rate forging
    CHEN Xiao, FENG Fan, WANG Jian-bao, LIAN You-yun, LIU Xiang
    2025, 45(2):  142-148.  DOI: 10.16568/j.0254-6086.202502003
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    Bulk W-Ta alloys with Ta contents ranging from 0.2 to 1.0 wt.% were prepared through high-energy ball milling for powder preparation, sintering under hydrogen atmosphere and high energy rate forging (HERF). The microstructure of the materials was analyzed by electron backscatter diffraction (EBSD) and scanning electron microscopy (SEM). The hardness and tensile properties of the materials were tested using a Vickers hardness tester and a universal tensile testing machine. The results show that near fully dense bulk W-Ta alloy materials were obtained through high energy rate forging, and obvious <100> and <111> preferred orientations were presented on the forging surface. With the increase of Ta content, the size of grain decreases obviously, the hardness and tensile strength of the material showed an increasing trend. The W-Ta alloy prepared by high energy rate forging exhibited obvious tensile ductility at 300℃. Among them, W-0.5 wt.% Ta had the best comprehensive mechanical properties, with a tensile strength reaching 900 MPa and a strain approaching 19% at 300℃.
    Parametric sensitivity analysis of the palladium permeator for CFETR
    WU Yi-hui, CUI Shi-jie, ZHENG Shan-liang, LIU Song-lin
    2025, 45(2):  149-155.  DOI: 10.16568/j.0254-6086.202502004
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    Due to the differences in the permeability of different hydrogen isotopes on the palladium membrane, the theoretical feasibility of utilizing this property for tritium fuel enrichment was preliminarily discussed. Based on the palladium permeator designed by the Chinese Academy of Engineering Physics for the tokamak exhaust processing (TEP) system of the China Fusion Engineering Test Reactor (CFETR), a mathematical model of the palladium permeator with multi-joints was built and sensitivity analyses were performed for different inlet gas deuterium-tritium ratio, inlet pressure, helium and other impurity gas ratio and inlet flow rate to study in detail their impact on the tritium processing capability of the palladium membrane. The results show that the palladium permeator can be used to adjust the deuterium-tritium ratio in the exhaust gas and achieve the effect of tritium enrichment by properly controlling the inlet flow and pressure.
    Simulation analysis of the influence of tungsten layer thickness on thermal damage of outer horizontal target plate of EAST lower divertor
    QI Kun-yu, CAO Lei, YAO Da-mao
    2025, 45(2):  156-161.  DOI: 10.16568/j.0254-6086.202502005
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    Based on the COMSOL Multiphsics platform, the steady-state thermal stress/strain simulation and plastic strain accumulation simulation under cyclic thermal load were carried out for the tungsten-copper flat-type structure of the outer horizontal target plate of EAST lower divertor by using the finite element method. It was found that during the cyclic thermal loading process, compared to tungsten and CuCrZr alloy, the copper layer undergoes faster and deeper cumulative plastic strain, and forms a cumulative difference with other metals at the interface. In severe cases, it will cause interface detachment; the thickness of the tungsten layer obviously affects the stress peak value of the W-Cu interface and the life of the Cu-CuCrZr interface. The design of the tungsten layer thickness should comprehensively consider the size of each component of the plate structure to extend the service life of the divertor as much as possible.
    RF analysis of CFETR ICRH RF vacuum window
    LONG Xu-yun, MAO Yu-zhou, YUAN Shuai, QIN Cheng-ming, ZHANG Xin-jun, WANG Yong-sheng
    2025, 45(2):  162-168.  DOI: 10.16568/j.0254-6086.202502006
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    To satisfy the demands of high-power, long-pulse, steady-state operations in forthcoming fusion devices, a dual-barrier structured RF vacuum window has been meticulously designed. The window consists of 99.5% pure alumina ceramic, with stainless steel inner and outer conductors featuring copper plating on their surfaces. The impact of size change on the S-parameters of the vacuum window was analyzed with the finite element method, and S11 was less than 87 dB within the designated operational frequency range. Optimization of the ceramic tilt angle was achieved through bending, effectively reducing its surface electric field component. The local electric field distribution was meticulously reconstructed using a corona ring structure. The electric field distribution of the vacuum window under a peak voltage of 45 kV was obtained, and the maximum electric field remained below 2 kV·mm‒1. Furthermore, an evaluation of RF losses was conducted under three distinct working conditions: stable operation state, full reflection state and extreme state, yielding power losses of 643.24 W, 1286.49W, and 5210.28 W, respectively. 
