ITER过渡馈线辅助支撑结构设计及传热计算

过渡馈线系统是为ITER磁体系统提供能量、制冷剂、进行测量诊断等服务的子系统。本工作对过渡馈线直线段内部辅助支撑和S弯箱内部辅助支撑等进行了设计,并借助ANSYS有限元分析软件[JP2]对过渡馈线直线段内管由辅助支撑引起的传导热进行了分析。结果表明,辅助支撑结构的设计是合理的。     

ITER磁体过渡馈线的结构设计与优化

国际热核聚变实验堆ITER(Intemational Thermonuclear Experimental Reactor)是正在进行的一项大型国际合作项目.磁体过渡馈线是保证磁体正常工作的重要通道.本文对磁体过渡馈线系统各组件结构进行了设计,利用有限元软件对结构作了初步分析和结构优化.结果表明:现有结构完全满足设计要求;通过对现有结构进行优化,如增设横向筋板、L型加强板,简化超导电流传输线(Busbar)的弯曲结构等,可以达到降低成本、简化结构的目的.     

ITER校正场磁体馈线结构分析

基于ANSYS对ITER校正场磁体馈线的结构进行了分析。根据馈线结构特点,对有限元模型进行了简化。通过电磁分析,获取了超导母线的电磁力,研究了电磁力与超导母线支撑间距的关系,并根据结果提出了推荐的支撑间距。在进行馈线模型结构分析时,电磁力按支反力的形式施加,并施加不同的载荷工况,获取了不同工况下馈线的应力及变形数据。分析结果显示馈线结构设计是合适的,满足设计应力准则要求。     

ITER超导纵场线圈内馈线系统冷却过程分析

国际热核聚变实验堆（ITER）超导纵场线圈内馈线系统位于主机杜瓦内,由18个盒体分别悬挂于相应纵场磁体终端,通过连接件组成多边形环。在装置降温过程中,内馈线与磁体冷却收缩的不同步导致相邻盒体环向端面发生相对位移,这要求连接件具有位移补偿功能。通过对内馈线收缩过程的研究,采用有限元分析法对内馈线稳态及瞬态温度场进行数值模拟,得到内馈线的热负荷值、温度及热应力分布、温度及变形的时间历程曲线,结果证明,内馈线无需主动冷却且热负荷小,热应力对结构强度影响小。研究结果同时为具有补偿功能连接件的设计提供了初步参数。     

线圈终端盒的改进设计与分析

为满足美国GA公司中心螺线管线圈模型CSM低温电性能测试的需要,基于ITER馈线系统的设计,对线圈终端盒壳体进行了修改设计。采用直立圆筒结构代替横卧立方体结构,优化了壳体安装工艺,提高了空间利用率。在此基础上,对线圈终端盒内部其他部件进行了相应的改进设计,最终实现了线圈终端盒的功能。利用大型有限元分析软件ANSYS对线圈终端盒壳体作弹性应力分析、屈曲分析及地震分析,并将屈曲分析结果与理论计算结果进行了对比。计算分析结果表明,直立圆筒结构形式的线圈终端盒设计合理可靠。     

ITER纵场磁体过渡馈线结构力学分析

运用数值方法计算了不同等离子体运行时刻纵场磁体过渡馈线(CFT)超导母线上的电磁载荷,并确定了磁感应强度最大的时刻,采用增量有限元法对过渡馈线进行非线性力学分析,得到不同工况下结构上的应力分布及变形情况。分析结果表明,带有万向节的过渡馈线结构具有足够的强度来承受运行过程中的各种载荷,从而证明了结构设计的合理性。     

200MW核供热站SPDS及其设计技术

描述了２００ＭＷ低温核供热站ＳＰＤＳ系统。着重讨论了系统的基本功能，系统的结构，安全监测参数的分析选择及ＳＰＤＳ的显示画面设计等设计问题。     

高温钼丝炉自动控制系统

本文介绍高温钼丝炉自动控制系统的设计过程，采用工业控制计算机，实现温度和真过程控制自动化，对计算机自动控制系统的硬件结构，接口信号处理，控制算法和应用软件的设计进行了较详细说明，本系统在实现应用中取得了较好的效果。     

一个核径迹图像自动分析系统的总体结构设计

设计并实现了基于人工神经网络的核径迹图像自动分析系统的硬件结构，并在系统中应用了显微干涉装置，有效地改善了么迹图像质量，设计并实现了显微镜自动换片样品台，提高了探测器样品测量的工作效率。     

