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.     

Physics basis for the advanced tokamak fusion power plant, ARIES-AT

The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A≡R/a=4.0, an elongation and triangularity of κ=2.20,δ=0.90 (evaluated at the separatrix surface), a toroidal beta of β=9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of β_N≡100×β/(I_P(MA)/a(m)B(T))=5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is f_BS≡I_BS/I_P=0.91. This leads to a design with total plasma current I_P=12.8  MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.     

核电机组电气设计分析

近年来,我国核电事业得到快速发展,一大批核电项目陆续开工建设,其中大部分为引进技术的二代改进型和三代核电机组。由于技术输出国的标准规范与我国现有的核电设计标准不一致,以及考虑厂址适应性等问题,我国对引进的核电机组存在逐步消化、吸收并改进的过程。本文对核电机组的电气设计进行探讨,希望对今后同类工程具有参考作用。     

Structural integrity analysis of an Ignalina nuclear power plant building subjected to an airplane crash

Recent terrorist attacks using commandeered commercial airliners on civil structures have raised the issue of the ability of nuclear power plants to survive the consequences of an airliner crash. The structural integrity analysis due to the effects of an aircraft crash on an Ignalina nuclear power plant (INPP) accident localization system (ALS) building is the subject of this paper. A combination of the finite element method and empirical relationships were used for the analysis. A global structural integrity analysis was performed for a portion of the ALS building using the dynamic loading from an aircraft crash impact model. The local effects caused by impact of the aircraft's engine on the building wall were evaluated independently by using an empirical formula.The results from the crash analysis of a twin engine commercial aircraft show that the impacted reinforced concrete wall of the ALS building will not have through-the-wall concrete failure, and the reinforcement will not fail. Strain-rate effects were found to delay the onset of cracking. Therefore, the structural integrity of the impacted wall of the INPP ALS building will be maintained during the crash event studied.     

Optimization of a dynamic uncertain causality graph for fault diagnosis in nuclear power plant

Fault diagnostics is important for safe operation of nuclear power plants (NPPs).In recent years,data-driven approaches have been proposed and implemented to tackle the problem,e.g.,neural networks,fuzzy and neurofuzzy approaches,support vector machine,K-nearest neighbor classifiers and inference methodologies.Among these methods,dynamic uncertain causality graph (DUCG)has been proved effective in many practical cases.However,the causal graph construction behind the DUCG is complicate and,in many cases,results redundant on the symptoms needed to correctly classify the fault.In this paper,we propose a method to simplify causal graph construction in an automatic way.The method consists in transforming the expert knowledge-based DCUG into a fuzzy decision tree (FDT) by extracting from the DUCG a fuzzy rule base that resumes the used symptoms at the basis of the FDT.Genetic algorithm (GA) is,then,used for the optimization of the FDT,by performing a wrapper search around the FDT:the set of symptoms selected during the iterative search are taken as the best set of symptoms for the diagnosis of the faults that can occur in the system.The effectiveness of the approach is shown with respect to a DUCG model initially built to diagnose 23 faults originally using 262 symptoms of Unit-1 in the Ningde NPP of the China Guangdong Nuclear Power Corporation.The results show that the FDT,with GA-optimized symptoms and diagnosis strategy,can drive the construction of DUCG and lower the computational burden without loss of accuracy in diagnosis.     

田湾核电站堆芯装换料管理子系统设计

田湾核电站机组堆芯采用堆内倒换换料技术,装换料管理子系统是燃料管理系统的子系统之一,它以直观的图形操作方式协助管理人员完成核燃料堆芯装卸料的步序设计和优化工作.该子系统为纯B/S结构,采用ASP.NET平台、矢量绘图、暗通道提交、图片缓存等技术.本文介绍了该子系统的设计思路,重点阐述了图形交互技术的实现方法.     