    Research on the mechanical performance of the pre-tensioning system of the background field coil in the CFETR superconducting platform under multi-load cases
    ZHAO Hai-kuo, XU Ai-hua, HAN Hou-xiang, LI Chen-yang, WANG Xian-wei
    2025, 45(2):  169-175.  DOI: 10.16568/j.0254-6086.202502007
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    The background field coil, as an important part of the CFETR superconductivity test platform, provides a constant magnetic field environment for performance and stability testing of superconducting coils. However, the background field coil is subject to multiple loads during operation, such as gravity, preload, thermal, electromagnetic, etc. so its integrity and stability must be ensured by the preload system. To verify the reliability of the preload system under multi-load cases, based on the homogenization theory, the mechanical properties of the preload system are analyzed by simulation under four working conditions, namely independent preload, integral assembly, integral cooling and coil excitation, and the different types of stresses are evaluated by using the ASME standard. The evaluation results show that the stress peaks of each preloaded component are below the stress threshold and have sufficient safety margins, and the analysis will provide theoretical references for the optimal design of the subsequent background field coils as well as their processing and manufacturing.
    Study on microstructure and properties of high energy rate forged pure W
    SHI Ye-zheng, WANG Ying-min, QIANG Jian-bing, WEI Ming-yu, ZHAO Wan-tong, WANG Zi-jie, ZHAO Chen-xi, REN Song-jia, LIAN You-yun, FENG Fan, WANG Jian-bao, LIU Xiang
    2025, 45(2):  176-182.  DOI: 10.16568/j.0254-6086.202502008
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    The processing and engineering application of pure tungsten (W) have been greatly limited by its low temperature brittleness. A high energy rate forging (HERF) processed pure W is reported, which has improved low temperature ductility and high strength. The pure W powder was made by high-energy ball milling of a commercial powder, and the sintered compacts were prepared by hot-pressing sintering. HERF processing of the sintered compacts was conducted at 1550℃, and two lots of samples are made, which were subjected to 57% and 84% plastic deformation, respectively. The microstructure, relative density, Vickers hardness, tensile property and thermal shock performance of the HERF-W material were investigated. The relative density of the sintered W increased from 96% to near full denseness (>99%) after HERF. The grains in HERF-W became pancake-like, associated with strong (111) texture along the forging direction. The hardnesses of the sintered W and HERT-W are 314 HV and 480 HV respectively. The HERF-W exhibited a plastic strain of 11%~14% in tension at 150℃. At 200℃, the tensile strength and plastic strain were greater than 1.0 GPa and 12.5%, respectively, which are superior to industrial pure W and part dispersion-strengthened W alloys. The transient thermal shock performance of the sintered W and HERF-W was evaluated experimentally under the loading conditions of 120 kV accelerating voltage, 1ms pulse duration and 100 pulse cycles within a 4 mm´4 mm area at room temperature on the 60 kW electron beam material testing platform (EMS-60). The crack thresholds of the sintered W and HERF-W (84%) were measured to be 220 MW·m‒2 and 330 MW·m‒2 respectively.
    Thermal hydraulic optimization and analysis of T-tube helium cooled divertor unit
    HU Hua-feng, LI Zai-xin, ZHAO Zhou, WANG Xiao-yong
    2025, 45(2):  183-190.  DOI: 10.16568/j.0254-6086.202502009
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    The current design of T-tube divertor in fusion reactor has problems such as uneven temperature distribution of tungsten tile and material overheating in local areas. In order to ensure the safety and economy of the divertor, the thermal hydraulic analysis of the initial T-tube helium cooled divertor unit model was carried out using the ANSYS CFX software, and the temperature distribution of each structure of the divertor unit and the flow velocity distribution of helium in the coolant were obtained. By optimizing the outlet position, wall roughness and coolant flow rate of the model, on one hand, optimize the helium flow rate, reduce the pressure drop and improve the structural temperature uniformity, on the other hand, improve the heat exchange efficiency of the divertor unit and reduce the maximum temperature of the divertor unit, so as to optimize the thermal hydraulic results of the T-tube helium cooled divertor unit.
