Recent ICRF coupling experiments on EAST

Recent ion cyclotron resonance frequency(ICRF) coupling experiments for optimizing ICRF heating in high power discharge were performed on EAST. The coupling experiments were focus on antenna phasing and gas puffing, which were performed separately on two ports of the ion cyclotron resonance heating(ICRH) system of EAST. The antenna phasing was performed on the I-port antenna, which consists of four toroidally spaced radiating straps operating in multiple phasing cases; the coupling performance was better under low wave number ∣k_‖∣(ranging from 4.5 to 6.5). By fuelling the plasma from gas injectors, placed as uniformly spaced array from top to bottom at each side limiter of the B-port antenna, which works in dipole phasing, the coupling resistance of the B-port antenna increased obviously.Furthermore, the coupling resistance of the I-port antenna was insensitive to a smaller rate of gas puffing but when the gas injection rate was more than a certain value(1021 s~(-1)), a sharp increase in the coupling resistance of the I-port antenna occurred, which was mainly caused by the toroidal asymmetric boundary density arising from gas puffing. A more specific analysis is given in the paper.     

CFETR氦冷固态包层设计及热工水力学分析

基于中国聚变工程实验堆(Chinese Fusion Engineering Testing Reactor,CFETR)提出了一种新型氦冷固态氚增殖包层设计方案。以托卡马克中平面上一块外包层模块为例,系统介绍了该包层概念设计。基于工程流体力学理论,对包层模块内冷却剂的流动特性进行了理论求解。同时采用计算流体动力学(Computational Fluid Dynamics,CFD)软件CFX,对包层模块流体域和固体域进行耦合传热分析,求解得到冷却剂的流动特性和理论计算难以求解的固体域温度场分布。计算结果表明:理论计算与模拟结果吻合程度良好,冷却剂在包层内总压降为243 k Pa,总温升为194.6°C,运行在合理区间;包层各结构材料在正常运行工况下的温度可以满足材料的最高温度限制要求,为该包层方案的进一步结构优化和安全分析提供参考。     

Thermal analysis and optimization of the EAST ICRH antenna

The ion cyclotron resonance of frequency heating(ICRH) plays an important role in plasma heating.Two ICRH antennas were designed and applied on the EAST tokamak.In order to meet the requirement imposed by high-power and long-pulse operation of EAST in the future,an active cooling system is mandatory to be designed to remove the heat load deposited on the components.Thermal analyses for high heat-load components have been carried out,which presented clear temperature distribution on each component and provided the reference data to do the optimization.Meanwhile,heat pipes were designed to satisfy the high requirement imposed by a Faraday shield and lateral limiter.     

液氮传导冷却型高温超导电流引线研制

80 A和200 A液氮传导冷却型高温超导(HTS)电流引线由铜引线段、中间过渡段和高温超导段组成,HTS热端采用液氮传导冷却,HTS冷端采用液氦传导冷却。铜引线段工作在室温到中间温度(~80 K),高温超导段工作温区6—80 K。介绍该传导冷却型电流引线的结构设计和低温性能测试。实验结果表明,中间过渡段温度~78 K,高温超导热端温度77 K;80 A、200 A电流引线液氦下稳态测试电流分别为100 A和250 A。     

ITER 10kA高温超导电流引线测试装置低温系统的研究

为ITER CC 10 kA高温超导电流引线服务的低温性能测试装置已研制完成,并成功运行。其低温系统主要由500W/4.5 K氦制冷机,真空杜瓦,低温组件(低温阀门,过冷槽,管道加热器,热防护层),汽化器及低温传输管线等部分组成。本文对真空杜瓦和过冷槽进行设计,并讨论该低温系统的冷却流程方案,最后通过电流引线10 kA稳态实验结果对低温系统的运行效果进行分析,结果表明该低温系统运行稳定,能满足ITER CC电流引线的测试需要。     

