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    15 December 2018, Volume 38 Issue 4
    Plasma Physics
    Design of plasma configuration with high elongation and triangularity for HL-2A tokamak
    MA Ze-yu, SONG Xian-ming, YUAN Bao-shan
    2018, 2(4):  373-378.  DOI: 10.16568/j.0254-6086.201804001
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    A code named SE which is based on MATLAB language for editing and designing plasma shape is introduced, with its design principle, main function, operation interface and operation steps. The correctness of SE is proved effectively with traditional code SWEQU. Furthermore, these two codes are used to design and confirm the discharge parameters of two plasma shapes with medium elongation and triangularity. In order to achieve shapes with higher elongation and triangularity, the limit of circular cross section must be broken by using upper divertor coils. Finally, a plasma shape with higher elongation and triangularity is designed and its discharge parameters are provided with SE code. The design results demonstrate that with upper divertor coils energized, new plasma shapes with higher elongation and triangularity can obtained on HL-2A tokamak. These new plasma shapes lay solid foundation for improving the plasma quality on HL-2A tokamak.

    The retroreflector characteristics study in CO2 dispersion interferometer on HL-2M tokamak
    LI Yuan, ZHOU Yan, WANG Hao-xi, LI Yong-gao, YI Jiang, DENG Zhong-chao
    2018, 2(4):  379-385.  DOI: 10.16568/j.0254-6086.201804002
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    For the influence of the mental retroreflector processing and installation error on the optical propagation, the relationship between the dihedral angle error of the retroreflector and the reflected beam was studied. The impacts of the surface and morphology of retroreflector on reflection properties was analyzed, and the reflectivity of different retroreflector cone was measured and compared. The polarization characteristics of retroreflector was also analyzed. According to the study results, for the retroreflector in CO2 dispersion interferometer on HL-2M tokamak, the surface machining accuracy should be within 0.3μm, the dihedral angle error should be a positive tolerance and controlled within 30'', the surface coating is firm and uneasy to fall off.

    Diagnosis of the width of ELMs filament by high-speed CCD visible camera-light system on EAST tokamak
    CHEN Shun-dong, MA Qun, ZHONG Fang-chuan
    2018, 2(4):  386-393.  DOI: 10.16568/j.0254-6086.201804003
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    The high speed CCD visible-light camera system has been installed to detect the dynamic characteristics of ELMs filaments on EAST tokamak. In order to convert the CCD video imaging coordinates into real space coordinates, the CCD system has calibrated using Tsai’s two-stage calibration technique. A raised spike in the grayscale profile, drawn by selecting the grayscale value of the image in the vertical direction of the ELMs filament in the CCD image, represents an ELMs filament structure whose positional coordinates are determined by the apex of the spike. The Sobel edge detection operator was used to examine the edge profile of the filament to obtain the width of the filament. By analyzing the characteristics of the filament width of the ELMs, it is found that the width of ELMs filaments continuously decreases outward from the outermost magnetic surface. This indicates that the filaments continue to dissipate energy and particles as they propagate outward. The width of filaments of Type-I ELMs is greater than that of Type-III ELMs.

    Tearing mode real time active control system
    XIA Fan, XU Yuan, LING Fei, YE Ji-fei, SONG Shao-dong, JI Xiao-quan, MA Rui, ZHOU Jian, SUN Teng-fei, YAN Long-wen
    2018, 2(4):  394-401.  DOI: 10.16568/j.0254-6086.201804004
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    Tearing mode real-time active control system has been developed on HL-2A tokamak. During the plasma discharge, electron cyclotron emission and soft X-ray diagnostic signals are used to get the geometric location where tearing modes emerge, combined with the real time profile reconstruction and electron cyclotron wave (ECW) deposition algorithm, the target angle of ECW steering mirror can be obtained. Then the mirror angle is set by the motor so that the ECW power deposit at the position of tearing modes finally. Consequently the tearing modes can be controlled, owing to the change of local current profile, and the plasma confinement is improved. This system has been deployed in HL-2A campaigns after 2015, and the good control effect is obtained. It has been proved that the system can discover and control not only the classical tearing modes in real time, but also has the potential to control the neoclassical tearing mode in the future.

