柏崎核电厂7号机组发生阀门故障但未造成泄露

【美联社华盛顿2004年1月2日电】 美国机密核武实验室钥匙失窃案件及其他安全漏洞引起了人们的担忧。在一些国会议员对几处设施的安全漏洞提出批评之后,美国能源部下属的核军工管理局(NNSA)计划在全国范围内对核设施的锁、钥匙及规程进行安全检查。NNSA负责维护美国的核武库,促进国际核不扩散,并为海军舰艇提供核推进系统。NNSA将在2004年2月派出一组检查员开始实施安全检查。此前NNSA曾在2003年7月主动宣布增加安全专家和检查频率,审查以前的研究和调查结果,为更大规模的安全计划建立一个委员会以及独立工作组。的钥匙丢失案件涉及N…     

新标准GB/T15474-95介绍

核电厂仪表及其供电设备安全分级是核电厂设备安全分级的一部分,既与核电厂安全密切相关,又直接影响核电厂的造价,是核电厂建造中必须解决的重要问题之一。 核工业标准化研究所1991年组织技术人员在参考了IEC/TC45/SC2《核电厂安全重要仪表和控制系统分级》和KCC-E等国际和国外先进标准后,结合我国国情编制了GB/T15474-95《核电厂仪表和控制系统及其供电设备安全分级》。     

IAEA安全标准丛书No.SSG-39 核电厂仪表与控制系统设计IAEA安全标准丛书 具体安全导则

正该出版物是对两项安全导则的修订与结合,即IAEA安全标准系列No.NS-G-1.1和No.NS-G-1.3。该出版物对以上两项安全导则发布后仪表与控制系统发生的改变进行说明。主要变化与计算机应用的持续发展相关,也与仪表与控制系统的安全、稳定和实际使用上必要     

核反应堆工业控制系统与企业信息系统互联安全防护体系研究

针对核反应堆工业控制系统与企业信息系统互联工程安全防护策略孤立分散的现状，根据系统互联的安全保密需求，分别从管理层面和技术层面对2个系统互联后面临的安全保密风险进行详细分析，并根据分析结果提出了基于管理和技术双重防御的核反应堆工业控制系统与企业信息系统互联安全防护体系。本文提出的安全防护体系可为核反应堆工业控制系统与企业信息系统的互联建设提供防护指南。      

锦屏深地强流高压加速器控制系统的研制

本文介绍了锦屏深地强流高压加速器自动控制系统的基本结构、控制软件和安全联锁设计,阐述了该加速器在运行过程中高压打火产生的强干扰影响控制系统和相关设备的正常运行及在调试和实验过程中遇到的问题。通过分析原因,采取各种保护措施提高控制系统的抗干扰能力,确保控制系统和设备运行的稳定性。     

IEC 61513分析研究

本文分析了IEC 61513∶2001<核动力厂安全重要仪表和控制系统系统总要求>与现有核电厂仪表和控制(I&C)系统标准文件之间的关系,介绍了安全重要I&C系统总的安全生存周期和单个系统的生存周期,讨论了I&C功能分类和安全重要I&C系统分级以及硬接线系统和基于计算机的系统等问题.     

IEC 61513分析研究

本文分析了IEC 61513∶2001<核动力厂安全重要仪表和控制系统系统总要求>与现有核电厂仪表和控制(I&C)系统标准文件之间的关系,介绍了安全重要I&C系统总的安全生存周期和单个系统的生存周期,讨论了I&C功能分类和安全重要I&C系统分级以及硬接线系统和基于计算机的系统等问题.     

核电厂安全级控制系统软件关键性分析

为规范核电厂控制系统的软件开发和验证活动,提出了软件关键性分析方法。运用软件关键性流程树对软件组件的关键性等级进行初步分类,按软件危险性与可操作性分析方法验证该关键性等级,结合控制系统的整体安全目标确定各软件组件的安全完整性等级。应用实验表明:与现有方法相比,本方法具有更好的可操作性和可验证性,可为核电厂控制系统的软件关键性分析提供参考。     

核反应堆功率控制系统的数字化实现

功率控制系统是反应堆的一关键控制系统,系统复杂,可靠性要求高.以前的核电站功率控制系统通常采用模拟技术.数字化方案将更有优势,但有相当的难度和待解决的问题.本文介绍一座试验堆的全数字化功率控制系统的设计方案和设计思想,采用了商品级计算机硬件、冗余联锁的软件、严格的质保措施、最终的半实物仿真实验,论证了数字化是可行的、可信的、安全的、经济的.     

