Loading...
Welcome to Nuclear Fusion and Plasma Physics, Today is Share:

Table of Content

    15 December 2017, Volume 37 Issue 4
    Plasma Physics
    Calculation and analysis of electromagnetic force of a HL-2M PF coil
    YUAN Bao-shan, QIU Yin, LI Guang-sheng, LI Jia-xian
    2017, 37(4):  373-378.  DOI: 10.16568/j.0254-6086.201704001
    Asbtract ( )   PDF (3440KB) ( )  
    References | Related Articles | Metrics

    A hybrid structure was adopted for the PF coil of the building HL-2M device. In the process of discharge, there is a strong coupling between the coils, each coil will be subjected to a large electromagnetic force. In this paper, PF coil electromagnetic force is computed by the analytic method under the discharge conditions of the largest Ip =3MA plasma current and various configurations. These calculation results are of reference value for the design of PF coil and its support structure.

    Simulation on shielding system of neutron camera for HL-2A
    ZHANG Peng-fei, LIU Yi, ZHANG Yi-po, YUAN Guo-liang
    2017, 37(4):  379-384.  DOI: 10.16568/j.0254-6086.201704002
    Asbtract ( )   PDF (2926KB) ( )  
    References | Related Articles | Metrics

    The physical model of the neutron camera Monte-Carlo partical transport (MCNP) for HL-2A was established by using Monte-Carlo simulation code. The shielding of D-D fusion neutrons and gamma rays was simulated. The shielding effects were compared for four common shielding materials, including mixture of paraffin lithium carbonate, polyethylene, lead, 316L stainless steel. Calculation results show that mixture of paraffin lithium carbonate and lead are the best shielding materials for neutron camera, among them the mixture of paraffin lithium carbonate is used for slowing-down and absorpting neutrons, while lead is used for blocking neutrons and gamma rays. In addition, both the required thickness of shielding material for neutron and gamma ray and the neutron scattering rate of collimator tube have been obtained by using MCNP simulation.

    Magnetic field distribution surrounding HL-2M tokamak and magnetic shielding analysis for NBI device
    HE Feng, CAO Jian-yong, WEI Hui-ling, LIU He, YANG Xian-fu, LI Jia-Xian, SONG Xian-ming
    2017, 37(4):  385-391.  DOI: 10.16568/j.0254-6086.201704003
    Asbtract ( )   PDF (2135KB) ( )  
    References | Related Articles | Metrics

    The time and space distribution of the toroidal and poloidal magnetic field surrounding the HL-2M tokamak was simulated with the electromagnetic field simulation software CST Studio from Germany. The results show that the magnetic field intensity surrounding the neutralizer tank and ion source of NBI device was more than2?10-3T, so the magnetic shielding of NBI neutralizer tank and ion source was necessary. Then the magnetic field distribution surrounding NBI neutralizer tank and ion source after shielding with iron was simulated with CST Studio.

    Deep penetration shielding calculation method for fusion reactors
    ZHANG Bin1,LI Xiao-jing2,LIU Cong1, CHEN Yi-xue1
    2017, 37(4):  392-398.  DOI: 10.16568/j.0254-6086.201704004
    Asbtract ( )   PDF (2709KB) ( )  
    References | Related Articles | Metrics

    In order to improve the computational accuracy of fusion reactor deep penetration shielding problems with complex streaming gaps, MC-SN coupling method is developed. Based on the Theta Weighted differencing scheme, the Directional Theta Weighted and Exponential Directional Weighted differencing schemes, which have adaptive features, are introduced. Biased quadrature sets are also constructed on base of Legendre-Chebyshev sets and angular refinement technique to deal with shielding calculation problems of strong fusion neutron penetration and anisotropic scattering. Through the comparative analysis with MCNP simulation results, it can be found that these methods can effectively improve the accuracy for some deep penetration shielding calculation in fusion reactors.

    Estimating electric field strength and electron mean kinetic energy for co-axial dielectric barrier discharge
    MA Tian-peng, ZHONG Fang-chuan
    2017, 37(4):  399-403.  DOI: 10.16568/j.0254-6086.201704005
    Asbtract ( )   PDF (1135KB) ( )  
    References | Related Articles | Metrics

    The electric field strength and electron mean kinetic energy in co-axial dielectric barrier discharge (DBD) were estimated based on static electric filed model. Through the comparison of the single dielectric layer DBD with the double dielectric layer DBD, it was found the electric field strength and electron mean kinetic energy in double dielectric layer DBD are greater than that in the single dielectric layer DBD under the same electrode configuration and discharge conditions. The calculation results can successfully applied to explain the toluene degradation efficiency in double dielectric layer DBD is larger than that in the single dielectric layer DBD under the same discharge parameters.

