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Some Technical Solutions for Environmental Protection System during Accidents at Nuclear Power Plants
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作者 Sergey A. Kulyukhin Igor’ A. Rumer +5 位作者 Viktor M. Berkovich Gennadii S. Taranov Ivan V. Yagodkin Viktor P. Osipov Sergey S. Skvortsov Leo N. Falkovskii 《World Journal of Engineering and Technology》 2017年第4期1-11,共11页
The paper reports some technical solutions, which suggested or used for increasing of environmental protection during accidents at NPPs. For NNPs with two protective shells and pressure release system such as WWER-100... The paper reports some technical solutions, which suggested or used for increasing of environmental protection during accidents at NPPs. For NNPs with two protective shells and pressure release system such as WWER-1000 a comprehensive, passive-mode environmental protection system of decontamination of the radioactive steam-air mixture from the containment and the intercontainment area was suggested. This system includes the “wet” stage (scrubbers, etc.), the “dry” stage (sorption module), and also an ejector, which in a passive mode is capable of solving the multi-purpose task of decontamination of the air-steam mixture. For WWER-440/230 NPPs three protection levels: 1) a jet-vortex condenser;2) the spray system;3) a sorption module were suggested and installed. For modern designs of new generation NPPs, which do not provide for pressure release systems, a new passive filtering system together with the passive heat-removal system, which can be used during severe accidents in case all power supply units become unavailable, was proposed and after modernization was installed at the KudanKulam NPP (India). 展开更多
关键词 nuclear power plants SEVERE ACCIDENT Environment protection RADIOACTIVE Steam-Air Phase
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Study on Lightning Protection Design of DCS in a Nuclear Power Plant 被引量:3
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作者 Jie Liu Yunfeng Zhu +1 位作者 Fang Tian Jin Wang 《Meteorological and Environmental Research》 CAS 2013年第10期14-18,共5页
DCS (distributed control system) plays a decisive role in the overall operation of a nuclear power plant. If DCS fails, it will seriously affect the normal production of nuclear power plant, causing great losses. So... DCS (distributed control system) plays a decisive role in the overall operation of a nuclear power plant. If DCS fails, it will seriously affect the normal production of nuclear power plant, causing great losses. So it is very important to take perfect lightning protection measures on DCS of the nuclear power plant. In this paper, according to the actual situation of DCS in a nuclear power plant, by controlling lightning point, securely booting lightning into the ground network, improving low-resistance ground network, eliminating ground loops, determining the safety space, surge protection of power and signal, a set of complete lightning protection design scheme was systematically put forward. Some specific lightning protection measures were highlighted, such as the DCS grounding, equipotential bonds and shields, and some specific considerations were put forward. All of these could offer reference in the practical application. 展开更多
