数字化核电站SGTR事故操纵员认知分析

核电站主控室数字化后的人因特征包括数字化规程、警报系统、操作班组信息共享、界面管理任务,它们对操纵员认知可靠性都有重要影响。IDA认知模型把操纵员认知过程分为信息(Information)、诊断(Diagnosis)/决策(Decision)、执行(Action)3个阶段。按IDA模型把数字化核电站主控室操纵员SGTR事故认知过程分为3个阶段,对每个阶段进行操作分析,找到操纵员在SGTR事故认知过程各阶段最容易发生的失误和主要失误。操纵员认知失误发生的原因在于界面管理任务增大了认知难度以及数字化后缺乏情景意识等。     

核电厂核事故应急疏散研究

根据我国法规、标准与美国核管委对核电厂核事故应急疏散的要求,考虑我国核电厂特殊的厂址条件与社会环境,分析核事故应急疏散的可行性。通过应急疏散行为研究、厂区的交通需求估计和路网分析,对不同情境,考虑核事故应急疏散的特殊问题,分别采用人工容量分析与宏观仿真模拟得到应急疏散时间。针对某核电厂,给出核事故应急疏散分析的一般步骤、方法与计算结果。对宏观仿真模型的主要参数进行灵敏度分析,找出影响应急疏散时间的主要因素,提出缩短应急疏散时间的针对性措施。     

石油石化重大工艺安全事故应急机制浅析

石油石化生产关键工艺设备或流程蕴藏的风险能量巨大,一旦发生事故,后果往往极其严重。分析了石油石化重大工艺安全事故专业性强、事故规模大、易形成连锁反应和诱发环境污染事件等3个典型特征。通过事故应急经验分析,研究提出了石油石化重大工艺安全事故应急工作需要遵循的风险辨识充分到位、专业应急保障有力、应急资源保障充足、企地联动迅速高效、社会舆论引导得力等5方面的重点应急策略。设计了工艺安全事故风险辨识与评估、专业应急队伍建设与能力提升、应急资源联合储备、区域应急联动和公共危机公关等5项石油石化企业重大工艺安全事故应急重点工作机制内容和建设要点。石油石化企业需要不断建立和完善5项应急工作机制,才能为重大工艺安全事故应急工作提供可靠保障。     

Extension of TACOM to the complexity of tasks designed for abnormal situations in nuclear power plants

TACOM (TAsk COMplexity) is a measure for evaluating the complexity of tasks prescribed for emergency situations in nuclear power plants. Five sub-measures constituting TACOM represent five different aspects of the task complexity exhibited in operating procedures for emergency situations. The practicality of TACOM has been verified through a series of empirical studies. However, tasks designed for abnormal situations that can significantly affect the safety of nuclear power plants, also need a proper measure for evaluating their complexity. TACOM provides a process, a systematic cognitive task analysis method and a set of guidelines to support its application. Therefore, although the characteristics of abnormal task situations are not the same as those of emergency situations, TACOM seems to be reasonably applied to abnormal situations or at least to offer meaningful insights for developing a measure for evaluating the complexity of tasks in abnormal situations. Thus this study examined the applicability of TACOM to abnormal situations through case studies. Particular attention was paid to the sufficiency and appropriateness of the three methodological tools, which are the process, the cognitive task analysis method and the set of guidelines. Collective consideration of the case studies and the characteristics of tasks prescribed for abnormal situations led us to draw the conclusion that TACOM could be reliably used for abnormal situations as well. This paper reports the process of how to apply TACOM to the tasks of abnormal situations and discusses some lessons learned through this application.     

An integrated framework to the predictive error analysis in emergency situation

This paper introduces an analysis framework and procedure to predictively analyze human errors in performing emergency tasks, which are mostly composed of cognitive activities, in nuclear power plants. The framework focuses on the cognitive errors and provides a new perspective in the utilization of context factors into cognitive error prediction. The basic viewpoint on the occurrence of cognitive error taken in this paper is that the cognitive function failures occur from the mismatch between operator's cognitive capability and the requirements of a given task and situational condition. In accordance with this viewpoint, performance influencing factors that influence the occurrence of human errors are classified into three groups, i.e. Performance Assisting Factors (PAF), Task Characteristic Factors (TCF), and Situational Factors (SF). This classification helps analysts view the overall task context in an integrative way by considering the level of PAF with the requirements of TCF and SF to predict the possibility of cognitive function failures. Further, it enables analysts to draw specific error reduction strategies. The framework suggested was applied to the analysis of cognitive error potential for the bleed and feed operation of emergency tasks in nuclear power plants.     