    Ring coded imaging for hard X-ray focal spot
    ZHANG Mei, HU Hua-si, CHENG Liang, WANG Pei-wei, LI Yang, YUAN Yuan, PENG Bo-dong, ZHOU Hai-sheng, LI Kui-nian
    2017, 37(4):  404-410.  DOI: 10.16568/j.0254-6086.201704006
    Asbtract ( )   PDF (5762KB) ( )  
    References | Related Articles | Metrics

    Ring coded imaging technology with high detection efficiency was put forward to diagnose space distribution for low intensity X-ray spot with several tens to hundred of keV. In this paper, the relations of detection efficiency and signal – noise ratio varied with the ring geometric parameters were researched. The coaxial imaging technology was resolved by employing the design of local micro joins on the ring aperture, and simulating the influence of micro joint area size on imaging quality. The ring aperture imaging system was developed and the Unique-II X-ray spot imaging experiment was implemented. The results show that the space distribution of the X-ray spot is approximate a ‘saddle’ shape, and the intensity in the middle part is lower than both sides along the long axis of the elliptical surface; this conclusion is consistent with pin-hole image; the detection efficiency of ring is evidently more than that of pin. Finally, the effects of and the R-L method and Wiener method used to restore the image are analyzed.

    Nuclear Fusion Engineering and Technology
    Development of deflecting magnet for HL-2M 5MW-NBI beam line
    CAO Jian-yong, ZHOU Hong-xia, LIU He, YANG Xian-fu, YU Pei-xuan, WEI Hui-ling
    2017, 37(4):  411-417.  DOI: 10.16568/j.0254-6086.201704007
    Asbtract ( )   PDF (4783KB) ( )  
    References | Related Articles | Metrics

    According to the design parameters of 5MW-NBI beam line of HL-2M tokamak, spatial arrangement of components, geometrical focus characters and so on, 3D model of the deflecting magnet with 8 groups of wires is built up. With an electromagnetic field simulation software-CST Studio, the deflection magnetic field distribution and deflection trajectories of ion beams with different components are obtained. With the simulation results the physical structure of deflecting magnet is optimized, the engineering design of the magnet is completed and then the manufacture and test are finished. The testing result of the magnetic field distribution of the deflecting magnet shows: the error between measurement value and calculation result is less than ±5%, and the machined deflecting magnet can meet the design requirement.

    Measurement and analysis of transmission line efficiency for 3.7GHz LHCD system on HL-2A
    WANG Chao, ZENG Hao, LU Bo, WANG He, BAI Xin-yu, LIANG Jun, CHEN Ya-li
    2017, 37(4):  418-421.  DOI: 10.16568/j.0254-6086.201704008
    Asbtract ( )   PDF (2604KB) ( )  
    References | Related Articles | Metrics

    The power measurement method for 3.7GHz LHCD system on HL-2A was introduced. It is found by HFSS simulation that the impact of backward wave phase on the measurement of forward power may be suppressed if the isolation of directional coupler is more than 30dB. After improving the system, the total transmission line efficiency of the LHCD system can reach 89% with maximum power 1.5MW in 2016 experiment campaign.

    Thermal-hydraulic analyses of HCCB TBM shield
    LI Xin-ze, WU Xin-hua, WANG Xiao-yu, LI Qiang
    2017, 37(4):  422-428.  DOI: 10.16568/j.0254-6086.201704009
    Asbtract ( )   PDF (4834KB) ( )  
    References | Related Articles | Metrics

    Preliminary design for HCSB TBM shield was introduced, and much attention is paid to the comparison between conception design review (CDR) design and the current design, the thermal-hydraulic analyses of TBM shield was performed. The results of analyses indicate that the maximum temperature of TBM shield is about 246.9℃ at the bottom key. The velocity, pressure and wall heat transfer coefficient are all well below the allowable values. Moreover, a panel is added to reduce the temperature of bottom key based on the result of thermal-hydraulic analysis.