关键词 DCS Lightning protection nuclear power plant GROUNDING China
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Bayesian belief-based model for reliability improvement of the digital reactor protection system 被引量:2
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作者 Hanaa Torkey Amany S.Saber +2 位作者 Mohamed K.Shaat Ayman El-Sayed Marwa A.Shouman 《Nuclear Science and Techniques》 SCIE CAS CSCD 2020年第10期55-73,共19页
The digital reactor protection system(RPS)is one of the most important digital instrumentation and control(I&C)systems utilized in nuclear power plants(NPPs).It ensures a safe reactor trip when the safety-related ... The digital reactor protection system(RPS)is one of the most important digital instrumentation and control(I&C)systems utilized in nuclear power plants(NPPs).It ensures a safe reactor trip when the safety-related parameters violate the operational limits and conditions of the reactor.Achieving high reliability and availability of digital RPS is essential to maintaining a high degree of reactor safety and cost savings.The main objective of this study is to develop a general methodology for improving the reliability of the RPS in NPP,based on a Bayesian Belief Network(BBN)model.The structure of BBN models is based on the incorporation of failure probability and downtime of the RPS I&C components.Various architectures with dual-state nodes for the I&C components were developed for reliability-sensitive analysis and availability optimization of the RPS and to demonstrate the effect of I&C components on the failure of the entire system.A reliability framework clarified as a reliability block diagram transformed into a BBN representation was constructed for each architecture to identify which one will fit the required reliability.The results showed that the highest availability obtained using the proposed method was 0.9999998.There are 120 experiments using two common component importance measures that are applied to define the impact of I&C modules,which revealed that some modules are more risky than others and have a larger effect on the failure of the digital RPS. 展开更多
关键词 nuclear power plants Reactor protection system Bayesian belief network
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Violation of the Convention on the Protection of the Black Sea against Pollution,Bucharest’s Convention of 1992 and the Sofia Protocol of 2018 by Turkish Government’s Sinop Nuclear Power Complex Project
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作者 Hayrettin Kilic Ismail Hakki Atal 《Journal of Environmental Science and Engineering(A)》 2021年第1期34-38,共5页
