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    15 March 2016, Volume 36 Issue 1
    Plasma Physics
    Preliminary investigation on the integrated simulation of the HL-2M divertor
    CAI Lai-zhong1, CUI Xue-wu1, LIU Jian1, XUE Lei1, DING Rui2
    2016, 36(1):  1-7.  DOI: 10.16568/j.0254-6086.201601001
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    The integrated simulation of the divertor is implemented. Many issues including the optimization of the divertor configuration, physical process of detachment, gas puffing and pumping, and vertical displacement event (VDE) on HL-2M are investigated by applying the SOLPS and DINA codes. The effects of divertor plates geometry and detachment on the deposited heat load of divertor plates are evaluated. And the impacts of the gas puffing position, the gas puffing rate and the pumping rate on the divertor performance are also discussed. In addition, the VDEs on HL-2M are also predicted by the DINA code, and the variation of plasma current profile during the VDEs is given, thus the input for the design and analysis of the HL-2M divertor is provided.
    Theoretical model and numerical calculation of pellet ablation rate
    CHENG Fa-yin
    2016, 36(1):  8-12.  DOI: 10.16568/j.0254-6086.201601002
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    A physical model of calculating the pellet ablation rate in tokamak fueling was proposed, which was combined with the 1-D transport model to develop the 1.5D pellet ablation code. Using the parameter of ITER-FEAT, the pellet ablation rate of radius 6mm with initial injection speed of 2000m•s-1 when injecting from low field side was calculated. The results show that the ablation rate first increases gradually over time, then decreases rapidly because of decrement of pellet radius, the maximum ablation rate is about 6×1026s-1, the total penetration depth is about 0.45m. This result is consistent with that gained from the neutral gas shielding model (NGS), and it proved the validity of the code. At the same time, the calculation result indicate that, for the reactor grade tokamak such as ITER, using conventional pellet injection method, the penetration depth is small enough so that the core plasma fueling cannot be achieved although the injection speed is 2000m•s-1. Therefore in order to raise the plasma fueling efficiency, other effective pellet injection scenario must be chosen.

    Simulations of alpha particle ripple loss on CFETR
    HAO Bao-long1, 2, WU Bin2, WANG Jing-fang2, LI Hao2, HU Chun-dong2
    2016, 36(1):  13-18.  DOI: 10.16568/j.0254-6086.201601003
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    使用导心轨道程序ORBIT,在平衡程序EFIT给出的中国聚变工程实验堆 (CFETR)平衡位型下,结合不同的阿尔法(α)粒子分布模型,计算了氘氚聚变产生的α粒子波纹损失情况。计算结果表明:在不考虑锯齿模不稳定性的α粒子分布下,ITER-like和super-X位型下的α粒子波纹损失份额为0.1%,snowflake位型在0.4%,反磁剪切位形在0.6%;在较平缓的α粒子分布下,损失份额增大,损失的高能量α粒子有局域性。

    Exact solutions of the nonlinear incompressible Hall MHD equations
    XIA Zhen-wei, YANG Wei-hong
    2016, 36(1):  19-23.  DOI: 10.16568/j.0254-6086.201601004
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    It was showed that the incompressible ideal Hall MHD equations submitted themselves to the plane-wave exact solutions. They were obliquely propagating left-handed or right-handed circular polarized waves. The fluctuating velocity and magnetic field were connected through the wave-number. In addition, the superposition properties of the plane-wave solutions were discussed. It was found that two arbitrary circular polarized plane waves could superpose when their propagating directions were parallel. But when the propagating directions of two circular polarized plane waves were non-parallel, they could superpose only if they had the same polarized direction, the same wave-number, and the curl of each wave and itself were all in the same direction (or opposite direction).
    Nuclear Fusion Engineering and Technology
    Commissioning and operating of 3MW 68GHz ECRH system in HL-2A tokamak
    KANG Zi-hua, HUANG Mei, RAO Jun, ZHOU Jun,FENG Kun, WANG He, Lu Bo, Wang Jie-qiong
    2016, 36(1):  24-31.  DOI: 10.16568/j.0254-6086.201601005
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    The microwave power source of 3MW ECRH system in HL-2A tokamak is a type of CPD (collector potential depression) gyrotron, which is powered by two kinds of high voltage power sources (PS), cathode PS and anode PS. The function of cathode PS is to offer beam current, and the function of anode PS is focused on two aspects, one is to accelerate the electrons at the region of resonant cavity and the other is to reduce the speed of electron after resonant cavity to decrease the heat load of collector. This design can increase the efficiency of the gyrotron up to 50%. The problems caused by different working condition of different sub-system when the six gyrotrons operated simultaneously, were resolved by optimizing the operating parameters of cathode, anode and other auxiliary PS. In the experimental campaign, six sets of 68GHz ECRH sub-system were operated on parallel at first time and the maximum output power of six gyrotrons was up to 2.5MW, reaching 83% of rating value, and the high power ECW heated the plasma adequately.
    Magnet characteristic study for klystron of 3.7GHz lower hybrid wave
    BAI Xing-yu, LIANG Jun, WANG Jie-qiong, CHEN Ya-li
    2016, 36(1):  32-36.  DOI: 10.16568/j.0254-6086.201601006
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    A new 3.7GHz/2MW/2s LHW system was built on HL-2A tokamak, where TH2103A type klystrons were used as the high power long pulse wave sources. The magnet field distribution in central axis for the klystron was measured via a device for probe fixing. The strongest magnetic field was 176mT at the rough middle of the magnet. Each coil current separately plays the most important role in magnet field distribution at different position. The influence of No.1 power supply was strong nearby the cathode and weaker nearby the resonant cavity. The influence of No.2 power supply was strong nearby the resonant cavity and weaker nearby the output window. The influence of No.3 power supply was strong nearby the output window but much weaker at other places. The data obtained supported for klystron operation optimization.