    Effect of EAST liquid lithium limiter distributor box on flow of lithium
    HU Le-Xin, YANG Qin-Xi, SONG Wei, SONG Yun-Tao, ZUO Gui-Zhong, HU Jian-Shen
    2017, 37(4):  429-435.  DOI: 10.16568/j.0254-6086.201704010
    Asbtract ( )   PDF (2415KB) ( )  
    References | Related Articles | Metrics

    Numerical simulation method is applied on different sizes, shapes, and surface conductivity of distributor channels to observe the effects of the structure and the surface conductivity of distributor channels on the flow of liquid lithium. The calculated results show that the smaller width of distributor channels is, the more uniform the outlet speed of liquid lithium is, and the smaller the peak velocity is. On the contrary, the smaller width of distributor channels is, the higher the pressure loss is between the inlet and outlet. Furthermore, the better the surface conductivity is, the higher the MHD pressure drop is as well. In comparison with the rectangular distributor channels, the outlet velocity distribution of circular and elliptic distributor channels is much more uniform. In addition, the thermal balance calculation of limiter can ensure the safe and stable operation of the flow liquid lithium limiter. The above calculated results have important guiding significance for the parameter designing of distributor, the selection of electromagnetic pump, and the design of the cooling system.

    Development of MoS2 self-lubrication coating of sliding pads for ITER poloidal field
    LUO Rong-rong, LI Peng-yuan, WEI Hai-hong, CHEN Hui, SUN Zhen-chao, HAN Shi-lei, LIU Bai-xin
    2017, 37(4):  436-440.  DOI: 10.16568/j.0254-6086.201704011
    Asbtract ( )   PDF (4446KB) ( )  
    References | Related Articles | Metrics

    The MoS2 self-lubrication coating spraying in the surface of 316LN austenitic stainless steel was developed and investigated. The test result shows that the coating had the preferable friction properties at liquid nitrogen temperatures (77K) for high pressure, and the bonding strength test showed that the coating was good adhesion with base materials. In addition, after the thermal shock between 300K and 77K, The coating was free from cracks, flakes and debonding. The average friction coefficient of MoS2 coating under static compression was reported, which indicated that the friction coefficient was less than 0.1, which met the requirements of ITER.

    Structural design and strength analysis of supporting rib in ITER vacuum vessel
    ZHANG Jian-zhong, CHEN Ke, WANG Yan
    2017, 37(4):  441-445.  DOI: 10.16568/j.0254-6086.201704012
    Asbtract ( )   PDF (684KB) ( )  
    References | Related Articles | Metrics

    As an important part of vacuum vessel, supporting rib not only supports double layer shell, but also supports neutron shielding layer. It must meet all strength requirement from them in practice. Vacuum vessel structure feature, supporting rib layout and structure requirement were analyzed. Supporting rib was designed with CATIA. Its strength stress nephogram and deformation nephogram were obtained with finite element analysis under the ANSYS Workbench environment. From the result, supporting rib structure and stress can meet the design requirement, so as to assure its normal working in ITER vacuum vessel.

    High heat flux test and post examination of ITER divertor W/Cu monoblock mock-ups
    SUN Zhao-xuan, LI Qiang, WANG Wan-jing, WANG Ji-chao, WANG Xin-li, WEI Ran, XIE Chun-yi, LUO Guang-nan
    2017, 37(4):  446-451.  DOI: 10.16568/j.0254-6086.201704013
    Asbtract ( )   PDF (4531KB) ( )  
    References | Related Articles | Metrics

    High heat flux test of ITER divertor W/Cu monoblock mock-ups were finished. All tested mock-ups successfully withstood the heat cycles above and met the requirements of high heat flux performances specified by IO. After HHF test, the post analysis was performed on tested mock-ups. The results found the debonding of the Cu/CuCrZr interface and the crack of W. The scanning electron microscope (SEM) image of the break shows that intergranular rupture was the main mechanism of the W crack. The recrystallization was observed in the W monoblocks and the recrystallized depth was estimated by metallography analysis. The temperature distribution was also obtained by finite element analysis and a good correspondence with recrystallization observed by experiment was found.

    Flow characteristics analysis of purge gas in binary mixed pebble bed of water-cooled ceramic blanket for CFETR
    CHEN You-hua, CHEN Lei, LIU Song-lin
    2017, 37(4):  452-456.  DOI: 10.16568/j.0254-6086.201704014
    Asbtract ( )   PDF (3757KB) ( )  
    References | Related Articles | Metrics

    As one of the breeding blanket candidates for China Fusion Engineering Test Reactor (CFETR), the water-cooled ceramic blanket (WCCB) was proposed to use binary mixed breeding pebble bed in order to increase the packing factor and meet tritium breeding ratio requirement. The DEM method was used to establish the packing structure of binary pebble bed which can meet the neutronics requirements and the flow characteristic of helium in the pebble bed was analyzed by CFD simulation. Porosity distribution, velocity distribution and pressure drop in the pebble bed were discussed.

