核电站计算机化规程设计的人因工程要求

在复杂的安全重要系统中,需使用规程支持人员任务,以减少失误并提高系统安全。在核电行业,随着数字化技术的发展,许多计算机化规程系统得到了开发和应用,可以支持操纵员进行信息搜集、判断决策和规程执行。在此基础上,IEEE 1786、IEC 62646和NUREG—0700等相关的人因工程标准导则对计算机化规程的设计和评审进行了规范。本研究调研了计算机化规程系统的设计和应用情况,从规程的呈现、规程步骤的标记、规程的管理、系统参数显示、参数监视与任务支持以及系统控制等方面进行了总结。在此基础上综述了相关标准导则的条款,并对计算机化规程的设计要求和一般设计原则进行了讨论。本研究希望通过总结相关信息,探讨计算机化规程人机接口设计的实践经验和人因工程要求,为设计和评估人员提供参考。     

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。     

操作规程的综合计算机化

规程的计算机化强调的不只是规程的呈现或显示方式，也强调它们是怎样产生和维护的。规程产生的计算机化将导致规程显示的基础提高，也使其通过内部表示的层次而不是在显示的层次上来维护规程成为可能。本文描述了一个工程．这个工程集中于发展一个基于认知系统工程规则的计算机化规程产生系统，使CPG系统与已有的计算机化规程显示系统结合．通过许多其它功能的提高来制造操作规程综合计算机化系统。     

计算机化运行规程在示范快堆中的开发

运行规程是指导核电厂运行人员对机组系统进行操作监护、处理各种故障及事故的指导文件。示范快堆采用数字化主控室,操作界面有大量实时参数显示。执行规程时,操作员需及时、准确地调取对应的画面。示范快堆对运行规程进行计算机化设计,将规程的步骤与相关操作画面链接,辅助操作员快速定位,有利于提高规程执行的效率,减轻操作员负担,降低人因失误。计算机化运行规程内容需与生效的纸质规程保持一致,这对规程计算机化开发的质量和效率提出了更高要求。示范快堆基于计算机化实施流程开发了一种规程编辑器,有助于保证纸质规程与计算机化运行规程的同步性和一致性,使计算机化运行规程有效应用于示范快堆。     

计算机化的核电厂操纵员支持系统

近十多年以来在国际核电界内计算机化的操纵员支持系统得到了委有大的发展。这个发展趋势在新核电厂控制室设计，旧核电厂控制室改进以及有关国际组织和有关国家对该研究基础上的开发划中都有体现。     

核电厂数字化人-机界面特征对人因失误的影响研究

以数字化主控室的现场调研和对操纵员的访谈内容为依据,分别从信息显示、用户界面交互与管理、控制系统、报警系统、规程系统等方面与传统的模拟控制系统进行了比较分析,识别数字化人-机界面新特征.结果显示,数字化人.机界面新特征对人因失误产生的不利影响主要表现为操纵员的认知负荷和操作负荷的增加,容易产生模式混淆、情境意识丧失等方...     

采用人工神经网络的基于征兆的核电厂运行诊断系统

核电厂运行过程中有许多瞬态过程，装置失灵、处理系统故障和安全系统失效都可能引起瞬态过程。这些瞬态过程可能导致电厂进入非期望的异常状态。如果电厂处于非期望状态(一般称为始发事件)，操纵员必须执行诊断和纠正措施，但是操纵员的反应可能太慢而不能减轻故障的不利影响。而本论文的目的是开发一种基于人工神经网络的操纵员支持系统，这个系统将辅助操纵员在始发事件的发展初期将其识别出来。电厂异常情况可通过处理仪表的读数来诊断和识别。基于征兆的诊断系统用于识别始发事件。该系统对始发事件的识别是通过使用弹性反传算法(Resilient Back Propagation Neural Network Algorithm)来实现。一旦识别出始发事件，系统将显示始发事件类型和必要的操纵员规程，还显示相关参数的趋势曲线。目前该系统能够识别Narora核电站的8个始发事件。本文将以一个始发事件为例，说明该诊断系统的特征。     

