Table of Content

15 March 2022, Volume 42 Issue 1

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Nuclear Fusion Engineering

Design and analysis on the HL-2M divertor cooling system

MENG Jian-peng, XIE Yan-feng, CAO Cheng-zhi, LI Qiang, LU Yong, ZHA Fang-zheng

2022, 42(1):  1-7.  DOI: 10.16568/j.0254-6086.202201001

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The equivalent three-dimensional model of the HL-2M divertor water-cooling flow channel was established. The temperature and pressure drop of the cooling water system load were simulated. A one-dimensional fluid model of the cooling system was constructed, and its hydraulic parameters were analyzed. Compared with the simulation results, the results were in good agreement.

Research of electrical braking system of 300MVA motor generator on HL-2M tokamak 

PENG Jian-fei, LIAO Chao, XUAN Wei-min, WANG Hai-bing, LI Hua-jun, PU Ming-nan, XU Li-rong, HU Hao-tian, SHI Ying-tian

2022, 42(1):  8-13.  DOI: 10.16568/j.0254-6086.202201002

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The electric braking system of 300MVA motor generator (MG) adopts the operation mode of 
combining electric braking and mechanical braking to rapidly shutdown the MG in case of frequent start-stop and 
major failure. The specific characteristics of the MG electrical braking system is introduced, and the electrical 
braking system of six-phase synchronous MG is analyzed theoretically and its' main circuit and control scheme is 
given. Based on the verified generator model, the dynamic simulation of the electric braking process of the unit 
under normal and extreme working conditions is carried out, and the main design parameters are determined, with 
the braking excitation voltage and braking resistance being 40V and 0.1Ω, respectively. 


Microstructure and mechanical properties of Fe-B-Si amorphous brazed W/CLF-1 steel joint

WANG Jian-bao, LIAN You-yun, FENG Fan, CHEN Zhe, LIU Xiang, WANG Ying-ming, QIANG Jian-bing

2022, 42(1):  14-19.  DOI: 10.16568/j.0254-6086.202201003

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Fe75B16.67Si8.33 amorphous alloy was prepared with arc melting, and the W/RAFM steel joint was obtained with vacuum brazing. Through the characterization of surface morphology, microstructure, composition, and mechanical properties, it is found that the brazing joint obtained under the condition of keeping the temperature at the 1250^oC for 10 minutes does not have macro-holes and cracks, Fe solid solution, Fe₃B and FeWB intermetallic compounds are formed in the joint structure, and the tensile strength is as high as 450MPa. 

Tritium transport analysis for ITER HCCB TBS during pulse operating

LI Ru-yan, WANG Xiao-yu, ZHANG Long, WANG Jun

2022, 42(1):  20-27.  DOI: 10.16568/j.0254-6086.202201004

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The dynamic tritium transport forChinahelium coolant ceramic breeder test blanket system (HCCB TBS) under ITER pulse condition was analyzed, an integrated dynamic tritium analysis tool was developed using Modelica language. The dynamic changes of tritium concentration and partial pressure in fluid, tritium inventory in solid, and tritium permeation flux under pulse operation and continuous operation were compared. The typical characteristics for tritium dynamic transport of system-level in TBS under pulse operation was consistent with that of the physical analysis result.

Thermal hydraulic analysis for ITER enhanced heat flux first wall of pipe joint assembly type 

WU Jing, CHEN Ji-ming, WANG Ping-huai, WANG Zheng-yu, KANG Wei-shan, GAO Hui

2022, 42(1):  28-34.  DOI: 10.16568/j.0254-6086.202201005

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Thermal hydraulic analysis for ITER enhanced heat flux (EHF) first wall (FW) of standard finger pair, edge finger pair and central beam (CB) of pipe joint assembly type is carried out. Analysis results show that the velocity distribution is reasonable and regions where coolant velocity is lower than 1m·s^-1 or higher than 10m·s^-1 are very small, mass flow distribution between finger pairs is rather reasonable, and the pressure drop for whole EHF FW is 0.351MPa lower than 0.4MPa, the limited value. The maximum temperature of CB during 8 burn and dwell cycles is about 409.21℃ within the allowable value of 450℃, however, the highest temperature in the sharp corner region of beryllium armor on the edge finger is 846.54℃, which requires high heat load experiment to verify its safety.