    Structural design and heat transfer analysis of limiter without active cooling structure for magnetic confinement nuclear fusion device
    ZHANG Si, YAO Da-mao, CAO Lei
    2025, 45(2):  191-196.  DOI: 10.16568/j.0254-6086.202502010
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    An unmovable limiter without water cooling structure is designed for the HH70 device. The main components are the graphite tile assembly and the base. The graphite tile assembly is mounted on the base through the inner hexagon bolt and butterfly gasket. The transient heat transfer analysis and thermal stress analysis of HH70 unmovable limiter are carried out based on COMSOL multi-physics simulation software. The simulation results show that under the working conditions of the loading heat load of the unmovable limiter being 1 MW·m‒2, 1.5 MW·m‒2 and 2 MW·m‒2, and its sustainable time being 19 seconds, 12 seconds and 9 seconds respectively the stress and temperature of the component materials are within the allowable range, which proves that the designed unmovable limiter meets the requirements of HH70 short pulse operation. Moreover, it provides a beneficial reference for the design of other high heat load components of the device.

    Preliminary design of ICRH antenna for gas dynamic trap experimental device ALIANCE-T

    ZHANG Ke-qing, ZENG Qiu-sun, YU Jie
    2025, 45(2):  197-204.  DOI: 10.16568/j.0254-6086.202502011
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    The preliminary design scheme of ion cyclotron resonance heating (ICRH) system antenna of the gas dynamic trap experimental device ALIANCE-T (Axisymmetric Linear Advanced Neutron Source-Test) is introduced. The purpose is to improve the plasma parameters and confinement. The finite element analysis software COMSOL is used to calculate the magnetic field distribution, which determines the resonant frequency and emission position of the ICRH slow wave heating antenna. The HFSS antenna simulation is used to obtain the impedance of the antenna and calculate the plasma impedance to design a corresponding matching circuit. This preliminary design of the ICRH antenna will provide reasonable scheme suggestions for auxiliary heating system of ALIANCE-T.
    Structural analysis and evaluation of different connection for the first wall with high heat load of the tokamak blanket
    ZHOU Yuan-hang, LIU Su-mei
    2025, 45(2):  205-211.  DOI: 10.16568/j.0254-6086.202502012
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    Based on the simplified first wall (FW) model and finite element method, the temperature distribution of two connection schemes for the FW is obtained under the same boundary conditions and thermal loads. Based on the temperature field analysis results, the elastic and elastic-plastic analysis of the FW connection structure is carried out to evaluate the mechanical properties of the two structures, which has a good heat transfer effect when the FW is connected by welding. Under the same thermal load, the armor temperature is relatively small. However, the structural analysis results show that the tungsten armor structure has high stress and the design margin of the FW flow channel structure is small; When the FW is connected by bolts, it has the advantage of convenient armor maintenance, but the heat exchange capacity is relatively poor, and the bolt design margin is small, which may cause cracks or even fractures. Therefore, when determining the FW scheme, a suitable FW connection scheme can be selected based on the operating conditions and maintenance requirements of the device.

    Virtual assembling technology for ITER correctioncoil assembly based on measurement data

    YUAN Zhong, GU Yong-qi, ZHENG Yuan-yang, WANG Lin, DENG Lei, MA Guo-jiang
    2025, 45(2):  212-219.  DOI: 10.16568/j.0254-6086.202502013
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    The pre-assembly of ITER bottom correction coils (BCCs) is a key milestone of large magnet coil assembly after PF6 / PF5 coil pre-assembly in ITER Pit on site. Because the BCCs should be installed between PF6 and the feeder rings, the assembly positioning of BCCs becomes a difficult construction with the narrow assembly gaps, the specific shape, and a high accuracy requirement of assembly. Therefore, the visual assembling technique based on alignment and measurement data was developed. According to the position measurement data of the positioned parts, the distribution of data, and the condition of sight lines in ITER Pit, using the delivered measurement data of BCC profile, the visual analysis, the position adjustment of the coils, and supports are performed, the lifting paths are optimized, the measurement process during lifting is simulated, and the assembly gaps are planed reasonably, to ensure the lifting safety and the positioning accuracy of the coils. The pre-assembly of six BCCs was successfully completed, the feasibility of the visual assembly technology based on measurement data was verified.
