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KSTAR vacuum vessel thermal shield analysis KSTAR真空容器热屏蔽分析
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027720
S. Cho, D. L. Kim, N. Her, K. Im, M. Kwon, G. S. Lee, B. J. Yoon, S. In
The KSTAR Vacuum vessel thermal shield is composed of multilayer insulation (MLI), cryopanel and supports. One of the major design parameters for the design of thermal shield cryopanel and supports is the eddy current induced during plasma disruption. The eddy current creates joule heating as well as electromagnetic (EM) loads combining with magnetic fields. Since the cryopanel should be maintained at a cryogenic temperature lower than 80 K, even a small amount of joule heating may play an important role in increasing the cyropanel temperature. Also the EM loads are very critical mechanical forces for the design of structure of the thermal shield, especially for the supports. Joule heating and EM loads on the vacuum vessel thermal shield during plasma disruption were calculated to provide the design requirement of the thermal shield. Based on the joule heating and EM loads, the structural and thermal stress analyses were performed for the assessment of the structural robustness of the vacuum vessel thermal shield. It was found that the effect of joule heating on the thermal shield design is minimal, but the EM loads are important for the design of cryopanel as well as supports. The optimal number and size of supports were determined.
KSTAR真空容器隔热罩由多层隔热层(MLI)、低温板和支架组成。热屏蔽低温板和支架设计的主要参数之一是等离子体破坏时产生的涡流。涡流产生焦耳加热以及与磁场结合的电磁(EM)负载。由于低温板应保持在低于80k的低温下,即使少量的焦耳加热也可能对提高低温板温度起重要作用。电磁载荷是热屏蔽结构设计中非常重要的机械力,特别是对支架的设计。计算了等离子体破坏过程中真空容器热屏蔽层的焦耳加热和电磁载荷,给出了热屏蔽层的设计要求。基于焦耳加热和电磁载荷,进行了结构和热应力分析,以评估真空容器热屏蔽结构的鲁棒性。研究发现,焦耳加热对热屏蔽设计的影响很小,但电磁载荷对低温板和支架的设计至关重要。确定了支架的最优数量和尺寸。
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引用次数: 0
Web interfaces to MDSplus data MDSplus数据的Web接口
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027670
W. Davis, P. Roney, T. Carroll, T. Gibney, D. Mastrovito
The MDSplus Data Acquisition System has been used successfully on NSTX at PPPL since early 1999. While the X-Window-based tools supplied with MDSplus are powerful, and both the IDL programming language and the supplied TDI language are effective for complex and specialized analyses, some users prefer the convenience of applications that can be run in a Web browser. Web users do not need to know about X-Windows, or even have accounts or privileges on server computers. The MDSplots page reads MDSplus "Scope" setup files and plots MDSplus signals with overlays. It uses a Perl script to open a pipe to an IDL subprocess. The TreeSearch page provides several options for finding information in MDSplus trees. The MDSshots page lists shots where the maximum for a specified signal is above or below a specified value. A variety of information in an MS-SQL database is also accessible from a Web browser. These utilities could be used at other sites which keep data in MDSplus.
MDSplus数据采集系统自1999年初以来已在PPPL的NSTX上成功使用。虽然MDSplus提供的基于x - windows的工具功能强大,而且IDL编程语言和提供的TDI语言对于复杂和专门的分析都是有效的,但是一些用户更喜欢可以在Web浏览器中运行的应用程序的便利性。Web用户不需要了解X-Windows,甚至不需要在服务器计算机上拥有帐户或特权。MDSplots页面读取MDSplus“Scope”设置文件并使用覆盖绘制MDSplus信号。它使用Perl脚本打开通往IDL子进程的管道。tresearch页面提供了在MDSplus树中查找信息的几个选项。mdshots页面列出了指定信号的最大值高于或低于指定值的快照。MS-SQL数据库中的各种信息也可以通过Web浏览器访问。这些实用程序可以在MDSplus中保存数据的其他站点上使用。
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引用次数: 2
Engineering design study of JT-60 superconducting modification JT-60超导改性的工程设计研究
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027680
A. Sakasai, S. Ishida, M. Matsukawa, G. Kurita, N. Akino, T. Ando, T. Arai, H. Ichige, A. Kaminaga, T. Kato, K. Kizu, K. Masaki, Y. Miura, Y. Miyo, A. Morioka, S. Sakurai, T. Sasajima, S. Takeji, H. Tamai, K. Tsuchiya, K. Urata, J. Yagyu, K. Tobita, H. Takenaga, K. Shimizu, M. Kikuchi
The modification of JT-60 is planned as a fully superconducting tokamak (JT-60SC). The mission of JT-60SC program is to establish scientific and technological bases for an advanced operation in an economically and environmentally attractive DEMO reactor and ITER. The research objectives are to accomplish high performance steady state operation with high beta and non-inductive full current drive, with high bootstrap current fraction, and demonstrate the plasma applicability of reduced-activation material for a plasma of break-even class relevant to the reactor plasma. Basic design of JT-60SC has been completed and the detailed design is under way. The engineering design for main components of JT-60SC is described.