Study on surface fitting algorithm applied in manufacturing of CFETR vacuum vessel

FAN Xiao-song, , JI Hai-biao, GU Yong-qi, LIU Zhi-hong, WU Jie-feng, MA Jian-guo

2022, 42(1):  35-38.  DOI: 10.16568/j.0254-6086.202201006

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To solve the problems of manufacturing errors in the manufacturing process and asymmetrical structure of future fusion reactor vacuum vessel, the surfaces of vacuum vessel are meshed, and least squares method is improved with introducing weight factor. Numerical results show that the contour accuracy is improved and overall errors are reduced.

Research of manufacturing technology of 316LN U-shaped clamp for ITER magnet supports

KANG Dao-an, LI Peng-yuan, SUN Zhen-chao, ZHANG Teng, HAN Shi-lei, ZHAO Xiao-guang

2022, 42(1):  39-44.  DOI: 10.16568/j.0254-6086.202201007

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 Dimensional accuracy and mechanical properties for U-shaped supporting clamps for ITER magnet support (PFCS2), fabricated with the welding process and the integral ring forging plus wire-electrode cutting process respectively, were studied. The final dimension of U-shaped clamp, manufactured by double-sided TIG welding and single-sided TIG welding of components with the help of various auxiliary tools and heat treatment, can be controlled within the required range, but the impact of the welds at 77K is less than 100J. By adopting the integral ring forging plus slot wire-electrode cutting process, the opening size and slot size of the U-shaped clamp can meet the tolerance requirements, meanwhile, the consistency of the material properties is guaranteed, and the mechanical properties of the U-shaped clamp are improved. The integral ring forging plus wire-electrode cutting process is finally recognized by ITER International Organization (IO) as the mass production method for U-shaped clamps.

Study on properties of silver solid lubrication coatings with a nickel intermediate layer

LUO Rong-rong, LI Peng-yuan, ZHANG Teng, DAN Min

2022, 42(1):  45-50.  DOI: 10.16568/j.0254-6086.202201008

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The properties of silver lubricating coating deposited on nickel-based alloy with and without nickel (Ni) intermediate layer were compared. The results show that the grain size of the silver coating with nickel (Ni) intermediate layer becomes smaller, the micro strain and lattice parameter have no obvious changes, the surface of the prepared coating is denser and the defects are reduced. After 50 cycles of thermal shock between 77~300K, the coating surface has good thermal shock resistance and no cracks and spalling phenomena. The friction and wear test results of the two coatings under normal temperature atmosphere, normal temperature vacuum and -100°C vacuum show that the nickel intermediate layer increases the bonding performance between the substrate and the coating, improves the friction and wear performance of the silver self-lubricating coating, and the main wear is adhesive.

Preliminary design and analysis of coil terminal box of CFETR PF feeder system

WEI Hui-xiang, LI Ren-jie, LI Cheng, XU Zhuang, WANG Wen-shan

2022, 42(1):  51-55.  DOI: 10.16568/j.0254-6086.202201009

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The design of the coil terminal box (CBT) of poloidal field (PF) feeder system of China Fusion Engineering Test Reactor (CFETR) is introduced. The CBT is mainly composed of external box body, internal cooling screen of 80K, current lead and superconducting bus, internal pipeline system, valve system and other sub-components. Using ANSYS finite element software, the structural strength check, structural thermal analysis and seismic response analysis of CTB external box body and internal cold screen are carried out under system operation and seismic conditions. Therefore the cloud map of displacement and stress distribution of CTB external box body and the peak response under earthquake load are obtained. The results show that the maximum deformation and the maximum stress of CTB outer box are kept within the allowable range, meet the seismic requirements.

Preliminary design of ITER Langmuir probe measurement and control system for divertor plasma

CHEN Xiang, ZHAO Li, WEI Ling-feng, WANG Ya-li, JIANG Fu-qiang, ZHAO Wei, NIE Lin

2022, 42(1):  56-62.  DOI: 10.16568/j.0254-6086.202201010

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According to the measurement requirements of ITER Langmuir probe system and the design specifications of CODAC (Control, Data Access and Communication) system, the preliminary design of the instrument and control system was carried out. The design model of Langmuir probe system was established on Enterprise Architect (EA) platform. Referring to the automatic operation and control process, the layered design of the process in plasma discharge mode was completed. The preliminary design of probe system was finished, whose hardware and software architectures conform to the ITER control, data acquisition and probe drive power management, and the cabinet health monitoring and communication specification, and meet the requirement of integration with the ITER central control system.

