一起特殊的干式电抗器故障分析

通过对一起户外10kV干式并联电抗器着火燃烧的事故分析,总结了干式电抗器类似故障发生的常见原因.在此基础上分析了这次事故的特殊性,继而提出了防止干式电抗器发生此类事故的日常维护和预防措施.     

昌平站35 kV串联电抗器短路事故分析和反措建议

从故障录波图、电弧路径和事故原因三个方面入手,对一起35kV串联电抗器事故进行了完整分析,确定了该事故是由于电抗器支柱绝缘子鸟粪闪络引起,建议为电抗器支柱绝缘子增加硅橡胶伞裙,并在无功补偿设备的保护和故障录渡方面提供了建议。     

一起变电站10kV电抗器击穿事故的分析

通过对电容器滤波电抗器击穿事故经过进行分析,阐明了事故原因及处理意见,同时对加强电抗器的运行维护提出了建议措施,避免类似事故的发生.     

运行中干式电抗器绝缘状况的诊断方法和判断标准

干式电抗器随着运行时间的延长，绝缘问题逐渐暴露出来，相继发生事故，对电力系统的安全稳定运行造成了一定的影响。章根据对系统内干式电抗器的事故和缺陷分析，对运行中干式电抗器的绝缘诊断方法和措施进行了研究，同时总结了判断干式电抗器绝缘状况的合格标准。     

高压调谐电抗器容量不匹配导致的事故原因分析

针对一起电抗选型设计失误导致的高压调谐电抗器烧毁事故,阐述了调谐型串联电抗器选配原则,并从电容器配置和电流方面对事故原因进行了分析。     

66 kV相控电抗器烧毁故障分析

简述了干式空芯电抗器的结构原理和用途,以及干式空芯电抗器在运行中常见的几种故障。详细介绍了李石寨变电站66 kV SVC用相控干式空芯电抗器烧毁事故的经过,对干式空芯电抗器烧毁事故的原因进行了论证、分析,找到设计、制造过程中,由于线圈的绝缘存在质量问题,覆膜绝缘制造工艺存在先天缺陷,导致匝间短路,致使大面积烧毁。提出了为避免此类事故再次发生,应该加强出厂及交接感应耐压试验。     

干式并联电抗器包封进水对运行可靠性影响的试验研究

干式空心并联电抗器在运行中曾发生多起烧损事故。人们在分析这些事故中普遍认为电抗器包封进水是导致其事故的主要原因,并对此采取了许多措施,然而运行的结果是事故并没有因此而减少。对此,作者对包封进水对电抗器可靠性的影响进行了试验研究。文章介绍了进行该试验研究所用试品、试验方法、试验过程及结果,并对试验前后的结果进行了对比分析。试验结果认为包封进水对电抗器可靠性有影响,但不是主要因素。建议进一步进行机理研究,并有针对地采取措施。     

500kV福泉变低压电抗器事故分析

500kV福泉变35kV3号低压电抗器的过流保护动作，跳开低抗断路器，3号低压电抗器A相起火烧损。贵州电力试验研究院联合都匀供电局对3号低压电抗器的B、c相进行了高压预防性试验，结合事故录波波形进行了事故分析，商量了事故的恢复处理方案。     

干式空心滤波电抗器温度场分布研究

针对干式空心滤波电抗器的运行事故主要来源于电抗器内部温升导致绝缘被破坏问题,为了提高电抗器的运行可靠性,基于温度场计算原理,在考虑空气流速的情况下对某型号电抗器的温度场进行了计算,分析了电抗器的流体场和温度场分布规律.研究结果表明:干式空心滤波电抗器的温升集中在电抗器的上部中心区域,径向电抗器温度上部大于底部,轴向电抗器温度由左至右先升高后降低.     

500 kV变压器、电抗器的套管事故及障碍分析

变压器、电抗器是电力系统的主要设备之一，在电力系统中起着举足轻重的作用，因此他们所发生的事故和障碍倍受关注。变压器、电抗器除本体所发生的事故和障碍外，附件套管的事故和障碍也占相当的比例。近年来，500kV变压器、电抗器的事故和障碍频繁发生，已经引起了有关部门的重视。文章介绍了近年来在我国运行的国产和进口500kV变压器、电抗器的套管事故和障碍情况，并进行了分析。     

A combined thermal and strength analysis of the behavior of a VVER-440 reactor’s vessel during an accident involving core melting

Results from parametric calculations of the thermal and strength behavior of a VVER-440 reactor’s vessel during a beyond-design-basis accident are presented. The ranges of gage pressure inside the vessel and the conditions of externally cooling the reactor with water are presented under which the corium that appears in the reactor vessel during a severe accident can be held there for a long time.     