HEPS快速轨道反馈系统网络拓扑结构的设计与实现

快速轨道反馈（Fast Orbital Feedback,FOFB）系统是影响高能同步辐射光源（High Energy Photon Source,HEPS）轨道稳定性的重要因素之一，在设计时应尽可能提高FOFB系统的有效反馈带宽。基于该需求，为HEPS的FOFB系统设计了两层环路集中计算式的系统网络拓扑结构，并在此基础上设计完成了FOFB系统信号传输链路的可编程阵列逻辑（Field Programmable Gate Array,FPGA）固件算法逻辑，内容包括束流位置获取、环路数据传输、FOFB算法、电源控制接口以及系统测试等多个部分。经实验室测试验证，当前结构下的FOFB系统总延迟时间约为140μs，满足HEPS装置对FOFB系统有效反馈带宽的需求。     

Crack shape evolution of surface flaws under fatigue loading of austenitic pipes

From the results of fatigue crack growth and fracture tests of a Ni–Fe base superalloy (Incoloy 908), an improved fatigue life analysis model has been derived from the framework of Newman and Raju. For a plate geometry with an initial semi-elliptical surface crack in its thickness direction, the new model can predict the evolution of crack aspect ratio for a wide range of initial crack geometry for Incoloy 908 that has been considered as the primary candidate for the ITER central solenoid conduit. The improved model is applied to the ITER central solenoid magnet life prediction. The model predicted the conduit fatigue lives that are about two times the values obtained by assuming the constant aspect ratio during the crack growth, for both free-standing and bucked against central solenoid designs. Therefore, we recommend the improved model for the best estimate design analysis of future magnet conduit.     

Safety Analysis Results for Cryostat Ingress Accidents in ITER

Accidents involving the ingress of air, helium, or water into the cryostat of the International Thermonuclear Experimental Reactor (ITER) tokamak design have been analyzed with a modified version of the MELCOR code for the ITER Non-site Specific Safety Report (NSSR-1). The air ingress accident is the result of a postulated breach of the cryostat boundary into an adjoining room. MELCOR results for this accident demonstrate that the condensed air mass and increased heat loads are not a magnet safety concern, but that the partial vacuum in the adjoining room must be accommodated in the building design. The water ingress accident is the result of a postulated magnet arc that results in melting of a Primary Heat Transport System (PHTS) coolant pipe, discharging PHTS water and PHTS water activated corrosion products and HTO into the cryostat. MELCOR results for this accident demonstrate that the condensed water mass and increased heat loads are not a magnet safety concern, that the cryostat pressure remains below design limits, and that the corrosion product and HTO releases are well within the ITER release limits.     

Materials selection and design for the International Thermonuclear Experimental Reactor(ITER)

The International Thermonuclear Experimental Reactor (ITER) program is a multinational effort to design and develop the technology for a superconducting magnetic fusion energy reactor that can achieve long burn times using a deuterium-tritium fuel. During the recently completed Conceptual Design Activity (CDA), teams from the U.S., Japan, Soviet Union, and EC generated a baseline design useful for physics and component modeling and also serving as a focus for component and materials R&D. Here I will review the ITER CDA magnet design, choice of magnet structural materials, and the effect of materials and design limitations on ITER operation. In addition, the selection and availability of superconducting materials will be briefly discussed.     

Study of electromagnetic noise influence on quench detection system under different discharge conditions for EAST

EAST is the first Tokamak device whose toroidal and poloidal magnet are superconducting. The enormous magnetic field energy stored in the magnet system will transfer into thermal energy and cause the damage of superconducting magnet, if a quench happened. Therefore, reliable quench detection is a key issue for steady-state operation. In addition to electromagnetic noise from poloidal magnet fields and plasma current which will experience fast current ramp rate, radio frequency noise from heating system also have some interference on quench detection system to a certain degree. The most difficult point for quench detection system is required to have more detail evaluation on electromagnetic noise interference.Recently experiments have been carried out successfully in EAST device. The steady-state operation with 1 MA of plasma current and more than 100-s plasma duration has been obtained. In the paper, the electromagnetic noise interference on quench detection system under different discharge conditions are analyzed and relative process methods are also introduced. The technological experience and experimental data are significant for the constructing ITER and similar superconducting device have been mentioned which will supply significant technological experience and experimental data for constructing ITER and similar superconducting device.     