On September 12th,2020,the Turkish Ministry of Environment and Urban Planning issued a final approved version of an EIA(Environmental Impact Assessment)report for the Sinop(4,800 MWe)nuclear power plant and nuclear fu... On September 12th,2020,the Turkish Ministry of Environment and Urban Planning issued a final approved version of an EIA(Environmental Impact Assessment)report for the Sinop(4,800 MWe)nuclear power plant and nuclear fuel fabrication complex project,located on Turkey’s Southern Black Sea coastline,in the Sinop Providence,which will be built on a BOO(Build-Own-Operate)basis by an offshore company known as General Directorate of Electricity Generation Inc.(EUAS)International ICC,along with unknown shadowy partners and investors.This project violates the Convention on the Protection of the Black Sea against Pollution,namely,Bucharest’s Convention of 1992,and the Sofia Protocol of 2018 which are established to preserve the uniqueness of the Black Sea,sustain the fisheries,and protect marine life.The Black Sea is the largest anoxic water basin in the world with oxygen rich surface waters supporting marine life which constitute only about 13% of the Black Sea volume.For the rest of the entire Black Sea at a depth greater than 150-200 m,there is a permanent hydrogen sulphide zone devoid of life,the oxygen is completely absent after this level.This unique bio-hydrological characteristic has been regulating the preconditions of its following distinctive biodiversity for thousands of years.The biologically rich regions are only limited to only oxygen rich shelf zones,with depths of up to 50-100 m in the southern coast line,and in the northern Black Sea shallow-water areas with depths of up to 5-10 m.This water body,bordering the hydrogen sulphide zone,is approximately 200-300 m wide and averages 5-50 m deep,in which high concentrations of fish eggs and larvae strive,and circulate counterclockwise along 4340 km coastline of the Black Sea. 展开更多
关键词 Bucharest convention protection Black Sea nuclear power plant POLLUTION
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核电厂安全级DCS缺省值设置策略研究
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作者 胡清仁 彭浩 +4 位作者 刘宏春 李谢晋 周岱 郑媛媛 张旭 《自动化仪表》 CAS 2024年第9期14-19,共6页
针对数字化仪控系统中无效信号的质量位随意蔓延使系统处于一种不确定状态的问题,结合核电厂运行工况和信号特性,对龙鳞平台故障诊断机制和信号质量位标识进行研究。考虑故障安全准则,系统性地提出缺省值设置原则。从信号执行功能和信... 针对数字化仪控系统中无效信号的质量位随意蔓延使系统处于一种不确定状态的问题,结合核电厂运行工况和信号特性,对龙鳞平台故障诊断机制和信号质量位标识进行研究。考虑故障安全准则,系统性地提出缺省值设置原则。从信号执行功能和信号边界两个维度进行分析,确认缺省值的设置范围,并详细给出执行保护功能、报警功能、维护和试验功能信号的缺省值设置策略。同时,针对传统的缺省值验证方式无法全面、有效地进行缺省值验证的问题,提出一种利用全范围模拟机和虚拟数字化控制系统(DCS)进行缺省值验证的新方法。利用该方法可有效地对DCS内设置的缺省值进行系统性的验证。所提出的缺省值设置策略和验证方法可为后续核电厂安全级DCS的缺省值分析和设置提供全面的指导。 展开更多
关键词 核电厂 保护系统 安全级数字化控制系统 故障诊断 质量位 缺省值
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IEC 63096核电厂仪控系统网络安全管控标准与国内等级保护相关标准的协调分析
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作者 郭云 李江海 《核科学与工程》 CAS CSCD 北大核心 2024年第1期161-167,共7页
伴随着全球工业数字化、网络化和智能化的发展,传统基于物理隔离的保护方式已无法确保核电厂仪控系统的网络安全。核电厂仪控系统遭受网络攻击不仅可能导致生产过程中断,还可能引起核安全事件,因此核电厂仪控系统网络安全已引起世界各... 伴随着全球工业数字化、网络化和智能化的发展,传统基于物理隔离的保护方式已无法确保核电厂仪控系统的网络安全。核电厂仪控系统遭受网络攻击不仅可能导致生产过程中断,还可能引起核安全事件,因此核电厂仪控系统网络安全已引起世界各国及相关国际组织的高度关注。国际电工委员会于2020年发布了关于核电厂仪控系统网络安全防范管控的国际标准IEC 63096,为核电厂仪控系统各相关方提供了基于网络安全防范等级和生命周期阶段的具体指引,用于指导核电厂实施网络安全管控措施,以预防、检测和处置网络攻击。同时,等级保护制度作为我国网络安全的基础制度,是国内各核电厂必须开展的规定工作。为此,本文分别对IEC 63096以及等级保护系列标准进行了介绍,重点对二者在安全等级及管控措施方面的协调性进行了分析,从而帮助核电厂在进行网络安全管控措施的部署时有效降低时间成本和投资成本。 展开更多