基于层次分析方法的核电火灾风险评估研究

核电火灾是现代消防安全的重要部分。依据核电厂的实际组成构造对其进行了层次划分,建立了由堆本体、一次冷却系统、化容控式系统堆安全系统、汽轮发电机组和燃料操作系统为中间层的核电火灾危险性评价指标体系。结合收集到的相关核电事故数据资料,运用层次分析法对核电厂各系统部位引发火灾造成的核电安全风险进行了评估,确定了各组分的统计权重,得到了针对核电厂各构造部位的火灾危险性层次评价模型。并利用评价打分的方法对核电厂进行调查模拟评价,计算出核电厂各组成部分消防安全状况的危险指数,所得结果比较符合核电火灾实际统计。     

The research on extracting the information of human errors in the main control room of nuclear power plants by using Performance Evaluation Matrix

Digitalized nuclear instruments and control systems have been the main stream design for the main control room (MCR) of advanced nuclear power plants (NPPs) nowadays. Digitalization of human–system interface (HSI) could improve human performance and, on the other hand, could reduce operators’ situation awareness as well. It might cause that humans make wrong decision during an emergency unintentionally. Besides, digital HSI relies on computers to integrate system information automatically instead of human operation. It has changed the operator’s role from mainly relating operational activity to mainly relating monitoring. However, if the operators omit or misjudge the information on the video display units and wide display panel, the error of omission and error of commission may occur. This study applies Content Category Analysis (CCA) and Performance Evaluation Matrix (PEM) methods to explore the potential problems in the MCR of advanced NPPs which are caused by human errors. The results show that the potential problems that would probably contribute to the human performance of MCR in the advanced NPPs are multiple accidents, pressure level, number of operators, and other factors such as working environmental. The conclusions of this research may be considered to avoid and prevent human errors in the human factor related researches especially in the nuclear safety field.     

基于三维GIS的火电厂应急救援决策支持系统研究

针对火电站事故灾害的应急救援工作、电厂应急预案制定的现状,提出基于三维GIS的火电厂应急救援决策支持系统,对火电厂区及周边环境进行虚拟现实仿真,实现对基础地图数据、应急资源数据、重大危险源及其相关属性数据的系统科学管理,以Web方式提供信息查询服务,实现重大危险源周边的三维仿真显示,预测事故影响及其后果,提供最佳路径及救援方案。该研究为火电站及有关部门实施远程应急救援决策提供科学依据。     

Evaluation and comparison of alarm reset modes in advanced control room of nuclear power plants

An automation function has been widely applied in main control room of nuclear power plants (NPPs). The alarm system of fourth nuclear power plant (FNPP) in Taiwan is also going to be developed with automatic technology that is expected to support the operators’ performance and reduce the number of alarms. In this study, an experiment with a training simulator as an advanced alarm system was conducted to compare the effects of different alarm reset modes on performance and subjective ratings. The objective was to evaluate the practicability of alarm system with only auto-reset function in FNPP. Results revealed that, using the auto-reset mode, participants had lower task load index (TLX) on effort in the first test trial and was more satisfied under multi-task condition. In contrast, using manual reset mode, participants were more satisfied on alarm handling, monitoring, and decision making. In other words, both reset modes are necessary to assist the operator in different aspects, but with only single reset mode is insufficient. The reset function in advanced alarm system therefore should be very flexible.     