    Manufacturing and testing of ITER FW CuCrZr/316L(N)-IG explosive Bi-metallic plates
    LI Qian1, WU Ji-hong1, LIU Dan-hua1, WANG Ping-huai1,LI Zong-qin1, MA Rui2, CHEN Ji-ming1
    2016, 36(1):  37-41.  DOI: 10.16568/j.0254-6086.201601007
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    CuCrZr/316L(N)-IG explosion bi-metallic plate manufactured by CuCrZr plate and 316L(N)-IG plate was used as heat sink component of ITER first wall (FW). CuCrZr plate and 316L(N)-IG plate were used as base plate and flyer plate, respectively. Metallographic test, hardness test and tensile test were performed. It turns out that there is an obvious wavy microstructure on the interface of CuCrZr/316L(N)-IG with mean wave length of 1200μm and mean wave height of 500μm. The tensile strength is up to 394MPa at room temperature. Six FW mockups were made, and it turned out that the bi-metallic plate met ITER requirement.
    Upgrade of radiative divertor gas puffing system in EAST tokamak and preliminary experimental results
    WANG Wen-zhang, XIANG Ling-yan, WU Jin-hua, YANG Zhong-shi, DING Fang, WANG Liang, DUAN Yan-min, HU Zhen-hua, MAO Hong-min, LUO Guang-nan
    2016, 36(1):  42-48.  DOI: 10.16568/j.0254-6086.201601008
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    The radiative divertor gas puffing system was redesigned to reduce the delay time by nearly 200ms by the way that valves were put closer to inflation inlet and protected by the thermal shield inside the neck tube. It was also discussed how the feedback control of the heat flux on divertor was effected by the delay time under quasi-steady state condition. Under neutral beam heating condition, the mixture of Ar/D2(1:4) was injected from outer divertor target and the evolution of saturated ion flux and heat flux on divertor target and the effect of gas puffing on the main plasma were investigated. The result shows that the saturated ion flux and heat flux were reduced dramatically through the gas puffing.

    Modulation type high voltage power supply for ICRH on EAST
    WANG Lei1, ZHAO Yan-ping1, HUANG Yi-yun1, JIN Guo-wei2
    2016, 36(1):  49-54.  DOI: 10.16568/j.0254-6086.201601009
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    The general design scheme of power supply is introduced. The structure, circuit and working principle of power supply module are discussed in detail. The component and function of control and protection system are analyzed completely. The abilities of modulation and short-circuit protection of power supply are tested practically and the experimental data and waveforms are given, and the correctness and reliability of design are also proved based on the experiments.
    Electrical analysis of CFETR CS model coil
    WANG Zhao-liang, LIU Xiao-gang, WANG Xian-wei, SHI Yi, WU Yu
    2016, 36(1):  55-59.  DOI: 10.16568/j.0254-6086.201601010
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    In the conceptual design stage of the Chinese fusion engineering testing reactor (CFETR), in order to design and manufacture the central solenoid coil, a model coil consisting of Nb3Sn inside coil and NbTi outside coil was conceptually designed. Internal magnetic field of wires with line current model was solved with data processing to achieve the precise calculation. On this basis, the electromagnetic parameters were calculated, such as the inductance of the coil and the electromagnetic force.

    Mechanical analysis of feeder for CFETR CS model coil
    WANG Xian-wei, WANG Zhao-liang, LIU Xiao-gang, LI Jun-jun , HAN Peng
    2016, 36(1):  60-64.  DOI: 10.16568/j.0254-6086.201601011
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    The magnetic field and electromagnetic force of the central solenoidal coil in China fusion engineering testing reactor (CFETR) are calculated based on Biot Safar’s law. The Von-Mises stress is analyzed by the finite element tool ANSYS and the simulation result is evaluated based on analytical design, then a further research about the stress distribution at the large stress intensity area is performed. The above work will provide reference for the future fabrication.