关键词 IEC 63096 核电厂 仪控系统网络安全 等级保护 协调分析
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数字化核电厂主控室软操作任务分析
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作者 任诚 刘德懿 +3 位作者 赵明 徐洁 易灿南 胡鸿 《中国核电》 2024年第1期61-65,共5页
核电厂数字化后,操纵员在计算机界面进行监视、评估与操纵,需要进行大量软操作。为全面了解数字化核电厂主控室软操作任务特征,基于操纵员任务类型以及NUREG/CR-6690,确定操纵员软操作类型。然后以某核电厂丧失给水事件复训为例,分析其... 核电厂数字化后,操纵员在计算机界面进行监视、评估与操纵,需要进行大量软操作。为全面了解数字化核电厂主控室软操作任务特征,基于操纵员任务类型以及NUREG/CR-6690,确定操纵员软操作类型。然后以某核电厂丧失给水事件复训为例,分析其反应堆操纵员(RO)和汽轮机操纵员(TO)的软操作特征。实例分析结果表明:TO软操作、界面管理任务和主任务次数大于RO;操纵员界面管理任务次数大于主任务次数;操纵员软操作工作负荷与任务有关,且不同工况下操纵员工作负荷存在差异;操纵员界面管理任务中,导航和查询/质问占比最大。 展开更多
关键词 数字化核电厂 软操作 操纵员 界面管理任务 主任务
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纸质规程下数字化核电厂界面管理任务研究
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作者 刘德懿 赵明 +2 位作者 易灿南 罗洋 徐洁 《安全》 2024年第2期66-71,共6页
为全面了解纸质规程下数字化核电厂界面管理任务特征,首先,基于NUREG/CR-6690以及操纵员在计算机屏幕上的点击行为,确定5类12条界面管理任务;然后,以某核电厂某班组复训过程操纵员监视与操纵行为为研究对象,利用INTERACT软件对反应堆操... 为全面了解纸质规程下数字化核电厂界面管理任务特征,首先,基于NUREG/CR-6690以及操纵员在计算机屏幕上的点击行为,确定5类12条界面管理任务;然后,以某核电厂某班组复训过程操纵员监视与操纵行为为研究对象,利用INTERACT软件对反应堆操纵员(RO)和汽轮机操纵员(TO)的界面管理任务和主任务进行统计与分析。实例分析结果表明:RO和TO界面管理任务均多于主任务,分别占各自总任务的69.3%和82.3%;正常运行工况下,RO与TO界面管理任务占比均超75%,事故运行工况下,TO界面管理任务占比均超81%;RO与TO相比需要执行更多的界面管理任务;RO和TO画面调整和配置次数较少,导航和查询/质问次数最多;在事故运行工况下,TO较多采用自动化执行监视、评估和操纵任务。 展开更多
关键词 数字化核电厂 操纵员 纸质规程 界面管理任务 主任务
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核电厂控制系统逻辑验证方案改进研究
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作者 何超 张鹏 +1 位作者 刘双金 刘岩 《自动化仪表》 CAS 2024年第9期20-26,共7页
随着自主三代核电技术的稳步推进,在建核电项目面临控制系统逻辑验证量大、工期长的问题,而现有验证方案源于二代加核电项目,限制了逻辑验证效率的提升。针对此问题,对国内二代加、自主三代核电项目的控制逻辑特点和验证策略进行分析和... 随着自主三代核电技术的稳步推进,在建核电项目面临控制系统逻辑验证量大、工期长的问题,而现有验证方案源于二代加核电项目,限制了逻辑验证效率的提升。针对此问题,对国内二代加、自主三代核电项目的控制逻辑特点和验证策略进行分析和归纳,以总结现有方案在工程实践中存在的问题。在此基础上,从验证策略、组织模式、实施方法三个维度研究应对措施,提出了重构逻辑测试场景、引入仿真技术、建立自动化测试系统的改进方案。改进方案和原方案的效益对比结果表明,改进方案的工作量和工期均大幅减少。改进方案提升了逻辑验证的实施效率和工程效益,对工程实际问题提出了针对性解决措施。该研究对后续批量化推进三代核电项目工程建设具有参考价值。 展开更多
关键词 核电厂 数字化控制系统 逻辑验证 工程调试 自动化测试
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核电厂地下管网结构化数据建模研究
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作者 李友 张梦雪 +2 位作者 刘聪 苏宇琪 吴德成 《山西建筑》 2024年第6期184-187,共4页
在数字化设计平台建设过程中,为了解决缺少专业设计软件的情况下少量地下管网模型的生产和集成问题,需要建立一种与设计软件解绑的建模方式。通过研究使用结构化的管网数据驱动生成三维模型的方法,实现核电厂已有地下管道和管道附属物... 在数字化设计平台建设过程中,为了解决缺少专业设计软件的情况下少量地下管网模型的生产和集成问题,需要建立一种与设计软件解绑的建模方式。通过研究使用结构化的管网数据驱动生成三维模型的方法,实现核电厂已有地下管道和管道附属物快速逆向建模,进一步实现核电厂室外工程设计模型和施工模型的集成与应用。 展开更多
关键词 核电厂 地下管网 结构化数据 数据建模 数字化
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基于CANDU型核电站的高精度线性电源分析设计
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作者 印健 邓爱民 +4 位作者 王学智 王旭 王灿 张皓然 何亚波 《电工技术》 2024年第8期34-38,42,共6页
40 V仪用直流电源国产化势在必行。在对电源应用场景和性能指标深入分析的基础上,设计出一款具有高可靠性、高性能、符合人机交互工学界面等特点的电源,第三方核级抗震试验、型式试验、老化试验、EMC试验结果表明该款40 V仪用直流电源... 40 V仪用直流电源国产化势在必行。在对电源应用场景和性能指标深入分析的基础上,设计出一款具有高可靠性、高性能、符合人机交互工学界面等特点的电源,第三方核级抗震试验、型式试验、老化试验、EMC试验结果表明该款40 V仪用直流电源的各项指标可完全比拟原用国外产品,并在电源安全防护和人机交互方面具有更好的性能。 展开更多
关键词 核电站仪用电源 高精度 高可靠性 数字化 国产化
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核电厂数字化仪控系安全问题及应对策略研究