云南—广东特高压直流滤波器电抗器故障分析

直流滤波器电抗器运行工况较为复杂,运行维护经验极为欠缺。通过介绍云广工程穗东站极2直流滤波器L_2电抗器起火事件,认真分析了引起故障的所有可能原因,最终确认引起故障的根本原因是该电抗器采用的降噪装置内吸音棉未达到阻燃等级,并提出了停电状态和非停电状态运维建议,丰富了直流设备运维经验,有力保证了设备安全稳定运行。     

The concept of extending the service life of the VVER-440-based power units at the Novovoronezh nuclear power plant

Basic statements of the Concept of Extending the Service Life of the VVER-440-Based Power Units at the Novovoronezh NPP beyond 45 years are considered. This topic is raised in connection with the fact that that in December 2016 and in December 2017 the extended service lives of Units 3 and 4 at this NPP will expire. The adopted concept of repeatedly extending the service life of the Novovoronezh NPP Unit 4 implies fitting the power unit with additional reactor core cooling systems with a view to extend the (ultimate) design-basis accidents (which have hitherto been adopted to be a loss of coolant accident involving a leak of reactor coolant through a break with a nominal diameter of 100 mm) to a reactor coolant leak equivalent to rupture of the main reactor coolant pipeline. The modified Unit 4 will also use the safety systems of Unit 3 that is going to be decommissioned. Preliminary calculated assessments of the new design-basis accident scenario involving rupture of the reactor coolant pipeline in Unit 4 fitted with a new configuration of safety systems confirmed the correctness of the adopted concept of repeatedly extending the service life of Unit 4.     

一起500 kV油浸式电抗器故障调查及防范措施分析

作为电力系统重要的无功补偿设备,高压并联电抗器能够补偿输电线路的电容效应,具有调节无功和电压的作用.运行中电抗器故障将对输电网络的安全稳定构成严重威胁,因此分析其故障成因对维护电网安全具有重要意义.针对一起500 kV油浸式高压并联电抗器故障,基于油色谱中特征气体成分分析、气体含量比值计算、特征气体增长趋势分析及返厂前...     

某开合串联电抗器用的40.5kV断路器爆炸的事故分析

笔者介绍了一起用于开合串联电抗器用的40.5 kV断路器爆炸的事故,基于现场检查、故障录波以及故障开关解体的结果,对事故发展过程进行了推理和重现,提出连接产品内拐臂与轴的弹性圆柱销的粉碎性破坏是造成此次事故的直接原因。通过对与故障断路器同厂家及型号的分合闸行程特性测试波形发现该厂家的此型号断路器之缓冲器缓冲性能不佳是引起事故发生的根本原因。     

简述低压电容器火灾事故的分析方法

针对某超市低压变电室一面电容器柜发生的火灾事故,从系统接线方式、事故现场情况、日常维护记录、保护的选择分析以及电能质量测试结果等几方面对事故进行详细分析,建立事故分析模型,并提出具体防范措施。此分析方法对投切电容器组由于缺少消谐电抗器而引起的恶性事故具有较好的参考价值。     

Estimation of thermal loads on the VVER vessel under conditions of inversion of the stratified molten pool in a severe accident

Analysis of the thermal state of molten pools that can be formed on the vessel bottom of the VVER-600 medium-power reactor during a severe anticipated accident with melting of the core is represented. Two types of the molten pool of core materials, with the two-layer and inverse three-layer stratification, are considered. Thermal loads acting on the reactor vessel from the melt are estimated depending on its formation time. Features of the thermal state of the melt in the case of its inverse stratification are analyzed. It is shown that thermal loads on the reactor vessel exceed the critical heat flux (CHF) when forming the two-layer stratified molten pool 10 and 24 h after its shutdown, and the thermal load is close to the corresponding CHF or somewhat exceeds it in 72 h. In the case of the formation of the inverse structure of the melt, one can observe a decrease by more than 2.5 times (in comparison with the two-layer stratified structure) in the thermal load on the reactor vessel in the region of its contact with the upper layer of the steel melt. Analysis of results showed that maximum densities of heat flux to the reactor vessel from the bottom metallic layer with the melt inversion did not exceed corresponding CHFs 24 and 72 h after the reactor shutdown. Because the thermal load on the reactor vessel can be localized in the region of its bottom, where the CHF is relatively small, during the inverse stratification of the melt, there is a need to carry out further in-depth experimental and analytical investigations of conditions for formation of the stratified molten pool and to obtain corrected experimental CHFs for conditions and outlines of cooling the external surface of the VVER-600 vessel in a severe accident.     

超临界水冷堆与WWER1000型压水堆的安全特性比较分析

超临界水冷堆(SCWR)是在高于水的临界点(374℃,22.1 MPa)的温度和压力下运行的反应堆。它的设计为一次通过循环,其中没有再循环回路。这点是与现在运行的轻水堆的最大不同。在超临界水堆电站系统中,以控制棒、汽轮机控制阀与反应堆冷却剂泵为主要的控制方式。通过对比分析超临界水冷堆与田湾核电站WWER1000型压水堆主泵卡轴事故下的安全特性,得出超临界水堆给水流量的丧失会造成反应堆冷却剂流量的丧失,而WWER1000型压水堆给水流量的丧失并不会造成反应堆冷却剂流量的丧失;WW-ER1000型压水堆的安全系统有控制棒、蒸汽发生器的主蒸汽旁排阀、应急给水泵,这些安全配置与超临界水冷堆相似;相比WWER1000型压水堆,超临界水冷堆在压力较快达到稳定状态前提下,其最高包壳温度有个剧烈变化过程,但超临界水冷堆和WWER1000型压水堆在卡轴事故发生后,都能建立稳定的自然循环。