A methodological approach to internal antifire crew optimization. An oil refinery case history

This paper deals with the problem of defining the operational tasks, modelling and optimizing of antifire crew and their attempts. Unwanted events are generally modest and easily controlled in their starting phase. This obviously leads to considering that quickness and coordination enhance the possibility of successful fire control. Hence the importance that the first intervention of the factory antifire crew is supported by strong organization and efficiency. Immediate and appropriate response to emergency is essential to minimize severity of accidents, life losses, as well as the potential reduction in the plant future productivity. In approaching internal antifire crew optimization, it is convenient to distinguish a traditional inventory phase, a subsequent optimization and a graphic modelling phase. Optimization criterion is developed according to graph theory, with regard to intervention pathways and to consistency of antifire crew. The proposed graphic model provides, in an immediately readable way, the sequence of operator actions to be followed in order to cope with emergency situations.     

Predicting work performance in nuclear power plants

Diagnosis and monitoring are the major tasks of an operator in main control room of nuclear power plants (NPPs). The operator’s mental workload influences his/her performance, and furthermore, affects the system safety and operations. This study investigated the operator’s mental workload and work performance of the NPP in Taiwan. An experiment including primary and secondary tasks was designed to simulate the reactor shutdown procedure of the fourth nuclear power plant (FNPP). The performance of the secondary tasks (error rate), subjective mental workload (NASA Task Load Index, NASA-TLX) as well as seven physiological indices were assessed and measured. The group method of data handling (GMDH) was applied to integrate these physiological indices to develop a work performance predictive model. The validity of the proposed model is very well with R² = 0.84 and its prediction capability is high (95% confidence interval). The proposed model is expected to provide control room operators a reference value of their work performance by giving physiological indices. Besides NPPs, the proposed model can be applied to many other fields, e.g. aviation, air transportation control, driving and radar vigilance, etc.     

A taxonomy of performance influencing factors for human reliability analysis of emergency tasks

This paper introduces the process for, and the result of, the selection of performance influencing factors (PIFs) for the use in human reliability analysis (HRA) of emergency tasks in nuclear power plants. The approach taken in this study largely consists of three steps. First, a full-set PIF system is constructed from the collection and review of existing PIF taxonomies. Secondly, PIF candidates are selected from the full-set PIF system, considering the major characteristics of emergency situations and the basic criteria of PIF for use in HRA. Finally, a set of PIFs is established by structuring representative PIFs and their detailed subitems from the candidates. As a result, a set of PIFs comprised of the 11 representative PIFs and 39 subitems was developed.     

基于“纵深防御”原则的危化企业事故预防系统建立

危险化学品生产是当前的高危行业和安全管理的重点领域。面对事故频发的严峻形势,如何开展好危险化学品生产企业的安全管理,建立事故预防系统防止事故的发生非常关键。“纵深防御”原则作为核电厂实现核安全的一项基本原则,为核电厂长期稳定安全的发展奠定了坚实的基础,对危化企业提升事故预防能力,建立事故预防系统有较强的借鉴意义。借鉴“纵深防御”原则,文章分析危化企业应用“纵深防御”原则预防和减少事故发生的必要性,结合生产特点建立了事故纵深防御系统,对企业提高安全管理水平,预防事故的发生有重要的意义。     

核事故中放射性核素扩散浓度的理论预测

在高斯烟羽模型的基础上,对核事故中放射性云团在大气中的扩散规律进行了研究。利用倾斜烟团模式,考虑实际过程中核素粒子的重力沉降、雨洗作用以及放射性衰变等因素的影响,提出一种迅速估算放射性核素扩散浓度的方法。该方法可计算核事故中连续点源和瞬时点源在不同气象、地形条件下的浓度分布,并可获得地面的干沉积率和湿沉积率。放射性核素浓度的确定是放射性事故抢险救援和辐射防护等工作的基础和前提,是放射性事故应急救援的重要组成部分。该结果在核事故的应急救援过程中,对救援人员划定警戒区和确定周围居民的疏散范围具有重要意义,并可为制定救援方案和应急决策提供科学依据。     

核电厂主控室数字化对人执行状态评估任务影响

核电厂主控室进行数字化变革后,操纵员执行状态评估任务的方式发生了巨大变化。为了有效地识别及评估数字化对状态评估的潜在影响,以知觉/循环、资源限制等认知理论为基础,以贝叶斯概率网络为工具,建立状态评估可靠度的影响因素模型。定性分析这些因素对状态评估任务的影响机制,并定量比较它们的影响程度。分析结果表明,界面管理任务和任务负荷变迁,对状态评估的影响最为显著。需采取针对性的措施,优先处理这些人因问题,以最大限度地提高数字化核电厂的安全水平。     