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作者 余毅 《阀门》 2024年第11期1293-1297,共5页
数字化仪控系统已广泛应用于我国核电厂。相较传统模拟系统,数字化仪控系统具有更高的可靠性和容错能力,但同时也增加了控制系统的复杂性和不确定性,带来了新的安全问题。通过将数字化仪控系统的失效机理和核电厂典型运行事件中呈现的... 数字化仪控系统已广泛应用于我国核电厂。相较传统模拟系统,数字化仪控系统具有更高的可靠性和容错能力,但同时也增加了控制系统的复杂性和不确定性,带来了新的安全问题。通过将数字化仪控系统的失效机理和核电厂典型运行事件中呈现的失效过程相结合,更加全面的分析了导致相关安全问题的深层次原因,并结合法规导则要求的安全原则提出了相应的应对策略,以及部分准则和具体措施,为核电厂数字化仪控系统安全设计和审评提供了参考。 展开更多
关键词 核电厂 数字化仪控系统 安全问题 失效机理 纵深防御
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SVBR-100 Nuclear Technology as a Possible Option for Developing Countries 被引量:3
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作者 Vladimir Petrochenko Georgy Toshinsky Oleg Komlev 《World Journal of Nuclear Science and Technology》 2015年第3期221-232,共12页
Many developing countries need ecologically clean power sources (PS). The nuclear power plants are such sources. However, a great number of the developing countries do not possess developed large capacity power system... Many developing countries need ecologically clean power sources (PS). The nuclear power plants are such sources. However, a great number of the developing countries do not possess developed large capacity power systems. Moreover, currently in the developing countries, there are no highly skilled personnel to provide construction and reliable and safe operation of the nuclear plants, which are complex and potentially hazardous systems. In some countries, the level of terroristic threat is extremely high. For that reason, there are specific requirements to the nuclear PSs intended for use in the developing countries. In the presented report, the specific requirements which must be met by the NPT proposed for use in developing countries are formulated, basic statements of the SVBR-100 concept are presented, design and principal scheme of the reactor fa-ility are described, major characteristics of SVBR-100 are summarized. 展开更多
关键词 SVBR-100 Reactor nuclear power Technology nuclear power Plant Inherent SELF-protection Passive Safety
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Reactor Protection Diversity Requirements and the Typical Solution Based on DCS 被引量:1
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作者 W.J. Huang Y.J. Tian X.S. Dong L.M. Zhang G.M. Liu G.J. Jiang 《Journal of Energy and Power Engineering》 2011年第12期1149-1153,共5页
The defense-in-depth and diversity have become the basic requirements for digital I&C and should be strictly followed when carrying out the overall scheme design of digital control system, in which the risk of common... The defense-in-depth and diversity have become the basic requirements for digital I&C and should be strictly followed when carrying out the overall scheme design of digital control system, in which the risk of common cause failure has to be prevented or coped with. This paper analyzes the requirements of the diversity principle and sums up the typical solution of the diversified protection of reactor based on the CPR1000 NPP. Some concepts will be helpful to the design of DCS for others plants. 展开更多
关键词 protection defense-in-depth and diversity DCS nuclear power plant.
