国际热核聚变实验堆过渡馈线设计与分析

国际热核聚变实验堆（InternationalThermonuclearExperimentalReactor，简称ITER）采用超导馈线系统传输磁体线圈所需电流、冷却液及数据信号等。本文介绍了馈线系统中过渡馈线的设计，并通过有限元法对设计结构进行全面校核和应力分析，为结构的进一步研制提供了理论依据。     

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。     

浮动式核电站过渡段对安全注射的影响分析及缓解方式研究

以浮动式核电站为研究对象,利用RELAP5程序,分析过渡段水封在发生特定当量直径破口的失水事故对安全注射运行特性的影响,探讨过渡段水封对安全注射的影响规律。结果表明,过渡段水封不利于安全注射水有效注入反应堆,可能将反应堆导向危险的状态。提高安全注射的压力和流量能够克服过渡段水封的不利影响,但对系统容量需求较大。根据浮动式核电站自身设计特点,设置有一次侧非能动余热排出系统,失水事故后投入一次侧非能动余热排出系统能够旁通过渡段水封,保证安全注射水的有效注射并辅助带出堆芯余热,该运行方式有助于优化安全注射的容量设计。     

秦山核电二期工程反应堆主冷却剂系统与辅助系统力学分析

介绍了在秦山核电二期工程反应堆冷却剂系统力学分析工作中所使用的设计规范、准则、分析方法、分析模型、使用载荷、分析结果等情况.主冷却剂系统结构分析是系统和部件设计的基础,包括静力分析、地震分析和失水事故分析(LOCA)三大部分,为各设备部件、管件、支撑及土建结构提供设计载荷和其它接口参数;辅助系统力学分析对核辅助管道进行了应力、疲劳和热棘轮分析,以验证管道在核电厂寿期内的结构完整性,为支撑的布置和选型提供依据.同时总结了设计工作中积累的经验和发现的不足,为将来的核电厂的设计工作提供参考.     

核电站辅助给水系统设计

介绍了３００ＭＷ核电站典型辅助给水系统的优化设计，提出了系统在功能、工况限制、容量和水源等方面的总体设计要求，就秦山核电产工程一期设计过程中辅助水系统设计的不足及改进内容进行了论述，对恰希玛项目辅助给水系统主要参数的选择进行了计算分析。     

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。     

上海光源静力水准系统的安装与调试

本文讨论了上海光源中直线加速器、增强器和储存环静力水准系统安装和调试过程中遇到并解决的技术问题。在静力水准传感器安装之前,必须进行检测,防止由于运输等原因造成的传感器精度达不到要求,本文首先介绍了检测的内容和方法。在系统的现场安装过程中会遇到难以预料的问题,比如支撑问题和供水问题等,本文介绍了解决问题的过程。系统安装后的实际测量结果表明,该系统运行正常,符合设计要求。     

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。     

模块式高温气冷堆超临界循环一次再热方案研究

基于模块式高温气冷堆先进技术和超临界蒸汽动力循环先进技术,研究了高温气冷堆模块与超临界蒸汽动力循环耦合配置方案。结合超临界热力循环理论及模块化高温气冷堆的特性,研究了超临界热力循环方案及相应的循环参数。针对标准一次再热循环,研究了反应堆模块与汽轮机组匹配模式;计算了循环可能达到的效率,并与先进压水堆效率进行了比较。结果表明：模块化高温气冷堆超临界循环效率比压水堆电厂约高30%。本研究结果可作为高温气冷堆超临界循环电站概念设计的理论基础,为进一步的技术研究与方案设计提供依据。     

螺旋管式直流蒸汽发生器的集总参数动态模型

基于基本的流体质量、能量和动量守恒原理，建立了10MW高温气冷堆螺旋管式直流蒸汽发生器的动态数学模型。模型采用了集总参数的建模方法，将蒸汽发生器作为单管模型处理，分为热水段、蒸发段和过热段，且各段间具有可移动的边界。对建立的模型进行了静态和动态仿真，仿真结果表明，所建立的模型是正确和有效的，能够用来进行蒸汽发生器的动态特性仿真。     