EASTICRF天线法拉第屏蔽的热-结构分析

在EASTICRF天线中,法拉第屏蔽是ICRF天线中的一个非常重要的部件。实验时,它位于真空室内直接面对等离子体,将承受着很大的热负荷。基于EASTICRF天线法拉第屏蔽结构的安全性,本文利用有限元的方法,首先对热负荷最大的法拉第屏蔽冷却管道在不同水流速下进行热分析,考察在不同水流速工况下法拉第屏蔽冷却管道上的温度分布情况,再通过热 结构耦合方法对法拉第屏蔽冷却管道进行结构分析,了解法拉第屏蔽在不同水流速下的应力大小和分布情况,分析结果为未来EASTICRF天线实验提供理论指导。另外,对法拉第屏蔽冷却管道结构进行了优化改进,并对优化改进后的法拉第屏蔽冷却管道在相同工况下进行了热和热 结构分析,分析结果确定了优化改进后的法拉第屏蔽冷却管道结构的优越性,分析数据为未来法拉第屏蔽冷却管道的优化改进提供理论指导,分析方法为其他同类装置提供有益的参考。     

一种应用于聚变堆的多层密封的设计与分析

遥操作系统的设计是中国聚变工程实验堆(CFETR)中的一个关键问题,其中遥操作车的密封结构设计在整个停堆维护过程中起着重要作用,它是保证操作者可以安全、可靠和可重复性执行针对不同维护对象的维护任务的前提。文中首先介绍了CFETR遥操作转运车以及双密封门的设计,针对多层密封的特点进行了优化改进;然后对密封圈的选材做了分析,并详细计算了所需密封力的大小,根据结果选择硬度50HS的氟橡胶作为密封圈材料;最后设计了检漏的方案,对泄露情形做了分析,计算了压降和随时间变化关系,结果满足操作时间要求和系统安全要求。     

A Consideration on Increasing Current Density in Normal Conducting Toroidal Field Coil for Spherical Tokamak Power Plant

The center post is the most critical component as an inboard part of the toroidal field coil for the low aspect ratio tokamak. During the discharge it endures not only a tremendous ohmic heating owing to its carrying a rather high current but also a large nuclear heating and irradiation owing to the plasma operation. All the severe operating conditions, including the structure stress intensity and the stability of the structure, largely limit the maximum allowable current density. But in order to contain a very high dense plasma, it is hoped that the fusion power plant system can operate with a much high maximum magnetic field BT ≥12 T-15 T in the center post. A new method is presented in this paper to improve the maximum magnetic field up to 17 T and to investigate the possibility of the normal conducting center post to be used in the future fusion tokamak power plant.     

托卡马克真空室内窥机器人的运动学仿真

托卡马克真空室内窥机器人主要用于携带摄像器材近距离观测托卡马克真空室第一壁的状况。基于EAST平台,设计了一种弧形关节臂托卡马克真空室内窥机器人;接着在已建立的机器人运动学正解和反解算法基础上,根据机器人不同工作位置,分别采用"点到点"和连续路径规划方法对机器人末端轨迹进行规划;最后整合轨迹规划数据,并将其导入ADAMS中实现真空室垂直断面扫描过程的仿真,得到机器人各关节的角位移,角速度,角加速度以及关节力矩随时间变化曲线,且曲线光滑连续。     

Design of the Cryostat for HT—7U superconducting Tokamak

The cryostat of HT-7U tokamak is a large vacuum vessel surrounding the entire basic machine with a cylindrical shell,a dished top and a flat bottom.The main function of HT-7U cryostat is to provide a thermal barrier between an ambient temperature test hall and a liquid helium-cooled superconducting magnet.The loads applied to the cryostat are from sources of vacuum pressure,dead weight,seismic events and electromagnetic forces originated by eddy currents.It also provides feed-through penetrations for all the conecting elements inside and outside the cryostat.The main material selected for the cryostat is stainless steel 304L.The structural analyses including buckling for the cryostat vessel under the plasma operation condition have been carried out by using a finite element code.Stress analysis results show that the maximum stress intensity was below the allowable value.In this paper,the structural analyses and design of HT-7U cryostat are emphasized.