    Dynamic control research of ferrofluid in the air-flow field
    LI Jun-long, ZHU Ping, GAO Peng, REN An-ye
    2018, 2(4):  402-407.  DOI: 10.16568/j.0254-6086.201804005
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    Based on the superparamagnetism of the ferrofluid which can receive the magnetic force after magnetization by the magnetic field, and there is no magnetic hysteresis after demagnetization, this paper presents a dynamic control method of the ferrofluid. The electromagnetic field is directly added to ferroliquid-column in the air domain to achieve the dynamic deflection. The surface tension, gravity force and magnetic force are added to the modified N-S control equation, and the magnetic induction equation is combined. The ferrohydrodynamics (FHD) model is established. The model of volume of fluid (VOF) is presented to describe ferrofluid jetting in the air domain with the secondary development of fluent. The liquid phase distribution and dispersion of ferrofluid are simulated under different magnetic field intensity. The effect of magnetism on its dynamical behavior is analyzed. The results show that with the increase of magnetic field intensity and jet distance, the ferrofluid velocity along the magnetic field direction and the offset increase, and its dispersion is gradually obvious.

    Nuclear Fusion Engineering and Technology
    Metrology for tilt angle of central axis of HL-2M tokamak toroidal field coils
    LIU Jian, CAI Li-jun, ZHOU Hui, LIN Tao, LI Guang-shen, LIU De-quan
    2018, 2(4):  408-411.  DOI: 10.16568/j.0254-6086.201804006
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    By measuring the spatial coordinates of several points on the figure joints and slice joints of the toroidal field coils on HL-2M device, the outer contour planes of the coils are fitted with the spatial data of the points by the least squared method and the tilt angle of central axis is calculated by the spatial relation between the planes and the central axis. With the simplified model and numerical simulation, the tilt angles of different spatial points with several standard deviations of measurement are calculated. The average relative error of tilt angle is 0.10‰ and the relative standard deviation is 1.21‰ with a low standard deviation of metrology (σ=0.05mm).

    Simulation analysis for helium cooling system of China helium cooled ceramic breeder test blanket system
    WANG Xiao-yong, ZHANG Hong-xiang, YE Xin-fu
    2018, 2(4):  412-419.  DOI: 10.16568/j.0254-6086.201804007
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    According to the system design and arrangement of helium cooling system of China helium cooled ceramic breeder (CHCCB), helium cooling system simulation model is built using large one-dimension fluid simulation software Flowmaster. For different operation conditions of tritium breeding blanket system, helium flow conditions and parameter distribution are simulated for helium cooling system, using such simulation model. Temperature, pressure and velocity distributions and other related parameters have been obtained on different scenarios for hot waiting state, hot standby state, normal operation state and tritium out-gassing state, which provide reference for the design of system and equipment selection. Meanwhile, the model and simulation results have some reference significances for the simulation of helium cooling system for CFETR.

    Investigation of packing behavior of pebble bed in solid tritium breeder blanket
    GONG Bao-ping, FENG Yong-jin, HE Kai-hui, LIAO Hong-bing, WANG Xiao-yu, FENG Kai-ming
    2018, 2(4):  420-427.  DOI: 10.16568/j.0254-6086.201804008
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    The packing behaviors of pebble bed in blanket were investigated by packing experiment and discrete element modeling. The packing behaviors of cylinder mono-sized pebble beds show that the average packing factor is gradually increased with increase of the diameter ratio of the bed to pebbles. The experimental and simulated results of cylinder mono-sized pebble beds are in good agreement. Using binary-sized pebble packing and increasing the size ratio of binary pebbles can increase the packing factor of pebble bed, significantly. For binary-sized pebble bed, the average packing factor increases first and then decreases with the increase of the large pebble volume fraction. The maximum value is achieved when the larger pebble volume fraction is about 60%~80%. By optimizing the filling process of the pebble bed, the packing factor of the binary-sized pebble bed has reached 0.8, but the uniformity of the binary-sized bed is poor.

