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1.
LUO Zhiren 《等离子体科学和技术》2015,17(6):510-516
The Vacuum Vessel(VV) system is a vital component of Keda Torus for experiment(KTX).Various accidental scenarios might occur on the VV.In this report,an extreme scenario is assumed and studied:plasma accidental termination during the flat-top stage.Numerical simulations based on finite element are performed as the major tool for analyses.The detailed distributions of eddy and the reaction forces on VV are extracted,and the total eddy current and the maximum reaction force due to electromagnetic load are figured out.In addition,according to the results,the VV can be approximately regarded as a centrally symmetric structure,even though its ports distribution is asymmetric. 相似文献
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利用数值模拟的方法,考察了树脂裂解反应器上部进气方式的效果,发现存在空气利用率低的问题,同时空气还会带走反应器内的大量热量,削弱树脂裂解反应区域的温度,由此证明了试验推论的正确性。同时,利用数值模拟的方法,对设备进气方式进行优化改进:当采用下部进气后,空气的利用率得到明显的提升,空气分布也较为均匀。但此时,空气对反应区域内温度的削弱作用也更为明显。此外,随着设备进气口直径的减小和进气口数量的增加,能够较为明显地提高树脂反应区域的空气分布均匀度,而提升设备的加热功率,对提高反应区域内的温度有显著的作用。 相似文献
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KTX(Keda Torus for eXperiment)is a new reversed field pinch device.The KTX plasma control system(PCS)can provide real-time,stable,flexible plasma control which is designed by ASIPP(Institute of Plasma Physics,Chinese Academy of Sciences),based on the Linux cluster system and EPICS(Experimental Physics and Industrial Control System)framework,and developed from DIII-D(Doublet III-D)PCS.The control of the equilibrium field in KTX uses a PID(Proportional-Integral-Derivative)feedback controller.The control of the gas injection is an open loop control.The plasma control simulation system is one part of the plasma control system,which is used to test the plasma control algorithm if it is revised and updated.The KTX PCS has been successfully tested using HT-7(Hefei Torus 7)experiment data in simulation mode.In the next phase,an error field feedback control and KTX simulator will be added to the KTX PCS,and the KTX PCS will be applied in experiments in the future. 相似文献
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LUO Bing 《等离子体科学和技术》2016,18(1):90-96
Radial equilibrium of the KTX plasma column is maintained by the vertical field which is produced by the equilibrium field coils.The equilibrium is also affected by the eddy current,which is generated by the coupling of copper shell,plasma and poloidal field coils.An equivalent circuit model is developed to analyze the dynamic performance of equilibrium field coils,without auxiliary power input to equilibrium field coils and passive conductors.Considering the coupling of poloidal field coils,copper shell and plasma,the evolution of spatial distribution of the eddy current density on the copper shell is estimated by finite element to analyze the effect of shell to balance.The simulation results show that the copper shell and equilibrium field coils can provide enough vertical field to balance 1 MA plasma current in phase 1 of a KTX discharge.Auxiliary power supply on the EQ coils is necessary to control the horizontal displacement of KTX due to the finite resistance effect of the shell. 相似文献
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The KTX device is a reversed field pinch(RFP)device currently under construction.Its maximum plasma current is designed as 1 MA with a discharge time longer than 100 ms.Its major radius is 1.4 m and its minor radius is 0.55 m.One of the most important problems in the magnet system design is how to reduce the TF magnetic field ripple and error field.A new wedgeshaped TF coil is put forward for the KTX device and its electromagnetic properties are compared with those of rectangular-shaped TF coils.The error field Bn/Btof wedge-shaped TF coils with6.4 degrees is about 6%as compared with 8%in the case of a rectangular-shaped TF coil.Besides,the wedge-shaped TF coils have a lower magnetic field ripple at the edge of the plasma region,which is smaller than 7.5%at R=1.83 m and 2%at R=1.07 m.This means that the tokamak operation mode may be feasible for this device when the plasma area becomes smaller,because the maximum ripple in the plasma area of the tokamak model is always required to be smaller than 0.4%.Detailed analysis of the results shows that the structure of the wedged-shape TF coil is reliable.It can serve as a reference for TF coil design of small aspect ratio RFPs or similar torus devices. 相似文献
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聚变堆包层第一壁是影响包层换热效率与运行安全性最重要的部件,为了研究第DEMO堆包层第一壁的热工水力性能,对第一壁流道内氦气冷却剂的流动及其与结构材料的换热进行了数值模拟研究及优化分析。结果表明,通过增大氦气进口质量流量可以有效地降低第一壁结构材料的最高温度,但是由此带来的压力损失很大,不能作为强化换热的主要途径。此外,增加每组流道的盘绕次数能起到强化换热的效果,目前每组流道盘绕五次的方案是合理的。流道中存在的圆角包层第一壁的流动换热影响不大,但圆角的存在会使第一壁最高温度有一定的升高。铍涂层的导热系数与第一壁最高温度成反相关关系,但是对第一壁流道的对流换热影响不大。结构材料的导热系数的增大能显著降低第一壁结构材料的最高温度。 相似文献
8.