核电站设备三维模型设计的基本准则和应用实践

详细介绍了三维设备模型设计在核电站中的实际应用,概括了建模准则的制定、程序编制、模型建立、项目实践的全过程。阐述了作为数字核电站的重要组成部分——三维设备模型设计的基本准则和应用实践,从而进一步验证了数字电厂主要结构体系和程序配置的合理性、有效性,对核电站全寿期管理概念的具体实践进行了有益的尝试,并取得了良好的应用成果。为三维设备模型更深入地应用于大亚湾、岭澳核电站的运行、维修模拟以及岭澳二期、广三核项目的工程设计管理,奠定了可靠的工作基础。     

自主化1000MW级压水堆核电站核蒸汽供应系统概念设计

本文简介介绍了我国百万千瓦级压水堆核电站（ＣＮＰ１０００）核蒸汽供应系统的概念设计,主要内容为主要技术参数、堆芯设计、反应堆冷却剂主回路系统及其主要设备设计、安注系统、辅助给水系统和数字化仪表与控制系统设计。     

核电厂厂址选择阶段的总图运输设计

简要地介绍了核电厂厂址选择阶段的总图运输设计的基本任务、规则设计，并讨论了建设子项的确定、主厂区平面设计、竖向布置和防设计基准共水位等技术问题。     

An interface redesign for the feed-water system of the advanced boiling water reactor in a nuclear power plant in Taiwan

A well-designed human-computer interface for the visual display unit in the control room of a complex environment can enhance operator efficiency and, thus, environmental safety. In fact, a cognitive gap often exists between an interface designer and an interface user. Therefore, the issue of the cognitive gap of interface design needs more improvement and investigation. This is an empirical study that presents the application of an ecological interface design (EID) using three cases and demonstrates that an EID framework can support operators in various complex situations. Specifically, it analyzes different levels of automation and emergency condition response at the Lungmen Nuclear Power Plant in Taiwan. A simulated feed-water system was developed involving two interface styles. This study uses the NASA Task Load Index to objectively evaluate the mental workload of the human operators and the Situation Awareness Rating Technique to subjectively assess operator understanding and response, and is a pilot study investigating EID display format use at nuclear power plants in Taiwan. Results suggest the EID-based interface has a remarkable advantage over the original interface in supporting operator performance in the areas of response time and accuracy rate under both normal and emergency situations and provide supporting evidence that an EID-based interface can effectively enhance monitoring tasks in a complex environment.     

结构材料常规疲劳数据库开发

开发了反应堆结构材料常规疲劳数据库管理系统,库中包含了常规疲劳设计分析曲线参量,即应力－寿命、概率－应力－寿命、应变－寿命、概率－应变－寿命、循环应力－应变及概率－循环应力－应变曲线参量,以及相关材料和试验条件信息。可通过材料名称或机械性能区间指标查询。根据查询结果,可进行常规疲劳设计分析与评价或常规疲劳可靠性设计分析与评价。     

Applications of fault detection and diagnosis methods in nuclear power plants: A review

Nuclear power industries have increasing interest in using fault detection and diagnosis (FDD) methods to improve safety, reliability, and availability of nuclear power plants (NPP). A brief overview of FDD methods is presented in this paper. FDD methods are classified into model-based methods, data-driven methods, and signal-based methods. While practical applications of model-based methods are very limited, various data-driven methods and signal-based methods have been applied for monitoring key subsystems in NPPs. In this paper, six areas of such applications are considered. They are: instrument calibration monitoring, instrumentation channel dynamic performance monitoring, equipment monitoring, reactor core monitoring, loose part monitoring, and transient identification. The principles of using FDD methods in these applications are explained and recent studies of advanced FDD methods are examined. Popularity of FDD applications in NPPs will continuously increase as FDD theories advance and the safety and reliability requirement for NPP tightens     

核电厂流程整理和优化试点项目的实施

为使江苏核电有限公司(以下简称"JNPC")的质量管理体系的适用性、操作性得到进一步提升,从扩建工程的程序体系入手,引入跨行业的先进经验和在程序管理领域的良好实践,JNPC组织实施了流程整理和优化项目的规划及试点工作。希望通过项目的开展,能够实现业务过程端到端的管理,减少不增值流程。     