    Design and realization of control system based on stepper motion driven by PLC for limiter displacement on HL-2A tokamak
    TIAN Pei-hong, XU Jie
    2018, 2(4):  428-436.  DOI: 10.16568/j.0254-6086.201804009
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    In order to realize automatic control of HL-2A limiter displacement, an automatic control system of limiter displacement has been designed. The two-phase hybrid stepper motor was adopted. The S7- 300PLC was used as the main controller and the FM453 was used as the positioning module of the stepping motor. The drive, control and detection of the stepping motor have been realized. At the same time, the communication with the host computer was completed, and the functions such as the limiter displacement settings and data display of the HL-2A tokamak have been achieved.

    System code costing analysis of CFETR
    XIE Jin-yu, LI Jia-xian, ZHENG Guo-yao, DUAN Xu-ru
    2018, 2(4):  437-445.  DOI: 10.16568/j.0254-6086.201804010
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    Based on conceptual design of CFETR, the paper focuses on the costing part, shows the predicted engineering cost and proportion of each key component, and presents the relationship of each subsystem, by using design parameters of CFETR as inputs in MathCAD. Primary analysis results are obtained from studying the tendency of outputs and compared with such proportions of ITER. Such output parameters and simulation results provide references to optimize parameter and operation advice, engineering design of CFETR, and new idea for the future fusion engineering costing analysis and structure optimization.

    A preliminary study of microstructure and properties about CLF-1 steel and 316L TIG welding joint used for fusion reactor
    HU Zhi-qiang, ZHAO Feng-chao, WU Xin-hua, LIAO Hong-bin, WANG Xiao-yu, FENG Kai-ming
    2018, 2(4):  446-451.  DOI: 10.16568/j.0254-6086.201804011
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    A preliminary study of microstructure and properties of the welded joint of low activation CLF-1 steel used for fusion reactor and 316L dissimilar metal by tungsten inert gas (TIG) welding using W19123L as filler material, has been performed. The welded joint forming is proved well and without defect. The welded joint consists of CLF-1 zone [base metal (BM), heat affected zone (HAZ), fusion zone (FZ)], inside layer (IL), weld zone (WZ), and 316L zone (BM, HAZ, FZ). Tensile strength of the joint is better than the base metal minimum value in room temperature. Both surfaces of welded joint are without crack and with deformation uniformity under the bending test. The distribution of impact value of the joint is concave-like and satisfies the designed values for the welded joint, the WZ’s value is the lowest, the HAZ’s of both WZ zones is the second, the BM’s was the best, and the 316L steel zone’s is slightly larger than the CLF-1 zone’s. The hardness values of the point under the 1.6mm top surface of welded joint have a larger fluctuation range, and is slightly higher than those of 1/2T and above down surface 1.6mm position. The hardness distribution of 1/2T and above the down surface 1.6mm position is roughly uniform, and has a downward trend from the CLF-1 zone to 316L zone. Welding properties generally has remained stable and satisfy the requirement of dissimilar steel welding performance matching.

    Structural analysis and fatigue life evaluation for W/RAFMs divertor target
    ZHANG Jian-wu, PENG Xue-bing, MAO Xin, YE Min-you, QIAN Xin-yuan
    2018, 2(4):  452-458.  DOI: 10.16568/j.0254-6086.201804012
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    The possibility of W/RAFMs divertor target using the RAFMs as the heat sink, and prediction of fatigue life under different operation condition were investigated. The maximum tolerable heat load is 8MW·m-2. The magnitude will be reduced to 7MW·m?2 if considering the 2 years operational cycle time. Taking into account the profile of heat load and neutron irradiation, the structural design of W/Cu and W/RAFM dual divertor target plates can be used.