复杂人机系统班组人误模型与量化分析

讨论一个班组人员行为模型,即包括:任务模型、事件模型、班组模型和人-机交互模型4个模块,并用其模拟和分析事故状态下的运行班组对异常事故的响应过程;利用班组认知过程流程图模型表征事件发展过程中班组成员对事故的征兆识别、决策、计划和行动执行的响应过程;采用CREAM的量化分析技术,对核电站的蒸汽发生器管道破管事故的班组认知失误事件进行量化分析。     

核电厂HRA定性分析

人因可靠性分析(HRA)是核电厂概率安全评价(PSA)的重要组成部分,定性评价对核电厂庞大的数据进行筛选和分析,是HRA的基础和出发点.本文介绍了核电厂HRA定性分析的目的、原则、方法和程序,并以压水堆核电厂蒸汽发生器传热管破裂(SGTR)为具体实例进行说明.     

Development of a new chemical process-industry accident database to assist in past accident analysis

Past accident analysis (PAA) is one of the most potent and oft-used exercises for gaining insights into the reasons why accidents occur in chemical process industry (CPI) and the damage they cause. PAA provides invaluable ‘wisdom of hindsight’ with which strategies to prevent accidents or cushion the impact of inevitable accidents can be developed.A number of databases maintain record of past accidents in CPI. The most comprehensive of the existing databases include Major Hazard Incident Data Service (MHIDAS), Major Accident Reporting System (MARS), and Failure and Accidents Technical Information Systems (FACTS). But each of these databases have some limitations. For example MHIDAS can be accessed only after paying a substantial fee. Moreover, as detailed in the paper, it is not infallible and has some inaccuracies. Other databases, besides having similar problems, are seldom confined to accidents in chemical process industries but also cover accidents from other domains such as nuclear power plants, construction industry, and natural disasters. This makes them difficult to use for PAA relating to CPI. Operational injuries not related to loss of containment, are also often included. Moreover, the detailing of events doesn’t follow a consistent pattern or classification; a good deal of relevant information is either missing or is misclassified.The present work is an attempt to develop a comprehensive open-source database to assist PAA. To this end, information on about 8000 accidents, available in different open-source clearing houses has been brought into a new database named by us PUPAD (Pondicherry University Process-industry Accident Database). Multiple and overlapping accident records have been carefully eliminated and a search engine has been developed for retrieval of the records on the basis of appropriate classification. PUPAD doesn’t aim to replace or substitute the well established databases such as MHIDAS and MARS but, rather, aims to compliment them.     

质子交换膜燃料电池电站多米诺事故概率和风险研究*

为探究氢能电站火灾爆炸事故发展规律,采用多米诺效应对电站进行事故概率和风险研究,建立氢能电站多米诺效应定量风险分析模型。基于设备受损概率模型与多米诺理论基础,提出氢能电站多米诺效应概率计算方法,并将方法运用到实际案例,结合SAFETI软件对具体多米诺事故场景进行定量计算。研究结果表明:氢能电站易发生多米诺事故,考虑一级多米诺效应后人员潜在死亡概率增加56%。研究结果可为制定氢能电站安全防控措施以及降低火灾爆炸事故对人员和设备的危害提供依据。     

基于CBR和RBR的环境污染事故应急辅助决策专家系统

随着我国经济的高速发展,环境事故呈现多发态势,给人民的生命和财产安全带来了一定的隐患,辅助决策专家系统为用户提供一种使用简便、结果可靠的环境应急决策手段,可以提高环境事故应急处置的成功率。目前辅助决策专家系统多基于CBR或RBR推理模式,介绍了两种推理模式的优缺点,研究了如何将二者联合使用构建环境污染事故应急辅助决策专家系统。利用CBR推理模式得到与用户输入条件相近的案例,用户可参考案例中应急处置部分内容指导应急处置,同时利用RBR推理模式得到与用户输入条件相近的化学品MSDS信息以及相应的应急处理步骤以供用户参考,上述三部分内容共同构成了环境污染事故应急指南以供用户参考,提高环境污染事故的应急处理成功率。