Wei YOU 《等离子体科学和技术》2018,20(11):115601-115601
The design of the poloidal field (PF) system includes the ohmic heating field system and the equilibrium (EQ) field system, and is the basis for the design of a magnetic confinement fusion device. A coupling between the poloidal and plasma currents, especially the eddy current in the stabilizing shell, yields design difficulties. The effects of the eddy current in the stabilizing shell on the poloidal magnetic field also cannot be ignored. A new PF system design is thus proposed. By using a low-μ material (μ=0.001, ε=1) instead of a conductive shell, an electromagnetic model is established that can provide a continuous eddy current distribution on the conductive shell. In this model, a 3D time-domain problem with shells translates into a 2D magnetostatic problem, and the accuracy of the calculation is improved. Based on these current distributions, we design the PF system and analyze how the EQ coils and conductive shell affect the plasma EQ when the plasma ramps up. To meet the mainframe design requirements and achieve an efficient power-supply design, the position and connection of the poloidal coils are optimized further. 相似文献
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邬佳仁;兰涛;庄革;吴捷;毛文哲;陈晨;汪兴康;邓鹏;董期龙;周永康;王天雄;卢鹏程;柏泽琪;黄玉华;吴征威;卫子安;温晓辉;汪海;周楚;刘阿娣;谢锦林;李弘;丁卫星;刘万东 《等离子体科学和技术》2025,27(4):044005-1-044005-8
The electromagnetic turbulence in reversed field pinch (RFP) plasmas exhibits three-dimensional characteristics. Suppression of this turbulence is crucial for enhancing plasma confinement, necessitating control over the electric field or the current profile. To this end, two sets of electrodes have been designed and installed on the Keda Torus eXperiment (KTX) RFP device to manipulate the edge electric field and the edge parallel current profile. Subsequently, the edge radial electric field and edge parallel current profile control experiments are conducted. In the edge radial electric field control experiments, the edge radial electric field is altered under bias, accompanied with an increase in the electron density and plasma duration. However, under bias, both electrostatic and magnetic fluctuations are enhanced. In the edge parallel current profile control experiments, the results indicate that bias modifies the edge parallel current profile locally, leading to a localized increase in the field reversal depth and electron density. Additionally, a reduction in magnetic fluctuations is observed within the reversed field enhanced region under bias, suggesting that the bias suppresses magnetic perturbations. 相似文献
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Shanshuang Shi Yuntao Song Qingxi Yang Hao Xu Zhongwei Wang Wandong Liu Hong Li Shude Wan Weixing Ding Zhiren Luo Jinxing Zheng 《Fusion Engineering and Design》2013,88(12):3180-3184
KTX is a new reversed field pinch (RFP) magnetic confinement device which is under design in ASIPP and USTC. Major disruption (MD) events may occur in future operating process, which is simulated with the finite element (FE) method. The results present that the peaks of eddy currents on vessel and conductor shell are respectively 11.791 kA and 68.637 kA with maximum stress 67.1 MPa due to high transient electromagnetic (EM) force. It is confirmed that the structure is still strong enough to bear the electromagnetic loads even if the worst case. Besides, as KTX vacuum vessel will take the method of natural cooling for heat dissipation during plasma discharge (0.5–1.0 MA), a preliminary thermal calculation was implemented in normal condition to decide suitable time parameters such as duration and interval. It is suggested that the discharge interval should be no less than 5 min for the complete 1 MA plasma with 100 ms duration, which can guarantee the temperature of vacuum vessel below 200 °C. 相似文献
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KTX反场箍缩装置的主要参数介于RFX装置与MST装置之间。反场箍缩的外加纵场需跟随等离子体电流的演化而变化,同时由于RFP中的磁面对于外部特别是等离子体边界处的径向磁场较敏感,所以需外部线圈的磁场更加精细,这对于线圈的磁场分布、误差场以及波纹度等的设计提出了更高的要求。根据KTX物理目标参数要求,提出矩形和楔形截面纵场磁体线圈设计方案,借助有限元软件和程序分析了其电磁场空间分布和结构受力大小。结果表明,6.4°楔形截面方案相比矩形截面方案在控制误差场方面更具有可行性。 相似文献
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Yuanming Xie Tianda Yu Chaojun Deng Xuefei Hu 《Journal of Nuclear Science and Technology》2020,57(9):1074-1090