Plasma Physics

Numerical calculation of plasma response to RMP for HL-2M tokamak

CHEN Hai-tao, HAO Guang-zhou, LIU Yue-qiang, ZHOU Li-na, CHEN Qian, DUAN Xu-ru

2022, 42(1):  63-70.  DOI: 10.16568/j.0254-6086.202201011

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Using the toroidal single-fluid code MARS-F, the plasma response to the phase difference of the resonance magnetic perturbation (RMP) field coil currents is studied in HL-2M equilibrium configuration (I_p=1.0MA, β_N=1.62, q₉₅=4.01). At the optimal phase difference, the perturbing magnetic field significantly changes the topology of the magnetic field in the boundary layer, forms obvious magnetic island chains, increases the transport of plasma in the layer, and reduces the pressure gradient and the drive to the ELM. The optimal phase differences are about 180°, 150° and -30° for the n=1, 2 and 4 toroidal modulus of the disturbance fields, , respectively.

Electron energy distribution function measurements in LEAD helicon plasma

ZHU Yu-xuan, NIE Lin, XU Min, LIU Hao, , WANG Hua-jie, CHEN Yi-hang, WANG Chen-yu, KE Rui, WANG Zhan-hui, HU Shi-lin, LI Bing-li, GONG Shao-bo, YUAN Jin-bang, YAN Yi-fan, LONG Ting, YU Yi, WU Ting

2022, 42(1):  71-76.  DOI: 10.16568/j.0254-6086.202201012

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The voltage-current characteristics and electron energy distribution function (EEDF) of helicon plasma measured by a voltage swept probe in Linear Experimental Advanced Device (LEAD) are presented. The profiles of some basic plasma parameters, such as electron temperature, density, plasma potential and sheath potential coefficient are given. It is shown that the EEDFs within a radius of 5cm conform to Maxwell distribution. However, the EEDF at the radius of 7cm which is the same as that of the RF antenna has a bi-Maxwellian distribution. This will affect some traditional measurements based on Maxwellian EEDF. 

Design and prototype development of the nonlinear electronic load simulating the current-voltage characteristics of Langmuir probe

WANG Ya-li, ZHAO Wei, NIE Lin

2022, 42(1):  77-83.  DOI: 10.16568/j.0254-6086.202201013

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A set of nonlinear electronic load simulating the current-voltage characteristics of Langmuir probe was developed, which was mainly composed of the cascade H-bridge converter with carrier phase-shifted sinusoidal pulse width modulation technique (CPS-SPWM) and the bidirectional DC/DC convertor. Simulation results and the preliminary test results of the prototype were shown that the system basically meets the expected requirements and can be used for testing the relevant parameters of the probe power supply and joint debugging the probe back-end electronics system.

Development of an electron density fringe jump correction program for the polarimeter-interferometer diagnostics system on EAST

WANG Yun-fei, , LIU Hai-qing, JIE Yin-xian

2022, 42(1):  84-90.  DOI: 10.16568/j.0254-6086.202201014

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A program is developed to correct the electron density fringe jump data by analyzing and summarizing the law of the electron density signals measured by the polarimeter-interferometer (POINT) diagnostics system on EAST. The results show that most electron density fringe jump signals can be effectively corrected with this program.

Influence of CFETR blanket equivalent resistivity on the growth rate of plasma vertical displacement

CHEN Dong, YE Min-you, MAO Shi-feng, CHEN Shu-liang, LI Hang, HUANG Tai-hao

2022, 42(1):  91-96.  DOI: 10.16568/j.0254-6086.202201015

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基于CFETR工程设计，使用TOKSYS建立了CFETR极向场线圈、真空室壁和包层结构的等效二维模型。在三种平衡的等离子体位形下，分析了包层结构整体等效电阻率和极向不同位置的等效电阻率对等离子体垂直位移增长率的影响。结果表明，垂直位移增长率随着包层整体等效电阻率的增加近似线性增大；降低极向±60°附近的等效电阻率，能减小垂直位移增长率。