    Comparison and analysis of heat transfer ability of EAST first wall water-cooled structure types
    ZI Peng-fei, CAO Lei, LI Lei, HAN Le, LIU Yan-wei, YAO Da-mao
    2018, 2(4):  459-465.  DOI: 10.16568/j.0254-6086.201804013
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    In order to compare heat transfer capacity of EAST first wall water-cooled structure more directly and give the selection reference in future design, this article compares the heat transfer capacities of different water-cooled structures in same conditions with the method of simulation analysis, and gets the comparison result by comparing the temperature of materials in different structures. At the same time, it made an overall comparison for various structures in considering the allowable temperature of various materials, the difficulty of manufacturing process and the project cost. It can be seen from the calculation results that the tungsten string structure has the best heat transfer capacity, followed by the welded structure, and the bolt connection structure is worst. Combining the cost and process difficulty, we can see that the tungsten string structure is still the most suitable structure for high heat flux area. Welding structure with W/TZM/C as first wall material is more suitable for lower heat flux area. Bolted structure will be replaced gradually in the future.

    Review of research progress of safety analysis on HCCB TBM
    WU Xiao, SONG Jiang-feng, YANG Lei, HUANG Zhi-yong, WANG Shuai
    2018, 2(4):  466-472.  DOI: 10.16568/j.0254-6086.201804014
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    Helium cooled ceramic breeder test blanket module (HCCB TBM) was introduced. The TBM system is mainly composed of test blanket, helium coolant system, tritium extraction system, coolant purification system, tritium measurement system and neutron activation system. The structural safety analysis of TBM mainly includes electromagnetic safety analysis, thermal-hydraulic safety analysis and neutronics safety analysis. The material safety analysis of TBM is divided into safety analysis of structural material, safety analysis of functional materials, such as tritium permeation barrier and tritium treatment materials. The research progress made by scholars at home and abroad in the above-mentioned security analysis research work was summarized, and the future safety analysis of the TBM tritium system was looked forward to, with a view to providing reference for the safety design of tritium systems.

    Non-Fusion Plasma Applications
    Multi-physics simulation of inductively coupled plasma torch based on COMSOL
    JIA Rui-bao, LUO Tian-yong, CHEN Lun-jiang
    2018, 2(4):  473-481.  DOI: 10.16568/j.0254-6086.201804015
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    In order to optimize the process of plasma spheroidization of the lithium micro-powder, a 2-D model of inductively coupled thermal plasma torch is presented. The calculating domain of the electromagnetic field is extended to the air region outside the plasma discharge region and multi-physics coupling calculation was performed by using COMSOL software. The plasma electromagnetic field, temperature and velocity distributions are obtained. The physical mechanism of distributions is analyzed. The simulation found that there are two sets of symmetrical reflux vortices in the coil section of the plasma region. The velocity distribution which locates in the center of coil section and closes to the wall of confinement tube is in disorder. The plasma particles hit the wall along the radial direction. Disorderly flow may cause a rupture area along the circular tube wall. Based on the simulation results, it is proposed that in the process of inductively coupled plasma spheroidization, powder injection port can be moved down to avoid the upper reflux vortex.

    Study on characteristics of ion emission from the ferroelectric media under low pressure condition
    XU Ao, YANG Lin, JIN Da-zhi, WAN Xiang, CHEN Lei
    2018, 2(4):  482-488.  DOI: 10.16568/j.0254-6086.201804016
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    Characteristics of ion emission from the ferroelectric media was investigated under low pressure condition. By utilizing high-speed camera photography, spectral analysis, and particle-in-cell simulation coupling with Monte Carlo collision, the optical emission composition and images from ferroelectric surface, plasma evolution of ferroelectric surface discharge, the mechanism of ion generation and the forming of ion current are discussed. These results are useful for further understanding to ferroelectric ion sources.