JT-60的改造计划成为一个完全超导的托卡马克(JT-60SC)。JT-60SC计划的任务是为经济和环境具有吸引力的演示反应堆和ITER的先进运行建立科学和技术基础。研究目标是实现高β和无感全电流驱动、高自举电流分数的高性能稳态运行,并证明降低活化材料对与反应堆等离子体相关的盈亏平衡级等离子体的等离子体适用性。JT-60SC的基本设计已经完成,详细设计正在进行中。介绍了JT-60SC主要部件的工程设计。
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引用次数: 9
Synchronous rectifier using power-MOSFET for high current AC/DC converter system 大功率mosfet同步整流器用于大电流AC/DC变换器系统
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027647
T. Matsukawa, Masanori Shioyama, J. Nomura, C. Neumeyer, S. Tsuji-Iio, R. Shimada
To supply high DC current to a single turn toroidal field coil of a spherical torus machine, it is an important engineering aspect that the operational losses should be minimized for the power supply system. As a switching element of an AC/DC converter, instead of a thyristor or diode, a power-MOSFET is a desirable component to be applied to a high current power supply system. The lowered resistance of parallel connected and pre-cooled power-MOSFET elements makes it possible to reduce the AC/DC converter power supply system losses. To output high DC current in one direction, the synchronous rectifier type AC/DC converter with parallel connected power-MOSFET elements is proposed as the power supply system for single turn toroidal field coil.
为球面电机的单匝环面磁场线圈提供高直流电流,使供电系统的运行损耗最小化是一个重要的工程方面。功率- mosfet作为AC/DC转换器的开关元件,代替晶闸管或二极管,是应用于大电流供电系统的理想元件。并联和预冷功率- mosfet元件的电阻降低使得降低AC/DC转换器供电系统的损耗成为可能。为了在一个方向上输出大的直流电流,提出了一种功率- mosfet并联的同步整流型AC/DC变换器作为单匝环形场线圈的供电系统。
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引用次数: 7
Towards real time control of the internal transport barriers on JET 面向JET内部传输障碍的实时控制
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027679
M. Riva, D. Mazon, R. Felton, X. Litaudon, G. Tresset, A. Becoulet, J. Chareau, S. Dalley, S. Dorling, E. Joffrin, D. Moreau, M. Lennholm
Recently a local criterion characterising the emergence and space-time evolution of internal transport barriers (ITB) has been proposed and extensively validated on the large JET database. It was shown that a dimensionless local parameter, /spl rho//spl dot/(T/sub e/) =/spl rho//sub s//L(T/sub e/) characterises with a low computational cost the typical ITB features such as the emergence time, location, collapse time and dynamics [/spl rho//sub s/ is the local Larmor radius and L(T/sub e/) is the temperature gradient scale length L(T/sub e/)=-T/sub e//(/spl part/T/sub e///spl part/R)]. We report on the recent implementation of the calculation of the ITB criterion together with the associated feedback algorithms in the real time system of JET. The system purpose is to acquire all the analogue channels of the high space resolution electron temperature ECE diagnostic (heterodyne radiometer) and to calculate in real time the relevant ITB parameters which am used for the control: the maximum value of the dimensionless local temperature gradient, the ITB radius and width, the core and volume averaged electron temperature.
