核电厂主控室人机界面评价实验研究

基于以人为中心的人机交互设计和评估的思想,结合国内核电厂的实际情况,确定一些重要的核电厂主控室人机界面评估因素,并划分核电厂主控室人机界面各组成部分的评价指标与评价层次,建立了客观的评价指标体系,为核电厂主控室人机界面综合评价奠定了基础。运用模糊数学的方法,建立核电厂主控室人机界面定量评价模型,对核电厂主控室人机界面进行较为客观的综合评价。通过对核电厂操纵员问卷调查的形式进行实验验证,从而实现了定性评价与定量评价的一致性。研究表明,该方法应用于核电厂主控室人机界面评价是一种有效的方法。     

基于STAMP模型的核动力蒸汽发生器水位控制系统安全性分析

核电厂蒸汽发生器(SG)水位控制系统的安全可靠运行是保证核电厂安全性和经济性的关键因素,其控制对象具有高度复杂、非线性的特点。由于复杂系统的安全性是特定环境下由系统相关要素交互作用所产生的一种涌现特性,运用系统理论,以STAMP模型为基础对SG水位控制系统进行安全性分析,以利于在设计早期阶段发现影响该系统安全运行的潜在风险因素,预防危险事故。该方法将系统理论用于核电厂关键系统和设备安全性分析,为核电厂安全运行提供了新的技术手段支持。     

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。     

MLS安全评价法在固井作业中的应用

固井是钻完井过程中必不可少的一部分,固井作业具有整体性、一次性和不可逆的特性,其过程中极易发生安全事故。根据固井作业其自身的工艺特点,明确固井过程中易发生的危险因素、危险因素是否具有控制和监测手段、危险因素造成事故的频率以及产生事故所造成的当量直接经济损失。运用MLS评价方法对固井作业施工过程中各种危险因素进行评估。最后,根据固井危险因素分析和危险值评估结果,明确固井施工过程中主要危险因素,分析主要危险因素存在的原因,采取明确的危险控制措施,减少施工风险,确保固井作业的安全进行。     

浅析AP1000核电在役无损检测安全管理的重要性

作为第三代核电自主技术,AP1000是目前全球核电市场中最安全、最先进的商业核电技术。在役无损检测作为AP1000核电运营安全性的重要保证之一,其安全管理的好坏直接关系到无损检测作业的成功与否。AP1000核电在役无损检测是十分复杂的系统工程,作业过程中存在诸多危险因素,检测工序复杂,因此核电厂无损检测服务企业必须将安全管理贯穿于整个在役无损检测管理过程之中。     

核电厂人因事故预防的定量化决策

人因事故的分析与预防是核电厂安全运行和管理的重要内容。笔者提出的系统安全性层次分析法主要从两种角度考虑系统的安全性:专家能力权值和安全性矩阵的建立。采用专家判断矩阵确定事故原因对系统安全性的重要度排序。举例某核电厂事故定量分析进行说明,在对事故进行原因分析基础上,构建事故影响因素层次模型,利用层次分析法分析得出事故原因重要度排序由高到低依次为组织管理、操作人员、人机界面、培训与设备状态,并据此提出了相应的预防与改进措施,为安全性要求较高的复杂工业系统提供事故预防的定量化决策依据。     

Markov reliability model research of monitoring process in digital main control room of nuclear power plant

Monitoring process is an important part in a high safety digital main control room of nuclear power plant (NPP), it is the source extracted information and found abnormal information in time. As the human factors events arisen from monitoring process recently take place more and more frequent, the authors propose a reliability Markov model to effectively decrease these abnormal events. The model mainly analyzes next monitoring object probability in terms of current information and plant state. The authors divide digital human–machine interface into two parts that are referred as logical homogeneous Markov and logical heterogeneous Markov. For the former, a series of methods of probability evaluation are proposed, such as, Markov transition probability with condition, probability distributed function with human factors, system state and alarm; for the latter, the authors propose the calculation of probability of correlation degree between last time and next time and probability calculation methods with multi-father nodes. The methods can effectively estimate the transition probability from a monitoring component to next monitoring component at time t, can effectively analyze which information is more important in next monitoring process and effectively find more useful information in time t + 1, so that the human factors events in monitoring process can greatly be decreased.     

