屏蔽式主泵飞轮方案论证及转子轴系动态性能敏感性分析

为保证核电主泵满足反应堆停堆和断电事故后惰转时间的要求,对屏蔽式主泵机组的转动惯量要求、飞轮配重方案以及主泵转子轴系的动态性能进行分析,给出了飞轮方案,并进行轴承水膜刚度对转子轴系动态性能影响的敏感性分析.     

我国首台CPR1000堆型的锻造主泵泵壳通过水压试验

福清核电站1号机组主泵泵壳在中国一重核电石化事业部一次通过水压试验，该台泵壳是我国首台CPR1000堆型的锻造主泵泵壳，成功填补了我国核电制造业的空白。     

ANDRITZ新型反应堆冷却剂主泵简介

ANDRITZ为配合中国的新核电项目(CNPl000)特准备了一套方案，为了继续跟综主泵的技术发展，根据大亚湾核电站用的反应堆冷却剂主泵资料，从性能参数、结构形式及布置等方面作了比较，以供新核电工程的决策．     

屏蔽电机有效材料重量的优化设计

屏蔽电机作为屏蔽式主循环泵中的主要大型部件之一，其重量、尺寸直接影响主循环泵重量和体积。本文基于自主开发的映射交叉遗传优化算法，以屏蔽电机的有效材料重量作为优化目标，研究了屏蔽电机的概念设计优化。结果显示：优化方案与原设计方案相比有效材料重量减小了9.933%，优化效果显著。同时，对屏蔽电机有效材料重量受相关尺寸参数、导线参数及槽型参数影响的敏感性进行了分析，其结果可供工程设计参考。     

电源频率变化对屏蔽式主泵电机性能影响及其设计调整分析

分析电源频率变化对屏蔽式主泵电机性能的影响,以及供电电源频率变化较大时的电机设计调整.通过将某60 Hz电机方案调整成50 Hz方案,采用有限元分析方法对2种方案电机的性能进行仿真计算,得到了2种方案电机的相关性能参数.     

世界首台AP1000主泵成功完成最终耐久试验

【人民网2012年4月17日报道】美国匹兹堡当地时间2012年4月16日,中国国家核电技术公司(SNPTC)和美国西屋公司(Westinghouse)、柯蒂斯怀特公司(Curtiss-Wright)宣布首台AP1000主泵成功完成了最后耐久试验,标志着AP1000所有核岛主设备的试验已结束。这台主泵由柯蒂斯怀特公司所属EMD工厂成功研制,将用于中国第三代核电自主化依托项目的首台机组(也是世界首台AP1000机组)——三门1号机组。三门1号机组前两台主泵预计在2012年5月发运。西屋运营总裁RicPerez说:"目前所有主设备制造和试验的完成给项目和客户以坚定的信心。主泵将支持AP1000核电机组安全     

大型先进压水堆核电站重大专项十年回顾

文章回顾了大型先进压水堆核电站重大专项实施十年来取得的主要成绩和具体进展,主要包括:完成了AP1000技术的消化吸收,开发出安全和经济性能领先的具有自主知识产权的CAP1400大型非能动核电站,攻克了屏蔽电机主泵、核电站数字化仪控系统、爆破阀、大型汽轮发电机、全锻造主管道、反应堆钢制安全壳、核电站用大型锻件、铟科镍690传热管等系列关键设备和材料,组织开发了以COSINE为核心的电厂工程设计与安全分析软件包,建立起一批世界水平的非能动安全试验台架并完成CAP1400非能动安全系统试验和设计验证,研究并形成了我国三代核电标准体系,建立了政、产、学、研、用相结合的核电技术创新体系和人才队伍。预期大型先进压水堆核电站重大专项确定的各项目标将全面达到,但由于示范工程开工延迟,建成的时间也将延迟。     

屏蔽式核主泵动静转子间的压力脉动特性

为了研究屏蔽式核主泵动静转子间的压力脉动特征,应用数值模拟方法,采用分离涡模拟（DES）,对模型泵不同流量工况进行非定常计算,分析其时域特征和频域特征,得到了其压力脉动特性。结果表明：核主泵模型泵动静转子之间压力脉动的频率为叶频及其倍频,这是由于叶轮出口边的射流尾迹与导叶入口边周期性的相互切割作用引起的。压力脉动的波动幅度在蜗壳出口处最大,且沿逆时针方向逐渐减弱;在小流量下较小,随着流量增大,其波动幅度增大。动静转子间存在低压流体区域,其数量与叶轮叶片数相同,传播速度与叶轮转速相同。     

秦山核电二期工程反应堆冷却剂泵

介绍秦山核电二期工程主泵结构及主泵的监测和保护系统,重点介绍了秦山核电二期工程特有的双通道振动监测器及相关设备.     