核电厂辅助给水系统水箱抗震分析研究

本文针对成熟M310堆型核电厂储液容器辅助给水系统(ASG)水箱,根据ASCE 4—98,采用基于壳模型的有限元法以及两种不同的地震输入,完成了抗震分析,并依据RCC-M规范J篇进行了地震屈曲评价。结果表明,ASG水箱原设计存在一定的地震屈曲风险。在此基础上本文对ASG水箱的结构设计分析给出了建议。     

Electromagnetic–thermal–structural coupling analysis of the ITER edge localized mode coil with fiexible supports

In a fusion reactor, the edge localized mode (ELM) coil has a mitigating effect on the ELMs of the plasma. The coil is placed close to the plasma between the vacuum vessel and the blanket to reduce its design power and improve its mitigating ability. The coil works in a high-temperature, high-nuclear-heat and high-magnetic-field environment. Due to the existence of outer superconducting coils, the coil is subjected to an alternating electromagnetic force induced by its own alternating current and the outer magnetic field. The design goal for the ELM coil is to maintain its structural integrity in the multi-physical field. Taking as an example the middle ELM coil (with flexible supports) of ITER (the International Thermonuclear Fusion Reactor),an electromagnetic–thermal–structural coupling analysis is carried out using ANSYS. The results show that the flexible supports help the three-layer casing meet the static and fatigue design requirements. The structural design of the middle ELM coil is reasonable and feasible. The work described in this paper provides the theoretical basis and method for ELM coil design.     

基于EAST装置上液态调配器系统的研究

液态调配器是用于离子回旋共振加热系统以代替传统活塞式调配器的一种新型阻抗匹配装置。通过对液态调配器工作原理的研究,设计了液态调配器的油路系统,采用计算机和可编程控制器对系统进行控制。同时,对液态调配器各支节匹配高度的计算方法进行了研究,提出了计算公式,并利用实验中测得的数据对计算公式进行了验证。经过两轮EAST实验使用证实,该系统完全满足设计要求。     

Status and progress of Indian LLCB test blanket systems for ITER

The lead–lithium ceramic breeder (LLCB) TBM and its auxiliary systems are being developed by India for testing in ITER machine. The LLCB TBM consists of lithium titanate as ceramic breeder (CB) material in the form of packed pebble beds. The FW structural material is ferritic martensitic steel cooled by high-pressure helium gas and lead–lithium eutectic (Pb–Li) flowing separately around the ceramic breeder pebble bed to extract the nuclear heat from the CB zones. Low-pressure helium is purged inside the CB zone for in situ extraction of bred tritium. Currently the LLCB blanket design optimization is under progress. The performance of tritium breeding and high-grade heat extraction is being evaluated by neutronic analysis and thermal–hydraulic calculations for different LLCB cooling configurations and geometrical design variants. The LLCB TBM auxiliary systems such as, helium cooling system (HCS), lead–lithium cooling system (LLCS), tritium extraction system (TES) process design are under progress. Safety analysis of the LLCB test blanket system (TBS) is under progress for the contribution to preliminary safety report of ITER-TBMs. This paper will present the status of the LLCB TBM design, process integration design (PID) of the auxiliary systems and preliminary safety analysis results.     