ITER Magnet Feeder:Design,Manufacturing and Integration

The International Thermonuclear Experimental Reactor(ITER) feeder procurement is now well underway.The feeder design has been improved by the feeder teams at the ITER Organization(IO) and the Institute of Plasma Physics,Chinese Academy of Sciences(ASIPP)in the last 2 years along with analyses and qualification activities.The feeder design is being progressively finalized.In addition,the preparation of qualification and manufacturing are well scheduled at ASIPP.This paper mainly presents the design,the overview of manufacturing and the status of integration on the ITER magnet feeders.     

Manufacture of ITER feeder sample conductors

The ITER feeders are the components that connect the ITER magnet systems located inside the main cryostat to the cryogenics, power-supply and control system interfaces outside the cryostat. The feeder busbars rely on the Cable-In-Conduit Conductor (CICC) design concept as all the conductors for the ITER magnet systems. There are two types of busbars for the feeder systems. One is the Main Busbar (MB) for the TF, CS and PF feeders, and the other is the Corrector Busbar (CB) for the CC feeders. The busbar cable is wound from multiple stage sub-cables made with Cu and superconducting strands. The superconducting material is NbTi for the busbar strands of all feeder systems. All Feeder conductors are provided by China. The R&D programs are needed to acquire knowledge on the behavior of such conductors.Since the conductors are new, some full size copper dummy conductors have been produced for the testing of the cabling parameters, definition of automatic TIG welding of seamless jacket section, elaboration of cable insertion and compaction. Then, two short qualification conductor samples (MB and CB) are prepared in ASIPP, and NbTi advanced strands are produced by Western Superconductor Technology (WST).The details of manufacturing procedures for Feeder conductor samples will be described in this paper.     

Assessment of ITER PF coil quality from magnetic measurements

A feasibility has been demonstrated for numerical reconstruction on the base of magnetic measurements for geometrical displacements or deformations occurred in the manufacture and assembly of magnet coils. For validation of the proposed approach the test results of reconstruction of possible misalignments and deviations of the ITER PF1 coil are presented.     

Magnetic compatibility of standard components for electrical installations: Computation of the background field and consequences on the design of the electrical distribution boards and control boards for the ITER Tokamak building

Inside the proposed Tokamak building, the ITER poloidal field magnet system would produce a stray magnetic field up to 70 mT. This is a very unusual environmental condition for electrical installation equipment and limited information is available on the magnetic compatibility of standard components for electrical distribution boards and control boards. Because this information is a necessary input for the design of the electrical installation inside the proposed ITER Tokamak building specific investigations have been carried out by the ITER European Participant Team. The paper reports on the computation of the background magnetic field map inside the ITER Tokamak building and the consequences on the design of the electrical installations of this building. The effects of the steel inside the building structure and the feasibility of magnetic shields for electrical distribution boards and control boards are also reported in the paper. The results of the test campaigns on the magnetic field compatibility of standard components for electrical distribution boards and control boards are reported in companion papers published in these proceedings.     

1-D thermal-hydraulic analysis of the high temperature superconducting current leads for the ITER magnet system from 5 K to 300 K

The magnet system of ITER includes high temperature superconducting (HTS) current leads with a maximum current of 68 kA for the toroidal field (TF) coils, 55 kA for the poloidal field (PF)/central solenoid (CS) coils and 10 kA for the control coils (CC), respectively. Although different in terms of size and operative conditions, the ITER HTS current leads have been all designed on the basis of an established concept, which was successfully developed for the LHC at CERN and proven by the so-called 70 kA “demonstrator” lead made by KIT and by the ITER pre-prototypes made by ASIPP in China. A broad R&D campaign has been undertaken by ASIPP and CERN in order to find optimized designs for each component of the leads. Nevertheless, a comprehensive picture of the performance of the entire HTS current leads is not yet available. In this paper, a steady state, full length, thermal-hydraulic 1-D modeling is applied to the study of the three types (TF, PF/CS, CC) of ITER HTS current leads. The results of this predictive analysis are then compared with relevant ITER requirements. It was found that the present design of the HTS current leads will fulfill these specifications.     

Cryogenic mechanical testing of ITER prototype axial breaks

Within the superconducting magnet program for ITER, cryogenic components need to be tested to verify their design. Especially for the helium supply of the magnet system, feeders are needed integrating at the same time high voltage insulation to separate the inner magnet system electrically from the outer cryostat shell. Beside of high voltage and helium flow properties, these axial breaks will be exposed to a limited mechanical loading during operation of the magnet system. Therefore, mechanical tests needs to be performed at room temperature as well as at cryogenic temperature of 77 K.A possible breaker design was provided by Babcock Noell. To verify this design mechanically quasi-static and fatigue tests under bending, torsion and axial loading were done. Results on the performance of the prototypes are presented approving a superior mechanical quality.