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Assessment of Containment Structures Against Missile Impact Threats
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作者 LIQ M 《Transactions of Tianjin University》 EI CAS 2006年第B09期22-30,共9页
In order to ensure the highest safety requirements, nuclear power plant structures (the containment structures, the fuel storages and transportation systems) should be assessed against all possible internal and extern... In order to ensure the highest safety requirements, nuclear power plant structures (the containment structures, the fuel storages and transportation systems) should be assessed against all possible internal and external impact threats. The internal impact threats include kinetic missiles generated by the failure of high pressure vessels and pipes, the failure of high speed rotating machineries and accidental drops. The external impact threats may come from airborne missiles, aircraft impact, explosion blast and fragments. The impact effects of these threats on concrete and steel structures in a nuclear power plant are discussed. Methods and procedures for the impact assessment of nuclear power plants are introduced. Recent studies on penetration and perforation mechanics as well as progresses on dynamic properties of concrete-like materials are presented to increase the understanding of the impact effects on concrete containment structures. 展开更多
关键词 impact threats protective design and assessment containment structure nuclear power plant
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福清核电厂5^(#)、6^(#)机组反应堆保护系统的设计 被引量:2
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作者 刘宏春 冯威 +4 位作者 李谢晋 贺理 陈鹏 王淼 丁书华 《自动化仪表》 CAS 2023年第6期36-41,47,共7页
反应堆保护系统是核电厂应对预期运行事件或设计基准事故而设置的重要安全级仪控系统。为满足“华龙一号”三代核电高安全性目标的设计要求,需要对反应堆保护系统的功能性能进行提升。以“华龙一号”示范工程福清核电厂5#、6#机组为研... 反应堆保护系统是核电厂应对预期运行事件或设计基准事故而设置的重要安全级仪控系统。为满足“华龙一号”三代核电高安全性目标的设计要求,需要对反应堆保护系统的功能性能进行提升。以“华龙一号”示范工程福清核电厂5#、6#机组为研究对象,通过充分考虑保护系统设计准则要求并基于事故分析结论,提出了更具高可靠性和全面保护功能特征的反应堆保护系统设计方案。详细介绍了系统自动保护功能的设计、系统结构设计以及系统健康管理等内容,并对系统拒动率进行了定量分析。分析结果表明,系统总体拒动率不高于5.0×10^(-7)/指令,达到了国际主流三代核电的可靠性水平。该研究成果可为后续核电厂的反应堆保护系统设计或优化提供借鉴。 展开更多
关键词 核电厂 华龙一号 安全级分布式控制系统 反应堆保护系统 共因故障 可靠性 定期试验
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核电厂流出物排放控制值研究 被引量:1
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作者 黄彦君 上官志洪 左伟伟 《辐射防护》 CAS CSCD 北大核心 2023年第5期431-437,共7页
排放量控制是我国核电厂环境辐射防护和流出物排放管理的重要内容。通过对比国内外压水堆核电厂流出物排放量水平,分析了我国现行标准中排放控制值对国外同类核电厂流出物排放量的包络率,同时与法国流出物排放控制值进行了比较。结果表... 排放量控制是我国核电厂环境辐射防护和流出物排放管理的重要内容。通过对比国内外压水堆核电厂流出物排放量水平,分析了我国现行标准中排放控制值对国外同类核电厂流出物排放量的包络率,同时与法国流出物排放控制值进行了比较。结果表明,除流出物中^(3)H、^(14)C外,现有标准控制值基本上可以包络国外核电厂统计排放量,且具有较大的余量。在目前的流出物排放管理水平下,现行标准中规定的排放量控制值仍是适宜的,其中对于^(3)H、^(14)C外的其他控制指标仍有很大的优化空间。 展开更多
关键词 核电厂 流出物排放 排放控制 环境辐射防护
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Safety of Future NPPs Must Not Be in Conflict with Economics
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作者 Vladimir Petrochenko Georgy Toshinsky Oleg Komlev 《World Journal of Nuclear Science and Technology》 2016年第4期284-300,共18页