秦山核电厂 30 万千瓦机组一回路平均温度的选择

反应堆一回路（ＲＣＳ）平均温度是压水堆核电厂的重要参数，对于电厂的安全、稳定及热效率关系很大。如何选择一个合适的设定点，需要考虑许多因素。由于饱和汽轮机的特点，使得这个问题更为复杂。本文重点讨论ＲＣＳ平均温度与电站热效率、堆芯安全、控制系统稳定等的关系。     

Seismic re-evaluation of nuclear facilities worldwide: overview and status

Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in the event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond the design basis. About two-thirds of the operating plants are conducting parallel programs for verifying the seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been re-evaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in the political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and upgrade the safety of their operating nuclear power plants. Finally, nuclear facilities in Asia are also being evaluated for seismic vulnerabilities. This paper focuses on the methodologies that have been developed for re-evaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide.     

A graded approach to cyber security in a research reactor facility

Recently, several accidents caused by cyber attacks on digital systems have been reported in the nuclear industry. To cope with such threats, regulatory agency and standardization organization have published several guidelines for nuclear power plants. However it is difficult to apply the requirements to research reactor facilities directly because the characteristics in terms of facility scale, purpose, and system design, are different from those of power plants. This paper suggests a graded approach to cyber security in a research reactor facility. It introduces cyber security activities for guarding digital systems of a reactor facility safely as a cyber security program based on the practices at a research reactor facility.     

核电厂信息安全问题研究及建议

信息和网络技术在核电厂的广泛应用,给核安全带来了新的威胁与挑战。本文深入分析了核电厂的信息安全现状以及面临的主要威胁,总结归纳了IAEA和美国NRC针对核电系统信息安全的研究成果、具体措施以及法规标准,最后结合中国的实际情况分析提出了关于保障我国核电厂信息安全的若干建议,为我国进行核电厂信息安全相关的决策及政策法规研究提供借鉴。     

Present status of nuclear containments and ISI in Korea

Since the first nuclear power plant started in commercial service in 1978 in Korea, 20 units have been operated and maintained, and most recently several units were under construction and planned to be constructed in order to meet the demand of more electricity. The importance of nuclear containments always has been one of the hottest issues for the safety and protection of nuclear power plants. From 1970s to present year, various types of nuclear containments have been constructed until now. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally a Korea standard nuclear power plant was defined. For those reasons, various regulatory issues, inspection technologies, technical requirements for periodic inspection have been applied differently depending on the specific nuclear containment types. In this study, overall status of nuclear power plants, development stages of nuclear containment systems, and inservice inspections in Korea were researched.     

核电厂辐射环境监督性监测系统选址和设计的思考和建议

本文基于某核电厂监督性监测系统建设的实践,同时参考其他核电厂的经验反馈对该系统选址和方案设计中容易疏忽以及需要关注的重点问题予以分析和讨论,提出相关建议,可供核电厂开展核电厂同类工作参考和借鉴。本文基于某核电厂监督性监测系统建设的实践,同时参考其他核电厂的经验反馈对该系统选址和方案设计中容易疏忽以及需要关注的重点问题予以分析和讨论,提出相关建议,可供核电厂开展核电厂同类工作参考和借鉴。     

核电厂堆外中子测量系统闪发高计数率问题研究

从故障现象、原因排查和解决措施三个方面,分析了我国核电厂近期发生的堆外中子测量系统闪发高计数率异常中所涉及的电缆接头问题和探头故障问题,提出了核电厂应关注堆外中子测量系统设备制造和安装的质量等建议,为解决和避免类似的堆外中子测量系统闪发高计数率问题提供借鉴。     

Plant Risk Effect Analysis Focusing on Digital I&C Equipment Failures

Safety-critical digital systems have been installed in nuclear power plants and thus their safety effect evaluation has become an emerging issue. The multi-tasking feature of digital instrumentation and control (I&C) equipment could increase the risk factor because the I&C equipment affects the actuation of the safety functions in several mechanisms. In this study, we quantify the safety of the digital plant protection system in Korean nuclear power plants based on probabilistic safety assessment (PSA) technology. Fifteen fault-tree models for the digital reactor-trip system and seven for the safety-feature actuation system are constructed and integrated into the plant safety assessment model. The result of the sensitivity study shows the boundaries of a plant risk and the effect of the digital equipment failures on the total plant risk.     

核电厂若干核安全管理问题的探讨

本文对核电厂安全管理中若干管理问题，如核电厂许可证制度、控制点制度、核电厂技术规格书、重大不符合项管理中若干问题进行了探讨和论证。是笔者对这些问题的体会、认识和见解。     

运行核电厂控制棒组件及其驱动机构异常事件的经验反馈

从1992年至2012年的我国核电厂以及其他国家核电厂的运行事件资料中,收集了17起与控制棒组件及其驱动机构相关的异常事件,对其进行了统计和分类,并分析了控制棒肿胀或燃料组件变形的影响、驱动机构焊缝的泄漏或渗漏、控制棒棒控系统的可靠性几个重要问题,提出了一些经验反馈的建议.