核电站风险监测器软件开发研究

在大型概率安全分析软件系统Risk A的基础上,开发了具有自主知识产权的核电站风险监测器Risk Amgel.使用Risk watcher及大亚湾核电站的部分参考模型对Risk Angcl系统进行了测试.测试结果表明,Risk Angel完全可以用于核电站实时风险的计算.     

秦山核电厂环境γ剂量率连续监测系统

本文介绍秦山核电厂环境γ剂量率连续监测系统，该系统由监测器，数据采集器，气象站和中心计算机组成，讨论了区分由核电厂排放引起的剂量率的升高斩方法，其监测灵敏度为３ｎＧｙ／ｈ。     

某核电厂在线风险评价与管理系统开发概况

核电厂在线风险评价与管理系统能够反映核电厂特定配置状态下的风险信息,对于核电厂的风险管理和综合决策的制定具有重要意义,在国内外进行了广泛的研究和应用。核电厂在线风险评价与管理系统采用能够反映电厂实际配置状态的低复杂度实时风险模型,系统软件通过接口程序读取电厂自动化系统中的电厂配置信息,利用智能并行计算技术对电厂配置状态进行高效风险分析,为电厂的安全管理提供风险依据。本文对某核电厂在线风险评价与管理系统的开发背景、总体框架、功能模块以及相关的关键技术进行了概要介绍,并对该在线风险评价与管理系统分析结果进行了验证,其结果能够正确反映电厂风险信息,具有实际的应用意义。     

海南“大机小网”下核电厂安稳策略研究

在核电机组投运后,海南"大机小网"问题比较突出。综合分析核电机组运行方式、故障方式、稳定和控制措施等相关情况,按联网和孤网运行方式对核电厂接入系统的稳定性进行深入探讨,提出针对核电厂安稳系统的策略功能及详细配置方案。比较和分析了核电厂安稳系统运行管理方式及主要风险,为其他核电厂安稳系统的设计及运行管理提供参考。     

控制核电厂多个系统不可用时的叠加风险的研究

本文的目的是基于核电厂可用的资源，建立一套控制核电厂的多个系统不可用时的叠加风险的方法。主要方法是研究现有的几种控制叠加风险的手段，比较各自的优点、缺点和所需资源，最后以确定论为基础，以概率论的方法为补充，建立一套现实可行的方法。该方法基于核电厂设计，在技术规格书管理的系统和功能范围内建立支持-被支持系统关系矩阵。建立合理的安全功能鉴定流程，基于支持-被支持关系矩阵开展安全功能鉴定，以确保任何安全功能的丧失都能被监测到。根据安全功能丧失的情况，采取最合适的措施来限制叠加风险。设定最长允许停役时间，以避免不可用系统的修复时间不合适的延长。对冗余系统或部件补充安排试验或维修，避免重大风险配置的发生。     

标准监管PSA模型开发与应用

本文介绍了NRC标准化电厂风险模型(SPAR)的发展历程以及在风险指引型安全监管活动中的应用情况和发展趋势。基于核电厂性能和风险指引型的安全监管理念,开发国内核电厂的标准监管PSA模型,本文重点介绍了模型开发的技术路线、分析范围、开发周期与计划,并对该模型拟在风险指引型的监管活动中的应用前景。标准监管PSA模型是作为核安全监管当局作为独立评价和验算核电厂PSA应用的重要工具之一,是保证国家核安全局对核电厂的安全监管活动的独立性和技术权威性的重要手段。     

压水堆核电厂地震概率安全评价开发方法研究

福岛核事故引发了全球范围内对核电厂地震风险的重新审视。我国是地震多发国家,同时在可以预期的未来多年内是世界上最大的核电建造国,因此应重视核电厂的地震风险。现有核电厂的抗震设计主要是基于确定论设计,难以全面评估核电厂地震风险的大小。核电厂地震概率安全评价是利用概率论方法评估核电厂地震风险的有效方法,对核电厂抗震薄弱环节识别和抗震安全改进具有重要意义。文章全面介绍了压水堆核电厂地震概率安全评价方法的开发流程和技术要素,指出了应在核电厂地震概率安全评价中考虑的重要因素和处理方法,为国内核电厂地震概率安全评价工作提供参考。文章建议尽快完善我国核电厂地震概率安全标准体系建设,指导国内核电厂广泛开展地震概率安全评价工作。     

核电厂仪控系统功能安全与网络安全

传统核安全监管聚焦功能安全，针对核电厂仪表和控制系统（仪控系统）功能安全，目前已建立了较为完备安全标准体系，形成良好监管实践。信息网络技术在核电厂仪控系统的广泛应用带来网络安全风险，如何正确处理功能安全和网络安全问题成为关注热点。通过概念溯源和文献研究，进一步理清了功能安全与网络安全概念的内涵，系统梳理了当前核电领域功能安全和网络安全的建设实践并简要分析其核心保护理念。以此为基础，分析讨论核电厂功能安全和网络安全之间相互关联又矛盾冲突的复杂关系。为后续建立核电厂网络安全标准体系奠定了基础。     

核电厂化学管理系统分析研究

详细说明核电厂化学管理系统的主要功能、主要作用、使用的主要流程,并介绍它在国内外的使用现状。结合开发化学数据管理系统的经验,探讨在核电厂化学管理中开展和应用人工智能技术,以满足核电厂安全、可靠、经济地运行的需求。     

核电厂声学泄漏监测系统的设计和验证

介绍VVER-1000型核电厂声学泄漏监测系统的设计基准和功能,给出判断泄漏过程、确定泄漏量和泄漏位置的系统算法。建立主回路声模型结构图,计算得到环路背景噪声分布,并和实际机组上的试验结果进行对比。建立管道模型的试验台架,并对管道模型进行了试验验证。根据试验数据得到用于计算泄漏量大小和泄漏位置的相关系数。通过核电厂声学泄漏监测系统的设计和验证,为开发田湾核电厂1、2号机组在线的核电厂声学泄漏监测系统奠定了基础。      