近年来,研究人员提出了一种表征内部输运障碍(ITB)出现和时空演化的局部判据,并在大型JET数据库上进行了广泛验证。结果表明,无量纲局部参数/spl rho//spl dot/(T/sub e/)= /spl rho//sub s//L(T/sub e/)以较低的计算成本表征了典型的ITB特征,如出现时间、位置、坍缩时间和动力学[/spl rho//sub s/为局部Larmor半径,L(T/sub e/)为温度梯度尺度长度L(T/sub e/)=-T/sub e//(/spl part/T/sub e///spl part/R]。本文报道了在JET实时系统中ITB准则的计算及其相关的反馈算法的最新实现。该系统的目的是获取高空间分辨率电子温度ECE诊断(外差辐射计)的所有模拟通道,并实时计算用于控制的相关ITB参数:无因次局部温度梯度的最大值,ITB半径和宽度,核心和体积平均电子温度。
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引用次数: 2
The Alcator C-Mod lower hybrid current drive experiment low power microwave and active control system alcatator C-Mod低混合电流驱动实验,低功率微波和主动控制系统
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027633
D. Terry, W. Burke, M. Grimes, D. Gwinn, J. Irby, N. Kambouchev, R. Parker, P. Woskov
A 3 MW (upgradeable to 4 MW) 4.6 GHz Lower Hybrid Current Drive (LHCD) system is being implemented on Alcator C-Mod to control and sustain current profile evolution. The LHCD low-power microwave and active control system, using fast vector modulators, will provide a phase and amplitude controlled driver for each of twelve 4.6 GHz, 250 kW klystrons. Resulting phase and power outputs of each klystron will be monitored by I-Q detectors and made available for closed-loop control of the klystron phase and amplitude during plasma shots. Synchronized digital controllers will be implemented for each control loop and operation will be coordinated with external fast protection circuitry provided in the LHCD transmitter and coupler protection systems.
一个3mw(可升级到4mw) 4.6 GHz低混合电流驱动(LHCD)系统正在Alcator C-Mod上实施,以控制和维持电流剖面的演变。LHCD低功率微波和主动控制系统,使用快速矢量调制器,将为12个4.6 GHz, 250 kW速调管中的每一个提供相位和幅度控制驱动器。每个速调管的相位和功率输出将由I-Q探测器监测,并可用于等离子体射击期间速调管相位和幅度的闭环控制。同步数字控制器将用于每个控制回路,操作将与LHCD发射机和耦合器保护系统中提供的外部快速保护电路协调。
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引用次数: 4
Engineering status and plans for the Fusion Ignition Research Experiment (FIRE) 聚变点火研究实验(FIRE)工程现状与规划
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027698
P. Heitzenroeder, R. Thorne
The FIRE project is being pursued as a possible option for the next step in the US magnetic fusion energy program. Its goal is to develop a compact, high field, highly shaped tokamak with the following parameters: major radius, R, of 2.14 m: minor radius, a, of 0.595 m.: a toroidal field on axis of 10 T; a plasma current of 7.7 MA, a flat top time of approximately 20 s, and fusion power of 150 MW. FIRE utilizes liquid nitrogen pre-cooled copper TF and PF magnets. An important goal is a project cost of approximately $1.2B. Initial cost estimates have been produced which indicate FIRE can achieve this cost goal. More detailed cost estimates are planned in FY 02. This paper will give an overview of FIRE's design. discuss the most significant design choices and the background for these choices, and summarizes FIRE's cost estimates and R&D plans.