核电厂先进测量控制系统发展：ADIOS和ASICS

文章中讨论了两个系统：自动启动智能控制系统(ASICS)，它自动地控制压水堆核电厂从冷停堆到反应堆功率的5％；警报与综合诊断操纵员支持系统(ADIOS)，它把报警过程值和诊断信息集成到一个进行警报处理的专家系统中。根据核电厂启动操作的常规规程，核电厂是手动控制从冷态到5％功率的.在核电厂和其它电厂中，检查异常主要利用的资源是警报信息。传统的硬件报警系统以单传感器单指示器为特点。这将使控制室中的操纵员在面对纷至沓来的警报的瞬间产生思维混乱、设计自动启动智能控制系统(ASICS)和警报与综合诊断操纵员支持系统(ADIOS)以减轻操纵员的负担。计算机软、硬件和信息处理技术的发展，给核电厂和有相关过程的电厂的控制系统与报警系统的改善提供了一个好的机会。对于像ASICS和ADIOS这样以计算机技术或以软件技术为基础的系统来说，测试与评价它们的功能和性能是非常必要的ASICS和ADIOS的功能和性能的评价是在实时功能测试装置上进行的。结果表明：开发的系统对于运行和操纵员的支持是有效的。     

核动力装置运行支持系统的设计与开发

利用实时嵌入式操作系统VxWorks开发了核动力装置运行支持系统(NPPOSS),该系统可以利用计算机技术的优势给操纵员提供装置运行状态监测信息、警报分析信息、故障诊断信息以及应急操作规程等。本文对核动力装置运行支持系统进行了设计和开发,并以蒸汽发生器传热管破裂为例,在全范围仿真机上对该系统的可行性进行实验验证。结果表明,采用NPPOSS可以减轻操纵员的工作负担和精神压力,提高核动力装置的安全性。     

核电厂数字化SOP对人因失误的影响

主控室中数字化状态导向规程SOP(State-oriented Procedure)的应用使操纵员执行事故处理的逻辑和信息显示方式都发生了重大变化。本文介绍了SOP规程的原理,描述了数字化主控室中操纵员执行SOP处理电厂事故的流程。以核电厂主控室现场调研、行为观察、模拟机实验和操纵员访谈为依据,发现数字化SOP在操作控制、信息显示、班组合作等方面带来了大量可能导致人因失误的因素,以及可能出现的新的人误模式,可期为SOP规程的优化提供支持。     

核电厂计算机化规程系统开发

利用C语言在实时嵌入式操作系统 VxWorks上开发了一种用于正常操作的计算机化规程系统(CPS).本文介绍了系统的组成,并对人-机界面的设计进行了分析.以冷启动为例,验证了CPS的技术可行性.结果表明,CPS能够提高操作的准确性,减轻运行人员的工作负担.     

Computerized procedure system for the APR1400 simulator

The ShinKori Unit 3&4 which is the reference plant for APR1400 simulator plans to utilize various display devices and computerized Human Machine Interface (HMI) as well as many kinds of digitalized instrumentation and control. The operating crew will be given a lot of information on display devices in order to diagnose the system states and control devices. And with the limitations of paper-based procedure (PBP) including lack of interactive capabilities between the PBP and sophisticated systems, and the high volume and cost associated with paper manuals used in complex and technically demanding environments, the computerized procedure system (CPS) is developed as a part of computerized systems for APR1400 simulator. The developed CPS covers all operating procedures including normal, abnormal and emergency, and provides information through workstation consoles using flowchart and tree structure and also has automatic checking capabilities of step logic including continuously applied steps. The CPS consists of Procedure eXecution System (PXS), and Engineering System (ES) including procedure editor (PED) and Non-Integrated System Test System (NISTS). The PXS is the execution system for the procedure provided to the operators and has the following functions. 1) Display of the plant status information necessary for the instructions and executions for the procedure, 2) auto-check functions instead of manual monitoring based on the paper-based procedures, 3) detection and recovery functions of operators’ faults, 4) generation function of the LCP (Logged Computerized Procedure) to search the results of the procedure execution, 5) generation function of the Log Paper Procedure supporting the continued operation using the paper procedure when the CPS fails. The ES (Engineering System) is the environment provided to the writer and maintainer of the CP (Computerized Procedure), the application program loaded in the PXS. The CP is frequently revised in the plant, and related to the safety of the plant. Therefore, the CP is provided to secure the quality and convenience of the developed procedure. For the verification, among the implemented computerized procedures by using PED, a procedure for the LOCA (Loss-Of-Coolant Accident) is selected for testing the integrity of the CPS including communication between CPS and other systems for APR1400 simulator, which is proved to be well implemented. Currently, the implemented CPS is being used to the Preliminary Validation Phase II Test hosted by NETEC (Nuclear Environment TEChnology Institute) in Korea.     