Knowledge-based software design for Defense-in-Depth risk monitor system and application for AP1000

As part of the new risk monitor system, the software for the plant Defense-in-Depth (DiD) risk monitor system was designed based on the state-transition and finite-state machine, and then the knowledge-based software was developed by object-oriented method utilizing the Unified Modeling Language (UML). Currently, there are mainly two functions in the developed plant DiD risk monitor software that are knowledge-base editor which is used to model the system in a hierarchical manner and the interaction simulator that simulates the interactions between the different actors in the model. In this paper, a model for playing its behavior is called an Actor which is modeled at the top level. The passive safety AP1000 power plant was studied and the small-break loss-of-coolant accident (SBLOCA) design basis accident transient is modeled using the plant DiD risk monitor software. Furthermore, the simulation result is shown for the interactions between the actors which are defined in the plant DiD risk monitor system as PLANT actor, OPERATOR actor, and SUPERVISOR actor. This paper shows that it is feasible to model the nuclear power plant knowledge base using the software modeling technique. The software can make the large knowledge base for the nuclear power plant with small effort.     

秦山三期重水堆核电站风险监测器研发进展

核电站风险监测系统(Risk Monitor)可对核电站的运行风险进行实时监测和预测,是概率安全评价(PSA)技术的高级应用之一.FDS团队广泛调研了国际现有核电站风险监测系统的研发现状,深入研究了风险监测系统涉及的各种关键算法并探索了相关实现技术,基于前期自主研发的大型集成概率安全分析软件RiskA发展了通用核电站风...     

风险监测系统中实时风险模型研发及其应用初步研究

风险监测系统因其实时性要求物理基础实时风险模型能够反映核电站任意时刻的任意配置状态.实时风险模型是在运行阶段风险模型基础上按照一定转换规则升级而得到.本文给出了实时风险模型的通用转换规则,并实现某重水堆的实时风险模型构建.结果证明,该重水堆实时风险模型能够良好地运行于FDS团队自主研发的风险监测系统软件RiskAnge...     

A human–machine interaction design and evaluation method by combination of scenario simulation and knowledge base

A method of designing and evaluating HMI (human–machine interaction) is proposed for the design in supervisory control of fully digitalized I&C (instrumentation and control) and digitalized human–machine interface system, which is a large-scale complex system in the NPPs (nuclear power plants). The proposed method consists of plant accident scenario simulation, knowledge base establishment, and interaction simulation. The plant accident scenario simulation is to analyze the plant behavior and system sequences under the predefined conditions; the knowledge base is modeled based on the simulation results as human and machine roles; and the interaction simulation is to simulate the interactions such as between operator and plant, operator and technical advisor. The proposed method utilizes the object-oriented software named plant DiD (defense-in-depth) risk monitor with the combination of accident simulation by an advanced nuclear safety analysis code such as RELAP5/MOD4. The practical developments for the details are demonstrated using an example practice for the SBLOCA (small break loss of coolant accident) case of passive safety PWR (pressurized water reactor) AP1000.     

Risk assessment of nuclear power plants

The objective of the present work is to develop recommendations for controlling the safety of nuclear power plants on the basis of risk assessments and safety certification of nuclear power plants. The Kursk nuclear power plant is considered as an example of a nuclear power plant with an RBMK reactor. The concept of risk assessment of a nuclear power plant consists in constructing a set of scenarios of the appearance and development of possible accidents followed by an evaluation of the realization frequency and determination of the scales of the consequences of each one. The result of an analysis is an evaluation of a system of risk indicators in accordance with the requirements of the safety compliance certificate of the nuclear power plant as well as the development of recommendations for increasing plant safety. In risk assessment, the consequences are divided into categories of the seriousness of the damage, for which their probability is evaluated separately. The graphical interpretation of risk due to any dangerous object consists of frequency–consequences curves. Recommendations are developed on the basis of the results of risk analysis.     

A framework for nuclear power plant emergency response system

<正>The purpose of this study is to establish an intelligent expert system for nuclear power plant emergency response.A new framework of environmental risk management methodology by the concept of pattern recognition was introduced in this paper.A knowledge-based decision support system for emergency response and risk management of nuclear power plant was also discussed.The mathematical pattern relationship of accidental release effects on neighboring area and the corresponding response measures were presented in this paper.With this decision system,the decision maker can specify the procedure and minimize their human error in the decision process.The improvement of risk response and the quality of management system could be upgraded by this system.Besides,the methodology can also be served as a basis for the future development of environmental risk response system design.     

核电站蒸汽发生器泄漏监测——氮-16辐射监测仪概述

蒸汽发生器是压水堆核电站核蒸汽供应系统的主要设备之一,对蒸汽发生器传热管进行泄漏监测关系到核电站的安全和经济运行。介绍了用于蒸汽发生器泄漏监测的氮-16辐射监测仪的概况、工作原理、系统组成等。     

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。     

计算机化规程系统在APIO00中的应用

数字化仪控技术在核电厂的推广,为计算机化规程系统（CPS）在以APl000为代表的三代先进压水堆中的应用提供了技术基础。本文对计算机化规程系统的结构、功能和特点进行了描述,CPS作为先进的规程系统,不仅将运行规程以电子化的形式显示在电脑屏幕上,而且同时能监测和处理电厂参数,为操纵员提供规程执行指导,并且显著提高了规程的执行效率。另外,本文还将APl000中的CPS与某M310;0H改进型核电厂的数字化规程系统进行了比较,并结合实际CPS的本土化以及存在问题进行探讨。