反应堆压力容器退役包装屏蔽方案初探北大核心CSCD

为保证核电反应堆压力容器安全退役,本文以国内最早运行的秦山一期反应堆压力容器源项为参考,模拟设计保持压力容器完整和切割压力容器两种包装屏蔽方案,通过估算两种方案下废物体积、包装成本、运输及处置成本,对比分析发现切割压力容器方案更佳。研究成果可为核电站退役工作提供支持。     

某核电厂主蒸汽管道振动原因分析及解决方案探讨

某核电厂在升功率试验及满功率运行时,发现主控室的噪声超过了设计目标值。经过测量,认为主蒸汽管道振动并通过支撑和贯穿件传播到主控室是造成主控室噪声超标的主要原因之一。本文应用流体力学软件和声学分析软件,采用流声耦合分析的方法,对主蒸汽管道的流场和声场进行了分析。在主蒸汽安全阀支管处和主蒸汽隔离阀空腔中存在着声共振现象,是导致主蒸汽管道振动的主要原因。根据主蒸汽管道振动的原因,可以通过振动源头治理、传播路径治理等方法降低主控室噪声。      

一种适用于新堆的零泄漏循环泵

磁力泵近年来发展迅速,具有零泄漏、结构简单、成本低和维修方便等优点.通过结合部分应用于核能条件下的试验和结构设计研究,研制了既满足高温高压运行、又做到零泄漏等要求的新型循环泵,并对其在新堆或研究堆上的应用前景进行了分析和研究.在一定条件下,磁力泵完全可取代目前大多采用的轴封泵、屏蔽泵和机械密封泵等,达到了简化系统配置、便于维修更换和降低设备成本的目的.     

Reliability of CANDU heat transport pumps

While CANDU heat transport pumps are effectively demonstrating their reliability in the most reliable reactors in the world, the current level of reliability was only achieved after ongoing refinements to the original design. Each design modification was initiated in response to a problem, with reliability taking precedence over cost and efficiency so that each modification has predictably increased pump reliability. Seal reliability, a problem with most large, high temperature pumps, has through an extensive research and development program been improved to a point where a reliable lifetime of about five years can be expected. Co-operative research and development programs at bearing manufacturers facilities and at AECL's Engineering Laboratory have resulted in no bearing related pump incapabilities at either Pickering or Bruce nuclear generating stations. Motor windings, a source of unreliability at the Bruce station, have been improved through the introduction of better turn insulation and additional surge protection. Refinements to the current pump design will continue and AECL is placing particular emphasis on evaluating pump performance in post-LOCA conditions.     

Development and diversity and defense-in-depth application of ABWR feedwater pump and controller model

This work developed an advanced boiling water reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element/three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including step change of dome pressure, feedwater pumps transfer, inadvertent closure of all turbine control valves, and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of stand-alone model and incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an emergency core cooling system (ECCS) automatic diverse back-up. In Lungmen nuclear power plant (NPP), a diverse manual initiation means for the high pressure core flooder (HPCF) loop C is designed as the back-up of digitalized engineered safety features actuation system (ESFAS). If the motor-driven feedwater pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common-cause failure (CCF).     

Cutting performances with new industrial continuous wave ND:YAG high power lasers: For dismantling of former nuclear workshops, the performances of recently introduced high power continuous wave ND:YAG lasers are assessed

Dismantling is a great challenge for nuclear companies which are facing with the cleaning of former nuclear sites. Among the available cutting processes is the multi-kilowatts laser whose power is transmitted through optical fibers. Unlike other cutting processes such as the plasma arc cutting process or the oxy-cutting process, the laser process can be easily implemented by robotic equipments. The mechanised robotic arm carries a laser cutting head to perform, with remote-controlled equipments, the cutting operation.The present study deals with the performances which can be reached with high power continuous wave ND:YAG lasers. The cutting tests were carried out up to 8 kW. The laser power was delivered through a specific power supply chain: a 0.4 mm fiber was transporting the power from the laser to a first interface (coupler) then a second 0.6 mm fiber was bringing the laser power to the cutting head. This solution allowed a power delivery chain whose length could be as high as 100 + 20/50 m. Another advantage of this kind of power supply is that the first fiber can be set in a non-contaminated environment whereas the second fiber lies in the contaminated area. The cutting head used for these tests was a specific tool developed for this laser dismantling work: it is a laser cutting head cooled by pressurized air. This tool was developed with the requirement to be able to sustain a laser power of 14 kW. The pressurized air used to cool the head is also used as cutting gas.The cutting capability was about 10 mm by kW. At the power of 8 kW, austenitic steel plates of thickness 100 mm were cut. These performances were reached with the cut started on the plate's edge. If the cut started in the middle of the plate, the cutting performances were not so high: 8 kW became the power to drill and to cut plates of thickness 40 mm.     