    Finite element analysis on plasma-driven transport of tritium in FW of WCCB for CFETR
    LAO Ding-yu, HUANG Kai, CHEN Lei, LIU Song-lin
    2017, 37(4):  457-464.  DOI: 10.16568/j.0254-6086.201704015
    Asbtract ( )   PDF (4100KB) ( )  
    References | Related Articles | Metrics

    Based on the finite element method (FEM), a one-dimensional tritium transport model is set up using COMSOL multiphysics. The model is benchmarked against literature results of hydrogen isotope retention in tungsten. Then a two-dimensional FW model of WCCB for China fusion engineering test reactor (CFETR) is built to analyze the transport of tritium, taking Soret effect into account. The simulation results show that for a single typical blanket, total tritium retention in FW is 0.12mg, and the permeation amount into the coolant is 0.12mg•yr-1. The retention in RAFM steel will increase by 8.80% while permeation to the coolant by 65.97% when the Soret effect is neglected. Therefore, the Soret effect is significant for the permeation and retention of tritium.

    Design and construction of a small helium loop
    YE Xin-fu, FENG Kai-ming, WANG Xiao-yu, LI Zai-xin, WANG Yan-ling, WANG Xiao-yong, WANG Fen, YAN Yong-jiang
    2017, 37(4):  465-468.  DOI: 10.16568/j.0254-6086.201704016
    Asbtract ( )   PDF (1020KB) ( )  
    References | Related Articles | Metrics

    The helium loop was designed and constructed to the testing of various components for nuclear fusion facilities. The loop contains diaphragm circulator, electrical heater, helium recuperator, water-helium heat exchanger and storage tank etc. The test section helium inlet parameters are pressure 8MPa, temperature 300℃,and flow rate 0.1kg•s-1. These parameters fulfill small components testing requirements.

    Logical control system for LHCD on HL-2A tokamak
    WANG Jie-qiong, HUANG Mei, LU Bo, FENG Kun, RAO Jun
    2017, 37(4):  469-474.  DOI: 10.16568/j.0254-6086.201704017
    Asbtract ( )   PDF (3845KB) ( )  
    References | Related Articles | Metrics

    The design and implement of logical control and monitor system of the lower hybrid current drive (LHCD) system on HL-2A tokamak was present. The system was based on the SIEMENS S7-400 series PLC. The performance on anti-interference was increased by using the industrial ethernet network, optical fiber isolation, embedded controller technology. The interlocks, parameter setting and remote monitor were established. The lower hybrid wave was injected into HL-2A plasma with the logical control system. It shows the logical control system was successfully developed.

    A TBR optimization method of PWR water-cooled blanket based on temperature control mechanism
    QIU Yang, YAO Da-mao, ZHANG Jie, LIU Chang-le, GAO Xiang
    2017, 37(4):  475-481.  DOI: 10.16568/j.0254-6086.201704018
    Asbtract ( )   PDF (4533KB) ( )  
    References | Related Articles | Metrics

    Based on the DEMO case, a Tritium breeding rate (TBR) optimization method used in the design of the PWR water-cooled blanket concerning the temperature requirement of tritium production and thermal was presented. Two-dimensional blanket models were set up for the neutronics and thermal hydraulics calculations. As the basis of this research, the blanket neutron heat sink was primarily calculated using the blanket energy multiplication factor. Exploring the variation trend of TBR with the changing of blanket structural parameters based on temperature control mechanism was focused. At last, the optimized value of the blanket structural parameters was proposed.

    Non-Fusion Plasma Applications
    Effect of small admixtures of oxygen on the characteristics of argon and oxygen mixture discharge at atmospheric pressure
    WANG Yi-nan, JIN Xin, WANG Li, JIN Ying
    2017, 37(4):  482-488.  DOI: 10.16568/j.0254-6086.201704019
    Asbtract ( )   PDF (6347KB) ( )  
    References | Related Articles | Metrics

    Based on 1-D fluid Model, numerical simulation was adopted to study the effect of small admixtures of oxygen on the characteristics of argon and oxygen mixture discharge at atmospheric pressure. According to the model equations, the simulation results showed that as the ratio of oxygen to argon increased from 0.1% to 0.6%, the electron density decreased, the density of O? increased, the density of the total negative particles increased, the electron temperature in sheath decreased. Furthermore, with the increase of discharge time, the density of O? increased, the electron density was obviously divided into three stages: the stage of electron growth, the stage of electron reduction and the stage of electron unchanged. When the ratio of oxygen to argon was within the scope of 1%, the electron density decreased rapidly, the oxygen atom density increased quickly. However, when the ratio of oxygen to argon was between 1% and 4%, as the ration of oxygen to argon increased the electron density decreased slowly and the oxygen atom density grew slowly until held the line.