核电站安全监督系统的数据处理

该文根据核电站模拟器上实现的核电站安全监督系统的数据处理,说明了对该实时动态系统参数进行提取、单位变换、进制转换、通讯数据量的压缩以及系统中个别参数重新计算的方法,给出了系统数据处理的程序框图,并指出了数据处理在动态系统中的重要作用。     

大亚湾核电站核燃料运输吊车桥架驱动双控制器闭环控制

为了提高大亚湾核电站换料大修的工作效率,对核燃料运输桥式吊车桥架两侧的电机驱动方式进行了技术改进.本文分析了原有核燃料运输桥式吊车所存在的问题,重点介绍了改造方案的特点和实施情况.改造后的桥式吊车驱动采用双控制器同步控制2台电机运行,采用可编程控制器(PLC)协调2台控制器工作,很好地解决了桥式吊车在高速和远程下的同步问题.     

利用核电厂模拟器进行操纵员可靠性研究

为提高核电厂运动可靠性,需要对核电厂操纵员进行可靠性研究。本文结合我国核电厂操纵员可靠性研究的状况,并参考国际上流行的核电厂操纵员可靠性研究方法,利用两参数威布尔分布的理论在核电厂模拟器上对我国核电厂操纵员进行认知可靠性研究,将该方法得到的结果与其他理论模型的结果进行了比较和讨论,得到了一致的认知。本文的研究方法可为真实核电厂运行提供参考。     

基于MSG指令的核电站PLC数据采集系统的故障处理

岭澳核电站的数据采集系统从投运以来一直存在采集板件偶发脱机的故障,且故障情况下可编程逻辑控制器(PLC)采集无法自动复位。本系统的PLC程序与上位机采用了一体化设计,无法单独修改PLC程序,通过外接PLC装置利用MSG指令,通过一种远程使用MSG指令复位的方式实现了PLC脱机故障的处理,成功地解决了原系统LEVEL1层PLC程序无法修改的难题。     

核安全审评中对某核电厂稳压器的模态分析

以稳压器模态分析校核为例,校核设计者的计算结果,为核安全审评提供依据。使用3种ANSYS单元对稳压器进行模态分析,比较结果的差异并作出总结。     

Management of the Service Life of a Nuclear Power Plant

Nuclear power plant service life management is the modern technology for providing efficient operation of nuclear power plants at an established safety level irrespective of the initial set service life. Consequently, this technology provides a realistic possibility for nuclear power not only to maintain but also to expand its presence in the electricity production market. Conceptually, service life management is viewed as a process that encompasses the entire life cycle of a nuclear power plant, including three basic stages: preoperation, operation, and postoperation. The technical, economic, and organizational aspects and the basic directions, including continuation and decommissioning, are discussed taking account of the international experience in such practice. The target function for managing the service life, the strategy, and a program for Russian power-generating units are examined.     

Calculation of the Economic Parameters of a Nuclear Power Plant

It is assumed that labor costs uniquely determine production costs. The production system is simulated by a black box. All cost components are fed into the input in real-time, starting with the first capital investments. The desired cost of continuous production is taken from the output. A single formula is presented for price of the product, encompassing all cost categories from running to capital. It is shown that under the existing conditions the more capital-intensive industrial objects are economically advantageous; this follows from the directively given formula for the computed costs. The conclusions are discussed for the problems of nuclear power. 2 figures, 5 references.     

大亚湾核电站核燃料的采购管理

本文介绍核电站核燃料采购各循环市场状况和主要特点 ,并结合广东大亚湾核电站的实例阐述核电站核燃料采购的合同模式和管理要点     

核电厂选址阶段的核安全监督

根据核电厂选址程序以及相关的规范标准，结合前一时期核电厂选址．分析了核电厂选址阶段核安全监督的方式和特点，并对当前监督存在的问题进行了讨论。     

地下核电研究现状

日本福岛核事故以后,能否探索一种安全性更好、公众接受度更高的核电站,成为未来安全发展核电的重要方向。地下核电站的研究经过几十年的蛰伏,重新进入研究人员的视野。本文总结了上世纪50年代以来国外地下核电领域的研究成果,介绍了近年来我国地下核电方面的研究历程和研究现状。地下核电利用洞室围岩增加了一道实体屏障,有利于实现从设计上实际消除大量放射性物质释放的可能性。     

16N γ-Ray Diagnostics of a Nuclear Reactor in a Nuclear Power Plant

The AIRM system, which uses the ¹⁶N activity in the VVÉR-1000 reactor at the Kalinin nuclear power plant to measure the thermal power of the reactor and the coolant flow rate, and similar systems used in nuclear power plants with PWR reactors are described.The influence of a change in the neutron spectrum as a result of the loss of ²³⁵U and the accumulation of ²³⁹Pu and ²⁴¹Pu in the VVÉR-1000 core over a run on the yield of the reaction ¹⁶O(n,p)¹⁶N and, correspondingly, the influence of the changes in the indications of the thermal power measured according to ¹⁶N are taken into account.     