Effective-lenght factors for buckling of cable-tray supports

Cable tray systems at many nuclear power facilities are supported by structural steel supports. These supports are safety related and therefore must be evaluated for seismic loads. Because vertical and horizontal earthquake motion may induce compressive loads on some supports, these supports must be design verified to meet compressive load (buckling) allowables. Although trapeze supports suspended from the ceiling are inherently more stable than floor-mounted supports, they must be evaluated for compressive loads as well as the floor-mounted supports. Many ceiling-suspended supports are attached to flexible concrete slabs which may induce vertical accelerations which exceed gravity. For this reason, such supports must be designed to withstand compressive loads in the vertical posts regardless of the cyclic nature of such loads and of the stabilizing effect of gravity.Many industry-accepted design procedures evaluate the stability of individual elements of a frame rather than the stability of the entire frame. In many cases, these industry-accepted design procedures may be overly conservative due to the simplifying assumptions that must be made ragarding the end restraints of each element of the frame.For this study, effective-length factors were developed for the buckling of cable-tray supports typically used at nuclear power facilities. The buckling response of the entire cable-tray support was considered. Nonlinear finite element analyses were performed to obtain the effective-length factors. Sensitivity studies were performed to assess influences of (a) vertical load distribution, (b) transverse loads, (c) longitudinal restraint, and (d) rotational restraint at support anchorages. These influences were important in obtaining effective-length factors. All were accounted for in developing the effective-length factors except the influence of transverse load which was conservatively neglected.     

Electromagnetic–thermal–structural coupling analysis of the ITER edge localized mode coil with flexible supports

In a fusion reactor, the edge localized mode(ELM) coil has a mitigating effect on the ELMs of the plasma. The coil is placed close to the plasma between the vacuum vessel and the blanket to reduce its design power and improve its mitigating ability. The coil works in a high-temperature,high-nuclear-heat and high-magnetic-field environment. Due to the existence of outer superconducting coils, the coil is subjected to an alternating electromagnetic force induced by its own alternating current and the outer magnetic field. The design goal for the ELM coil is to maintain its structural integrity in the multi-physical field. Taking as an example the middle ELM coil(with flexible supports) of ITER(the International Thermonuclear Fusion Reactor), an electromagnetic–thermal–structural coupling analysis is carried out using ANSYS. The results show that the flexible supports help the three-layer casing meet the static and fatigue design requirements. The structural design of the middle ELM coil is reasonable and feasible. The work described in this paper provides the theoretical basis and method for ELM coil design.     

Behaviour of nonlinear supports on a PWR coolant system during a postulated LOCA: Part 1: Effect of modelling methods

A 4-loop Pressurised Water Reactor (PWR) primary coolant system has been analysed for the postulated Loss of Coolant Accident (LOCA) event in order to derive peak dynamic loads for qualifying the design of equipment supports and pipe whip restraints. Pipe whip restraints as well as pipe and equipment supports are nonlinear by nature because of the presence of gaps and the different directional stiffnesses arising from snubber, steelwork and geometric and material interaction at the concrete to steel embedment. The different structural idealisations for the supports and restraints have an influence on the dynamic response of the structure. In the first of the two part paper a range of idealisation models for the Steam Generator and Reactor Coolant Pump vertical columns ranging from elastic stiffnesses to bilinear stiffnesses with or without preload were examined. Due to both structural and loading complexity, the behaviour of these supports were analysed by the Nonlinear Modal Superposition Method [1] and [2]. Analyses with the different models that are within the capabilities of the WESTDYN [3] piping analysis code enabled variations in the peak dynamic loads at the supports, restraints and equipment nozzles and other parameters to be determined and the design acceptability of the hardware established.     

Improvement of plasma uniformity and mechanical properties of Cr films deposited on the inner surface of a tube by an auxiliary anode near the tube tail

In order to improve the length of plasma in a whole tube and mechanical properties of Cr films deposited on the inner surface of the tube, a high-power impulse magnetron sputtering coating method with a planar cathode target and auxiliary anode was proposed. The auxiliary anode was placed near the tube tail to attract plasma into the inner part of the tube. Cr films were deposited on the inner wall of a 20# carbon steel tube with a diameter of 40 mm and length of 120 mm. The influence of auxiliary anode voltage on the discharge characteristics of the Cr target, and the structure and mechanical properties of Cr films deposited on the inner surface of the tube were explored. With higher auxiliary anode voltage, an increase in substrate current was observed, especially in the tube tail. The thickness uniformity, compactness, hardness and H/E ratios of the Cr films deposited on the inner surface of the tube increased with the increase in auxiliary anode voltage. The Cr films deposited with auxiliary anode voltage of 60 V exhibited the highest hardness of 9.6 GPa and the lowest friction coefficient of 0.68.