    Thermal-hydraulic analysis of the CFETR blanket first wall
    WEI Chuan-zi1, SONG Yun-tao1, 2, LEI Ming-zhun2
    2016, 36(1):  65-70.  DOI: 10.16568/j.0254-6086.201601012
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    This article describes the overall design of CFETR helium cooling solid breeding blanket and the cooling structure of the blanket first wall. Thermal-hydraulic analysis of the CFETR blanket first wall was carried out using ANSYS CFX code. Research on how to get the best outlet temperature and satisfy the limit of the first wall material allowable temperature was done. One way is to promote the tube roughness and another way is to optimize the cooling circulation. The results show that the optimization of the cooling loops can satisfy the requirements of the material allowable temperature and the outlet temperature.

    Preliminary analysis of time dependent tritium breeding characteristics of a water cooled ceramic breeder blanket for CFETR
    PU Yong1, LIU Song-lin1, CHEN Yi-xue2, LI Jia3, HUANG Kai1, LI Xiao-jing2, GAO Fang-fang3
    2016, 36(1):  71-77.  DOI: 10.16568/j.0254-6086.201601013
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    Water cooled ceramic breeder blanket (WCCB) is one of the three blanket candidates for Chinese Fusion Engineering Testing Reactor (CFETR). Using a 1-D neutronics model of WCCB for CFETR and correction factor for simplification of neutronic model, time dependent tritium breeding characteristics of blanket were assessed by coupling calculation of the Monte Carlo neutron transport code MCNP and the inventory code FISPACT. Results showed that reduction of tritium breeding ratio (TBR) after several years, even to 20 years, was not obvious when duty time factor of CFETR is 0.5 and fusion power is 200MW, while reduction of annual tritium breeding production was distinct. Additionally, initial TBR of blanket has a great influence on time dependent tritium breeding characteristics.

    Seismic response analysis of ITER TF feeder
    LU Su1, NI Xiao-jun1, CHEN Wei2, ZHANG Shan-wen1, SONG Yun-tao1, WANG Zhong-wei1
    2016, 36(1):  78-82.  DOI: 10.16568/j.0254-6086.201601014
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    The seismic response analysis of the TF coil feeder system is presented, and the modal analysis and response spectrum analysis about a TF coil feeder are carried out using the finite element software ANSYS. The peak response under earthquake load (stress, displacement) is obtained. Finally, according to the ITER magnet structure design standards, the maximum Tresca stress of the system is evaluated. The results show that, feeder system of TF coil meets the SC1 aseismic grade requirements.

    Real-time monitoring and warning system based on EPICS in HL-2A tokamak
    ZHANG Gang, XIA Fan, LI Xin-yi, CHEN Liao-yuan
    2016, 36(1):  83-87.  DOI: 10.16568/j.0254-6086.201601015
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    Based on the analysis of the problems of the HL-2A experiments, a new real-time monitoring and warning system with EPICS network was developed. IT systems, control systems and collecting host were effectively monitored in the course of the experiment. Alarms including phone alarm, email alarm, message alarm were activated simultaneously when an exception occurred in whole domain. The monitor and alarm problems existed in the experiment would be solved fundamentally.

    Seismic analysis of the external bypass equipment for ITER PF converter
    LIAO Yuan-xu, SONG Zhi-quan, GAO Ge, FU Peng, WANG Peng
    2016, 36(1):  88-91.  DOI: 10.16568/j.0254-6086.201601016
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    In order to acquire the anti-seismic capability of ITER external bypass, response spectrum method has been carried out to study the seismic performance through finite element software ANSYS Workbench. Maximum equivalent stress, directional deformation and reaction force of fixed supports of the external bypass structure are analyzed under the design seismic spectrum provided by ITER organization. The analysis results show that the maximum equivalent stress is not more than 8.3MPa, and the maximum directional deformation is not more than 2.6mm. The results above indicate that the external bypass structure can meet anti-seismic requirements. In addition, the results also provide reference for the foundation design of the external bypass, as well as make a contribution to the follow-up seismic design work.

    Non-Fusion Plasma Applications
    Corrosion behavior of liquid lithium to 316L stainless steel weldment
    CAO Zhi1, CAO Xiao-gang1, WANG Jian-qiang1, GOU Fu-jun1, CHEN chun-li1, PAN Yu-dong2, LI Ying3, YANG Dang-xiao1
    2016, 36(1):  92-96.  DOI: 10.16568/j.0254-6086.201601017
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    Static corrosion of 316L stainless steel (SS) in liquid lithium at 350°C, 0.15MPa, 500h was studied by corrosion weight loss, SEM and Metallographic analysis, and penetration depth of liquid lithium was represented by LIBS combined with step profiler. The result show that average corrosion ratio of 316L SS sample (containing weld) was 99.8mg·m-2·h-1, corrosion depth was 6.4μm, and in weld of 316L SS the penetration depth was 8.6μm, and in base metal it was 4.8μm. There was significant intergranular corrosion of lithium to material at the weld.