    Plasma Physics
    Study of the distribution and evolution behaviors of atomic reaction in the divertor region of the HL-3 tokamak
    MA Hui-cong, GAO Jin-ming, CAI Lai-zhong, HE Zong-yu-hui, DU Hai-long, WANG De-zhen
    2025, 45(2):  220-226.  DOI: 10.16568/j.0254-6086.202502014
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    A real-time diagnostic system has been developed for monitoring the atomic reaction in the divertor region on the HL-3 tokamak. The system can obtain the spatial distributions of recombination and ionization in the divertor region, and then atomic reaction characteristics of the divertor region are analyzed and studied. The experimental results demonstrate that in the high-recycling regime, the atomic reaction near last closed flux surface (LCFS) of the divertor region is mainly dominated by the ionization, and the dominant regions of the transition from ionization to recombination and the recombination are distributed away from LCFS. The increase in line-averaged electron density leads to an expansion in the distribution region and a rise in the rate of ionization. Higher heating power significantly enhances the radiation of Dα and Dγ spectral lines, resulting in an increased rate of ionization while reducing the occurrence of recombination. It is significant for the understanding of the detachment mechanism, real-time control of divertor detachment and steady-state control technology of heat load under the different divertor configurations of HL-3 tokamak in future.
    The effects of plasma pressure and toroidal rotation on the linear growth rate of resistive internal kink modes
    CHU Jia-Xuan, YANG Jin-hong, REN Zhen-zhen, XIAO Zheng, ZHANG Pei-jie, KUANG Jun, WANG Wei-hua
    2025, 45(2):  227-234.  DOI: 10.16568/j.0254-6086.202502015
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    Using the three-dimensional toroidal nonlinear magnetohydrodynamic code CLT, the influence of plasma pressure and toroidal rotation on the linear growth rate of resistive internal kink mode (RIKM) was numerically investigated. The results show that: (1) The linear growth rate of RIKM decreases (stabilizes) with the increase of plasma pressure at the rational surface q=1, or increases (destabilizes) with the increase of pressure gradient at that location. Therefore, for general plasma pressure profiles, there exists a  QUOTE βcrit value that minimizes the linear growth rate of RIKM, taking into account the combined effects of stabilization and destabilization factors. (2) The larger the peak degree of the pressure distribution, the smaller the βcrit value. When the peak degree of the pressure distribution is small, the βcrit value disappears. (3) When the plasma β is low, the effect of toroidal rotation in suppressing the linear growth rate of RIKM is more significant. As the plasma β increases, the influence of toroidal rotation on RIKM decreases.

    Global multispecies gyro-Landau-fluid model and simulation of turbulence transport

    LIU Yi-fei, LI Ji-quan
    2025, 45(2):  235-241.  DOI: 10.16568/j.0254-6086.202502016
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    In this work, a global multispecies gyro-Landau-fluid model to simulate the ion temperature gradient (ITG) mode in tokamak plasma is proposed. The methods applicable to the accurate calculation of finite Larmor radius (FLR) effects and zonal flow residual levels in global ITG turbulence simulation are developed based on the extended fluid code (ExFC). The simulation results show that the model is not only able to self-consistently simulate the hydrogen isotope ITG instability, but also simulates residual levels of zonal flows in the long wavelength region accurately, and the critical temperature gradient and transport level of the ITG turbulence simulations are closer to those of gyrokinetic model. In addition, the nonlinear simulations demonstrate an avalanche transport phenomenon, which is a typical nondiffusive transport feature of the global ITG turbulence.
    Application of improved particle swarm optimization in temperature control of CFETR helium cooled loop
    XU Jing-han, WANG Xiao-yu, WANG Fen, YAN Yong-jiang
    2025, 45(2):  242-248.  DOI: 10.16568/j.0254-6086.202502017
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    Helium cooled solid blanket thermal test platform has a large capacity and high operational parameters. The heater regulation displays nonlinear and highly inertial dynamic characteristics, posing significant control challenges. To ensure system safety and heating efficiency, the control process is divided into two stages. In the initial heating stage, a segmented PID target setting method is employed to achieve uniform temperature rise. The second stage is steady-state regulation. When parameters change or unexpected events cause temperature fluctuations, rapid temperature adjustments are required. An innovative control method is presented. It integrates an improved particle swarm optimization algorithm with a fuzzy PID controller, which utilizes the particle swarm algorithm to search for optimal parameters, enhancing the performance of the fuzzy PID controller. Simulation results indicate that, compared with traditional PID control, this method exhibits stronger adaptability, nearly eliminates overshooting, and possesses enhanced disturbance rejection capabilities.