FIRE项目是美国磁聚变能源计划下一步的一个可能选择。其目标是开发一个紧凑,高场,高形状的托卡马克,具有以下参数:大半径R为2.14 m,小半径a为0.595 m,轴为10t的环面场;等离子体电流为7.7毫安,平顶时间约为20秒,聚变功率为150兆瓦。FIRE采用液氮预冷铜TF和PF磁铁。一个重要的目标是项目成本约为12亿美元。初步的成本估算表明FIRE可以达到这个成本目标。更详细的成本估算计划在02财年进行。本文将对FIRE的设计进行概述。讨论了最重要的设计选择和这些选择的背景,并总结了FIRE的成本估算和研发计划。
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引用次数: 1
Tritium behavior on SiC 氚在SiC上的行为
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027667
K. Katayama, M. Nishikawa, T. Takeishi
SiC (silicon carbide) has been considered as one of the primary candidate materials for a first wall component in a future fusion reactor because it has been claimed that SiC has excellent high temperature properties and low activation. However, the behavior of tritium on SiC has not been discussed yet. In this study, the tritium trapping capacity on the surface of SiC is experimentally obtained as about 10/sup 10/ Bq/m/sup 2/ at the temperature range of 298K- 1073K in consideration of the static system effect. It is also observed that tritium is trapped to the surface through hydrogen isotope exchange reaction. The isotope exchange reaction rate between tritiated water in a gas phase and hydrogen on the surface is quantified at the temperature of 298K, 773K, 973K in consideration of the kinetic system effect by the numerical curve fitting method applying the serial reactor model. The reaction rate is observed to be constant at 3.48 /spl times/ 10/sup -5/ m/s. The comparison of tritium properties of SiC with that of graphite or stainless steel is also discussed.
SiC(碳化硅)被认为是未来核聚变反应堆第一壁组件的主要候选材料之一,因为它具有优异的高温性能和低活化性。然而,氚在碳化硅上的行为尚未得到讨论。在本研究中,在298K- 1073K温度范围内,考虑到静态体系效应,实验得到SiC表面的氚捕获容量约为10/sup 10/ Bq/m/sup 2/。还观察到氚通过氢同位素交换反应被捕获到表面。考虑动力学系统效应,采用串联反应器模型,采用数值曲线拟合的方法,量化了298K、773K、973K温度下气相氚化水与表面氢的同位素交换反应速率。观察到反应速率恒定在3.48 /spl次/ 10/sup -5/ m/s。并对碳化硅与石墨、不锈钢的氚性能进行了比较。
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引用次数: 0
Design of the National Compact Stellarator Experiment (NCSX) core 国家紧凑型仿星器实验(NCSX)核心设计
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027696
B. Nelson, L. Berry, A. Brooks, T. Brown, M. Cole, J. Chrznowski, F. Dahgren, H. Fan, P. Fogarty, P. Goranson, P. Heitzenroeder, S. Hirshman, G. Jones, J. Lyon, H. Neilson, D. Strickler, W. Reiersen, D. Williamson
The design status of the stellarator core for the National Compact Stellarator Experiment (NCSX) is presented. The purpose, configuration, and possible manufacturing and assembly techniques of the various components of the core are described.
介绍了国家紧凑型仿星器实验(NCSX)仿星器核心的设计现状。描述了该核心的各种组件的用途、配置以及可能的制造和组装技术。
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引用次数: 0
Disruption load calculations using ANSYS transient electromagnetic simulations for the Alcator C-Mod antennas 利用ANSYS瞬变电磁仿真计算alcater C-Mod天线的干扰载荷
IF 0.4 1区 艺术学 Q3 Arts and Humanities Pub Date : 2002-11-07 DOI: 10.1109/FUSION.2002.1027634
P. Titus
ANSYS has been used to compute eddy current loads in C-Mod antenna components due to a disruption. The antennas are on the outboard mid-plane, away from the direct involvement with halo currents, which characterize loading in the inner divertor and wall. Only inductively driven currents are computed. A rather complex but manageable electromagnetic model is used. Three of the antennas used in C-Mod were analyzed, Lower Hybrid, ICRH, and MHD antennas. The goal of these simulations was principally to quantify upper bound disruption loads.
利用ANSYS计算了C-Mod天线因断裂而产生的涡流载荷。天线位于外侧平面的中间,远离直接参与的光晕电流,光晕电流表征了内部导流器和壁的负载。只计算感应驱动电流。使用了一个相当复杂但易于管理的电磁模型。分析了C-Mod中使用的三种天线:低混合天线、ICRH天线和MHD天线。这些模拟的目的主要是量化破坏载荷的上限。
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引用次数: 6
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