高温气冷堆核电站的经济分析

本文采用动态分析法对中外合资高温气冷堆(HTGR)电站作了经济分析,在此基础上整理出一个核电站经济分析通用的模型,可用于气冷堆,但所编程序具有通用性。     

核电厂管道弯曲工艺

目前,在核电管道安装中大量使用了弯管,这些弯管不仅改善了流体的力学性能,同时也减少了管道上的焊口数量,提高了管线运行的可靠性;弯管可根据技术要求采用冷弯或热弯工艺,每种工艺又各有几种方法,弯管的加工一般都在车间进行,生产环境和精度上有可靠地保证,是工厂化管道生产的发展趋势,而合理地选取弯曲工艺和方法是保证弯管质量的关键,目前工艺管道弯曲半径普遍都在3倍公称直径以上,管径愈大,弯曲半径也愈大,工艺操作难度愈大,所以在选材、弯制、检查、处理等环节上必须严格执行标准;随着弯管在核电、化工等领域的普遍应用,弯管的加工工艺水平还在不断的提升。     

核电站功率控制的问题探讨

核电站的功率控制是核电站的重要方面。从澄清各种功率的说法出发,详细分析说明了核电站各种功率的定义、表达式及相关显示,进而分析了各种功率的准确性问题。通过清晰几个功率的说法,较全面地分析了核电站如何在保证核安全的情况下,尽量提高热功率进而提高发电量的方法,对核电站的持续改进有所帮助。     

核电厂厂用电供电方式改进分析

通过对比大亚湾核电站、田湾核电站、台山核电站6 kV厂用电的系统结构、用电现状,分析机组在启动、功率运行、停运、主电网电源失去、机组保护动作时厂用电系统的运行方式,指出3种设计的优缺点,提出了一些改进意见,供设计、工程、运营和改造部门参考.     

某核电厂主蒸汽管道应力分析

本文研究了某核电厂中主蒸汽系统管道的计算和评定等典型内容。此系统管道运行中承受的载荷工况多样,管道应力状态复杂。为了保证系统管道能够正常运行,在设计上需保证该系统管道的应力能够满足相关规范要求。分析采用管道力学分析软件PIPESTRESS进行,计算模型包括主回路、主蒸汽系统及相关的管道和阀门,分析包含静力和动力计算等。对计算结果依据美国机械工程师学会的ASME及相关规范进行了应力评定,并包含了LBB评定,保证了回路运行的安全。     

某核电厂2018年度个人剂量监测

介绍了某核电厂职业照射监测的方法和质量控制措施,从个人剂量的监测人数、剂量范围、人员平均剂量、大修剂量、专业剂量等方面分析了2018年度某核电厂职业照射监测结果,为核电厂个人剂量监测与控制提供参考。     

Nuclear Power Plant Control beyond the 1980s

Designers of nuclear power plant control and instrumentation systems are being pushed by an electronics technology that currently passes through several generations of development during the time taken to design and bring a plant into production. Despite the success of existing designs and the pressure to stick to them, the rapidity with which new components become available and others drop from the suppliers' shelves, require that we give attention to system architectures that are more tolerant of this situation. A distributed data base, containing both on-line and archival information, made available to all systems of a nuclear power plant by means of a highly reliable communications medium, could form the basis for such an architecture. It could not only solve this problem of rapid component development but also provide for complete and comprehensive plant control and surveillance. The possibility of implementing such schemes in an operating plant is probably ten years away but development must begin now if the new electronics technology is to have a planned place in the architectures of the future. At the Chalk River Nuclear Laboratories a long range program is underway. It is exploiting extensive additions that were needed in the data acquisition and processing capability associated with engineering experiments in the large research reactors NRU and NRX.     

秦山核电厂调试

本文综合介绍了秦山核电厂的调试,其中包括无核和带核调试的试验内容、进度、调试网络、调试机构、人员和管理。总结了调试经验。调试结果证明,秦山核电厂的设计、建造是成功的。