The conflict between safety and economics requirements is peculiar to the present nuclear power (NP). The main point of the conflict is that for traditional type reactors the increase of requirements to safety of nucl... The conflict between safety and economics requirements is peculiar to the present nuclear power (NP). The main point of the conflict is that for traditional type reactors the increase of requirements to safety of nuclear power plants (NPP) worsens their economical characteristics. This is caused by large potential energy accumulated in reactor coolant. In the presented paper the opportunity and expediency of changeover to reactors with heavy liquid-metal coolants (HLMC) in future NP is grounded. First of all, this refers to lead-bismuth coolant (LBC) mastered in the process of operating nuclear submarines (NS) reactors. The reactor facilities (RFs) of that type cannot cause destruction of defense barriers and make possible deterministic elimination of severe accidents with catastrophic radioactivity release. So it will make possible to eliminate the highlighted conflict and reasons for existence of population’s radiophobia. Lead-bismuth fast reactor SVBR-100 with electric power of 100 MWe is the reactor facility of that type. The effect of accumulated in coolant potential energy on safety and economics is considered. Main specific features of SVBR-100 technology providing a high level of inherent self-protection and passive safety are presented. 展开更多
关键词 SVBR-100 Reactor Lead-Bismuth Coolant nuclear power Plant Inherent Self-protection Passive Safety
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某核电厂滤网用铝合金牺牲阳极的失效原因 被引量:1
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作者 江锋 刘蔚伟 马韦刚 《腐蚀与防护》 CAS CSCD 北大核心 2023年第1期75-78,82,共5页
针对核电厂凝汽器二次滤网及旋转滤网用铝合金牺牲阳极存在溶解不足及阴极保护效果不佳的情况,对相关海水水质、牺牲阳极化学成分和电化学性能进行分析,研究了铝合金牺牲阳极失效的原因。结果表明:阳极中主要合金元素In含量偏低、杂质元... 针对核电厂凝汽器二次滤网及旋转滤网用铝合金牺牲阳极存在溶解不足及阴极保护效果不佳的情况,对相关海水水质、牺牲阳极化学成分和电化学性能进行分析,研究了铝合金牺牲阳极失效的原因。结果表明:阳极中主要合金元素In含量偏低、杂质元素Si含量偏高是其性能变差的主要原因。建议核电厂在牺牲阳极采购过程中严格把控原材料化学纯度,对进厂牺牲阳极进行表面质量、化学成分复验和电化学性能测试,在上述性能均满足相关标准和技术要求后方可使用。 展开更多
关键词 牺牲阳极 阴极保护 核电厂 化学成分 电化学性能
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高温气冷堆示范工程反应堆保护系统调试工具研发与应用 被引量:1
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作者 雷川 程鹏 张智军 《南方能源建设》 2023年第6期153-159,共7页
[目的]为克服反应堆保护系统调试技术存在的不足,以提高反应堆保护系统调试效率和质量。[方法]设计了一套专用于高温气冷堆示范工程反应堆保护系统的自动化调试工具。该工具采用了先进的技术,能够自动化地完成反应堆保护系统的调试,可... [目的]为克服反应堆保护系统调试技术存在的不足,以提高反应堆保护系统调试效率和质量。[方法]设计了一套专用于高温气冷堆示范工程反应堆保护系统的自动化调试工具。该工具采用了先进的技术,能够自动化地完成反应堆保护系统的调试,可以大大提高调试效率和质量。[结果]阐述了高温气冷堆示范工程反应堆保护系统调试工具的研发与应用,介绍了调试工具的研发过程、难点及内容,以及信号输出、信号采集、数据处理、信息显示等自动调试功能的设计思路、实现方式及成果,经过高温气冷堆示范工程反应堆保护系统功能和性能验证方面的实际调试与应用。在调试过程中,该工具能够快速准确地发现和解决问题,证明了该工具的有效性和可用性。[结论]自动化调试工具可以提高反应堆保护系统调试的效率和质量,提高了反应堆保护系统的可靠性和安全性。同时,还需要继续研究和改进自动化调试工具,以适应反应堆保护系统不同的调试需求。 展开更多
关键词 核电厂 高温气冷堆 反应堆保护系统 调试工具 调试效率
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