Fusion neutron test facility requirements for interactive effects in structural and high-heat-flux components

A relevant design data base is needed for structural components in near-term and commercial fusion devices. A high-flux, high-fluence fusion neutron test facility is required for testing the failure mechanisms and lifetime-limiting features for first wall, blanket, and high-heat-flux components. We describe here the key aspects of the fusion environment which influence the response of structural and high-heat-flux components. In addition to test capabilities for fundamental radiation-effects phenomena, e.g., swelling, creep, embrittlement, and hardening, it is shown that the facility must provide an adequate range of conditions for accelerated tests to study the limitations on component lifetime due to the interaction between such fundamental phenomena. In high-heat-flux components, testing of the failure mechanisms of duplex structures is shown to require maintenance of an appropriate temperature gradient in the 14-MeV neutron field. Thermal stresses are shown to result in component failure, particularly when the degradation in the thermal conductivity and mechanical properties by irradiation are considered. Several factors are discussed for assessment of the failure modes of the first wall and blanket structures. These are displacement-damage dose and dose rate, the amount of helium gas generated, the magnitude of irradiation and thermal creep, prototypical temperature and temperature-gradient distributions, module geometry, and external mechanical constraints.     

从某核电站运行情况分析今后辐射监测系统设计的改进

以巴基斯坦恰希玛核电站一期辐射监测系统近两年测量数据为依据,对该核电站辐射监测仪表的运行工况进行分析.结果表明:绝大部分辐射监测仪表处于正常运行状态,部分仪表偶尔会出现异常数据.根据工艺过程特点分析了辐射监测仪表出现异常数据的可能性原因,并对辐射监测系统设计的改进提出了建议,供今后核电站辐射监测系统设计参考.     

核电厂选址及环境影响评价应关注的问题

结合近年来我国核电厂选址工作,根据核安全以及环境保护的有关法规要求,重点分析了我国核电厂选址及环境影响评价的特点,并提出了我国核电厂选址及环境影响评价应关注的问题。     

Design of structural components for the helical reactor FFHR-d1A

FFHR-d1 is a conceptual design of the helical reactor being developed at the National Institute for Fusion Science. The maintenance of in-vessel components is very important for the fusion demo reactor. In addition, sufficient pathways are needed for the divertor exhaust. To implement these, the vacuum vessel, coil support structure, and cryostat require large apertures. However, the coil support structure has to be sufficiently rigid to remain within soundness and deformation limits. A design combining the structural components in the FFHR-d1A was developed from mechanical and thermal viewpoints. Consequently, components having a sufficiently large port area were provided. An investigation of the maintenance and exhaust schemes has been planned on the basis of this fundamental design.     

我国核电厂放射性废物管理进展及挑战

分析了我国核电厂放射性废物管理现状;指出了核电厂放射性废物管理面临的挑战;提出了包括进一步完善法规标准、完善放射性管理体制、加强群堆核电厂放射性废物管理、鼓励技术创新和产学研结合等加强核电厂放射性废物管理的应对措施。     

核电站核岛物项质量控制信息化实现

根据核电站核岛物项质量管理模式,阐述了核电站核岛物项质量控制信息化实现的设计思路、实现方法和一些关键技术,说明了核岛物项质量控制方式可以提高核岛质量、保证核电站的安全、降低核电站建造和运营成本。     

核电厂土建施工三大原材料质量控制

核电厂的建造运行是一项系统工程。为了保证核电厂的质量安全,从设计立项到运行使用,每一个环节的工作都对质量安全产生不同程度影响。与之相关的每一步工作都必须做到质量受控。从核电厂建造过程中土建施工环节中的原材料质量控制入手,着重分析了土建施工中钢材、混凝土材料、模板材料三大主材如何实施质量控制和管理。