氧化还原法去污对核电站上充泵安全影响的试验研究

研究化学法去污过程中对核电站上充泵腐蚀量的影响。以马氏体不锈钢和奥氏体不锈钢为研究对象,分别进行氧化过程和还原过程中溶液浓度、反应温度、时间对腐蚀量的影响试验;之后进行了氧化还原全过程对两种不锈钢材料的腐蚀量影响试验;最后,对某核电站上充泵进行了实操去污工作。试验结果表明:在超声作用下,使用0.25%高锰酸钾+0.25%氢氧化钠混合溶液作为氧化剂、70 ℃反应4 h,然后再使用0.25%草酸+0.25%柠檬酸混合溶液作为还原剂、70 ℃反应2 h,马氏体不锈钢和奥氏体不锈钢样品表面主要为均匀腐蚀,平均腐蚀量小于1.5 g/m²,腐蚀量满足相关标准要求,同时可有效去除上充泵表面的放射性物质。该配方和工艺流程可推广应用于核电站上充泵的去污工作。     

An application of non-homogeneous Poisson point processes to the reliability analysis of service water pumps

The purpose of this paper is to present an application of the non-homogeneous Poisson point process to the study of the rates of occurrence of failures (ROCOF) when they are time dependent, and the times between failures are neither independent nor identically distributed. The application concerns the analysis of the reliability of service water pumps of a typical PWR nuclear power plant. These pumps are repairable components, in general. Standard statistical techniques, such as the maximum likelihood parameter estimation and linear regression analysis are applied. As a conclusion, the non-homogeneous Poisson process is an adequate tool for analyzing time-dependent ROCOFs for repairable component failure data. It can be used for surveying aging mechanisms during the operation life of repairable systems and also for the assessment of maintenance policies effectiveness.     

多泵并联给水系统给水泵切换运行规律仿真研究

多泵并联给水系统作为核动力系统的主要子系统之一,其给水泵的切换运行规律对系统运行经济性以及系统运行特性至关重要。本研究利用系统仿真支撑软件APROS建立了多泵并联给水系统仿真模型,并依据额定设计值验证了模型的准确性。基于此,通过进行不同切换条件下的线性升、降负荷仿真,对给水泵切换运行规律和系统动态特性进行了研究。研究结果表明,针对本研究对象,其高负荷工况切换点选取为70%额定流量,低负荷工况切换点选取为30%额定流量时,既能获得良好的系统动态响应,还能保持给水泵运行经济性较高。此外,低负荷工况对给水泵切换引入的扰动更为敏感。低负荷工况下,若切换条件选取不当,则会导致降负荷过程中系统触发超压排放。     

低温堆中间回路循环泵隔振设计研究

低温堆作为船用核动力装置使用时,中间回路循环泵选用低转速变频泵。本文针对该泵开展隔振系统设计研究。通过理论分析研究了管道刚度对系统频率的影响,获得了保证泵机组正常运行的隔振系统参数范围。通过有限元数值分析,研究了隔振形式、隔振器参数等因素对泵机组隔振性能的影响。结合正常运行与隔振性能要求提出了低转速变频泵隔振系统的设计方法。结果表明,低温堆中间回路循环泵采用浮筏隔振系统时,通过合理选择隔振器刚度,可使隔振系统的固有频率不在泵机组工作频率范围内,同时具有良好的隔振性能。     

基于时间常数的核电厂主循环泵惰转模型开发与验证

在核电厂初步设计阶段,针对反应堆进行的工况设计和安全分析均需要泵的惰转模型提供输入。现有泵的惰转模型几乎都需要已知泵的设计参数和管路系统阻力特性,但在电厂初步设计阶段,泵的详细结构设计尚未开展,管路阻力特性也难以获取。针对上述问题,提出了两种基于时间常数的主泵惰转特性曲线计算模型,并采用核电厂主循环泵的惰转试验数据进行了对比验证。分析结果表明,模型A在高转速时与试验值吻合较好,低转速时偏差较大,而模型B在整个惰转过程中与试验值均较接近,可用于核电厂的工况设计和安全分析。