基于CFD的核电厂防火安全评估方法研究

目前国内核电厂普遍采用确定论方法进行防火安全评估。采用CFD模型对核电厂某典型电气间火灾发生过程进行数值模拟研究。模拟火灾行为（火势增长和蔓延）、温度场变化、烟气浓度变化等,分析结果中温度对电缆和电气设备的失效判定、烟气层对电缆和电气设备的风险影响,研究该方法对于核电厂防火安全分析的指导作用。通过分析数值模拟数据,计算结果与二代机型确定论分析方法结果相符,有效验证了CFD火灾模型在核电厂防火安全评估中的适用性,为国内自主建立核电厂火灾数值模拟评价体系提供参考。     

核电站电缆安全使用寿命评定方法

针对核电站电缆寿命评定试验的若干要素,结合该类电缆常用的两种高分子绝缘材料即交联聚乙烯和低烟无卤交联聚乙烯的特点,设计了完善其安全寿命评定试验的方案,并按相关要求进行长达5000h的试验,该方案运用数理统计中准确性较高的最小二乘法原理对试验数据进行处理,克服了以电性能加速老化手段评估电缆安全寿命时准确性较差的缺陷。最终结果验证了该类电缆能够满足其使用60年的要求,对核电站电缆的设计及安全运行具有重要的现实意义。     

通用航空公司安全运行保障能力未确知测度分析

通用航空公司安全运行保障能力是通用航空公司可持续健康发展的前提条件,是实现民航"两翼齐飞"的重要基石。根据通用航空公司安全运行保障能力较为低下的现状,以通用航空公司为例,基于日常运行状况和特点,结合现场调研结果,从人员、机械设备、环境、管理4方面提出了通用航空公司安全运行保障能力指标体系,鉴于其运行具有不确定性、模糊性和复杂性等特点,构建通用航空公司安全运行保障能力未确知测度分析模型,对其安全运行保障能力的水平进行评估,并与公司评估小组的评估结果进行对比,发现:模型计算所得到的安全运行保障能力等级与实际情况相符合,确定了通用航空公司今后应重点加强专业化人员培养、设备及时更新和设备维护等方面的工作。     

Improved qualitative fault propagation analysis

Fault propagation analysis is the cornerstone to assure safe operation, optimized maintenance, as well as for the management of abnormal situations in chemical and petrochemical plants. Due to plant complexity and dynamic changes in plant conditions, current approaches have major limitations in identifying all possible fault propagation scenarios. This is due to the lack of realistic equipment and fault models. In this paper, practical framework is proposed to synthesize and assess all possible fault propagation scenarios based on robust modeling methodology. Fault models are constructed where deviations are identified and associated with symptoms, faults, causes, and consequences. Fault models are tuned using real time process data, simulation data, and human experience. The proposed system is developed and applied on case study experimental plant.     

Safety and human factors considerations in control rooms of oil and gas pipeline systems: conceptual issues and practical observations.

All oil and gas pipeline systems are run by human operators (called controllers) who use computer-based workstations in control rooms to "control" pipelines. Several human factor elements could contribute to the lack of controller success in preventing or mitigating pipeline accidents/incidents. These elements exist in both the work environment and also in the computer system design/operation (such as data presentation and alarm configuration). Some work environment examples include shift hours, shift length, circadian rhythms, shift change-over processes, fatigue countermeasures, ergonomics factors, workplace distractions, and physical interaction with control system computers. The major objective of this paper is to demonstrate the critical effects of human and organizational factors and also to highlight the role of their interactions with automation (and automated devices) in the safe operation of complex, large-scale pipeline systems. A case study to demonstrate the critical role of human organizational factors in the control room of an oil and gas pipeline system is also presented.     