Modeling of computerized procedure execution with State Token Petri Net for formal verification of procedure flow

Computerized procedure system (CPS) is one of the primary operating support systems in the digital main control room (MCR) of a nuclear power plant. CPS displays the procedure at computer screen in the form of a flow chart and displays plant operating information along with procedure instructions. It also supports the operator to make a decision by providing system decision with logic. Most importantly, CPS guides the operator to follow a procedure flow that is predefined when the computerized procedure (CP) is written. A procedure flow should be correct and reliable, as error would lead to operator misjudgment and inadequate control. As such, the procedure flow should be verified before being applied to the MCR. In this article, we present a model of CPS that enables formal verification based on Petri nets. The proposed State Token Petri Net also supports modeling of a procedure flow that has various interruptions by the operator according to the plant condition.     

Experimental studies of computerized procedures and team size in nuclear power plant operations

The operation of a nuclear power plant is so complex that it requires teamwork. To support team performance, a system need to provide all team members integrated information displays as well as decision aids (e.g., computerized procedures). Two experiments were conducted to investigate the effects of computerized procedures and team size on operating performance. Forty-five participants were involved in the experiments. Each participant executed decision and action tasks to deal with alarm signals, while detecting occasional system errors in the interface. Results showed that effects of computerized procedures were significant on various performance indicators, such as operation time, operation errors, and learning effect, and that two operators would be a satisfactory size in the teamwork system providing computerized procedures.     

A neural network based operation guidance system for procedure presentation and operation validation in nuclear power plants

An operation guidance system (OGS) was developed to regulate and supervise operators’ actions during abnormal environments in nuclear power plants (NPPs). The system integrated a primitive computerized procedures system (CPS) and an operation validation system (OVS) imbedded in a virtual simulated operational environment. As the key component of the OGS, OVS provided two important functions for the operators: validated check of operations, and qualitative and quantitative effects analysis of operations. Each of operators’ action was evaluated by the system and possible results were simulated by using artificial neural networks (ANN). Finally, corresponding suggestion or warning was provided to operators. This should reduce human errors during operation in emergency scenarios.     

Guidelines for computerized presentation of emergency operating procedures

New methods of information presentation and interface design have changed the work conditions in the modern nuclear power plant control room. One area that is receiving considerable attention is that of procedures—in particular, emergency operating procedures (EOPs). Such procedures are traditionally available as printed documents; however, developments in information technology have created new opportunities for procedure presentation, and this paper reports on the development of human factor guidelines for computerized presentation of EOPs. After identifying the principle stages in the transition from procedures as documents to fully automated procedures, computerized procedure presentation (CPP) is briefly discussed. Guidelines for the presentation of such are outlined, starting with the high level goals that also constitute the criteria against which the computerized procedures are measured during implementation. Six dimensions that describe CPP are presented and explored in detail, by identifying points in each dimension that characterize different levels of information technology sophistication.     

高温气冷堆核电站计算机化运行规程方案及异常事件处理规程入口识别

根据高温气冷堆核电站计算机化运行规程系统的设计准则,给出了高温气冷堆核电站计算机化运行规程的总体设计方案,指出计算机化运行规程系统的一个重要作用就是提供规程入口选择。高温气冷堆核电站的异常事件处理规程是基于事件的,因此选择规程入口的关键在于异常事件的识别。为解决该问题,采用具有图形描述能力和严密数学理论的模糊Petri网,构建了异常事件识别专家系统。相较于传统方法,模糊Petri网结构化特性和知识表达能力更强,推理效率大幅提高,便于计算机编程实现。通过典型异常事件识别的仿真,表明所构建的异常事件识别专家系统是合理可行的,为高温气冷堆核电站计算机化运行规程系统的研制打下了基础。     

Experience and technical issues of liquid lithium application as plasma facing material in tokamaks

The following critical issues of liquid lithium used in tokamak conditions are considered: major physical properties of lithium, physico-chemical aspects of lithium interaction and compatibility with structural materials of fusion reactors. Lithium capillary-porous system (CPS) is considered as advanced plasma facing material for power fusion reactor and its main properties are presented. Review of plasma facing element (PFE) structures based on lithium CPS and tests results in T-11M, T-10 and FTU tokamaks are included. Brief review of projects of lithium limiter of FTU with active system for thermal stabilization and module of lithium divertor for KTM tokamak with liquid metal (Na-K) cooling system based on the lithium CPS use are presented.     

失效评定图（FAD）技术在核管道缺陷评定规程编制中的应用

本文介绍了失效评定图（ＦＡＤ）技术的概念，用ＦＡＤ进行管道失效模式的判别，以及裂纹稳态撕裂扩展分析，进而预测承载能力的方法。对ＡＳＭＥ锅炉压力容器规范Ⅺ卷中核管道缺陷评定规程的技术难点以及在使用ＦＡＤ时所做的特殊处理及其背景作了分析和探讨。