ABSTRACT In the lower chamber of pressurized water reactor (PWR), the flow distribution device is the core module to distribute coolant into the core. It has complex structure and numerous design parameters. Therefore, it has important theoretical and practical significance to optimize the device. The mesh independence verification, turbulence model selection, and data processing all can influence the numerical simulation results of the lower chamber, in order to research the influence, a numerical simulation method based on the original model of CNP1000 reactor lower chamber is proposed in this paper. In the method, an optimization design method of flow distribution device is established based on surrogate model. The main design variables and optimization objectives are determined based on the device’s structure and function characteristics. And then it respectively adopts Kriging algorithm and multi-objective genetic algorithm to establish a surrogate model of flow distribution device and optimize it globally. Finally, the optimal design variables are obtained. Compared with the device’s performance before optimization, the after optimization has smaller total pressure loss and more uniform flow. The effectiveness and practicability of proposed optimization design method can be verified. 相似文献
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Plasma Shape and Current Control Simulation of HT-7U Tokamak 总被引:1,自引:0,他引:1
This paper describoes the discharge simulation of HT-7U tokamak plasma equilibrium and plasma current by solving MHD equations and surface average transport equations using an equilibrium evolution code. The simulated result shows the evolution of plasma parameter versus time .The simulated result can play an important role in the design of the plasma equilibrium and control system of a tokamak. 相似文献
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The ITER neutron shielding blocks are located between the inner shell and the outer shell of the vacuum vessel (VV) with the main function of providing neutron shielding. Considering the combined loads of the shielding blocks during the plasma operation of the ITER, limit analysis for one typical ferromagnetic (FM) shielding block has been performed and the structural design has been evaluated based on the American Society of Mechanical Engineers (ASME) criterion and European standards. Results show that the collapse load of this shielding block is three times the specified load, which is much higher than the design requirement of 1.25. The structure of this neutron shielding block has a sufficient safety margin. 相似文献
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采用VOF方法及耦合表面张力模型的动量方程,结合UDF功能,模拟了竖直通道内静水中水平分布两气泡之间的相互作用以及摇摆对其运动特性的影响,详细分析了两气泡上升过程中出现的吸引及排斥现象。模拟所得两气泡上升时的形态变化过程与实验结果符合良好。结果表明,水平分布两气泡在水中会呈上下摇摆状上升,且位置关系变化具有周期性,摇摆会使气泡在上升过程变得更加扁平,两气泡所能达到的最小距离变小,但摇摆会破坏两气泡在上升过程其位置关系所具有的周期性。 相似文献
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通过对秦山核电厂系统回路的仿真试验分析,指出了其化容系统上充回路现有的几种设计方案所存在的缺陷,并分析了其对核电厂运行的可能影响,同时给出了一个可供参考的优化方案。 相似文献
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Yu-shi Tang Qiu-ju Guo Jian-zhu Cao Jie-juan Tong 《Journal of Nuclear Science and Technology》2017,54(9):991-1001
The modular pebble-bed nuclear reactor (PBR) is a candidate Generation IV reactor being developed. The pebble flow in the very slow draining of fuel pebbles draws attention for its implications on core physical design and reactor physics analysis. One of the effective and simplified methods to address this problem is the kinematic model which is based on continuous theory to derive a diffusion equation for vertical velocity. This paper investigates the appropriate numerical solutions for the kinematic model of pebble flow velocity profiles in PBR geometry. Our method is based on a previously proposed transformed Cartesian coordinates and uses the implicit Crank–Nicholson integration scheme with two different treatments of the boundary conditions. Validations show that this numerical solution gives preferable agreements with the experimental results in the reference. Finally, the simulated velocity profiles are applied in the investigation of two pebble burnup-related issues, which are the pebble residence time prediction and the channel scheme in realistic high-temperature reactor pebble-bed modules reactor core geometry. 相似文献
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加速器内电子束团在传输过程中因束流传输截面发散或偏离中心,会超出尺寸一定的传输器件.为防止因此导致扫描盒前端法兰盘局部温升过高,在法兰的外侧安装温度传感器以实时监测受照点的温度,从而及时调整系统的电流、电压、聚焦等有关参数.建立了法兰盘两侧热传导的数学模型,用数值模拟的方法计算得出了放置温度传感器的测量点B和受照点A的温度关系.计算结果与实验值符合,证明了数学模型的正确性,并为加速器的调试、运行提供了一种重要的检测手段. 相似文献