On the operator action analysis to reduce operational risk in research reactors

Human errors during operation and the resulting increase in operational risk are major concerns for nuclear reactors, just as they are for all industries. Additionally, human reliability analysis together with probabilistic risk analysis is a key element in reducing operational risk. The purpose of this paper is to analyze human reliability using appropriate methods for the probabilistic representation and calculation of human error to be used alongside probabilistic risk analysis in order to reduce the operational risk of the reactor operation. We present a technique for human error rate prediction and standardized plant analysis risk. Human reliability methods have been utilized to quantify different categories of human errors, which have been applied extensively to nuclear power plants. The Tehran research reactor is selected here as a case study, and after consultation with reactor operators and engineers human errors have been identified and adequate performance shaping factors assigned in order to calculate accurate probabilities of human failure.     

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。     

核电站FDA安全管理信息流系统模型的构建研究

为了从安全信息的角度完善核电站的事故致因机理，并在实践中加强核电站的安全管理，首先以安全信息为视角，以系统安全行为链为主线，建立核电站FDA安全管理信息流系统模型，该模型由运行操作人员、核电站企业、国家核安全局3条子链和1条必要安全信息主链构成；然后结合模型和核电站具体工作流程，分析得到3个子事故域和1个总事故域，并归纳出核电站安全运行各阶段所需的必要安全信息；最后结合事故域，分析模型在核电站安全管理中的实际应用价值。     

一种地铁综合监控系统安全性分析方法研究

地铁综合监控系统的安全直接影响整个地铁系统的安全,根据地铁综合监控系统的特点建立该系统的安全性评价模型,将层次分析法和模糊综合评判法相结合用于地铁综合监控系统的安全性分析。用层次分析法确定各影响因素的权重,模糊综合评判法评定地铁综合监控系统的安全等级。该评定方法能较好地反映地铁综合监控系统的实际安全状况,可为地铁的安全运营提供决策依据,并且评价结果简单直观。     

城市污水处理厂安全运行问题探讨

从城市污水处理厂达标出水的生命周期评价的角度,提出城市污水处理厂安全运行的内涵,即以保障出水达标为核心,同时防止污水处理过程中发生安全事故和对污水处理厂周围环境的污染;分析影响城市污水处理厂安全运行的因素;从保障出水达标、防止污水处理过程中发生人员伤亡、防止污水处理厂对周围环境产生污染和建立健全完善的管理制度等方面,探讨如何保证污水处理厂安全运行。笔者所探讨的问题,旨在为提高我国城市污水处理厂安全运行提供理论依据,对预防及减少污水处理的安全事故发挥积极作用。     

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.     

核电营运安全文化主体考

提出并论述了核电营运单位是核电安全文化的主体 ,核电营运单位是核电安全的全面的法定负责者 ;阐明了核电营运安全文化的特性 ;介绍了核电安全文化的考核 ,重点说明了以WANO关于核电厂综合性能指标量化的考核。     

集散控制系统作业安全人机环工程研究

为了解集散控制系统作业安全人机环工程中存在的匹配情况，采用自制《集散控制系统作业安全人机环工程》调查表，对某石化企业390名DCS作业人员进行了问卷调查。结果85．5％的操作者认为操作室的空气不新鲜，57．4％的操作者认为DCS操作系统的性能不够完善，55．3％的操作者认为DCS操作劳动强度大，90．5％的操作者认为DCS显示屏产生直接眩光，87．2％的操作者认为下肢活动空间过小，85．2％的操作者认为下肢活动深度过浅，72．7％操作者认为下肢活动高度过低，56．6％的操作者认为装置区的噪声对控制室有影响。由此得出结论，集散控制系统在人-机-环诸方面不同程度的存在失配。