核电厂主控室人员作业绩效综合评价方法应用研究

为了对核电厂主控室操纵员的作业绩效进行综合评价,通过广泛的文献调研并结合问卷调查建立评价指标体系,基于层次分析法和DEMATEL法确定既能反映指标相互重要关系又考虑指标间相互影响的综合指标权重,应用非线性加权综合法将多个指标评价值合成为一个最终评价值。采用该方法在模拟机上对事故工况下操纵员的作业绩效进行实例评价,结果表明,该方法能够对核电厂主控室人员绩效进行有效评价。     

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。     

危险化学品企业安全验收评价结论量化分析

为了使危险化学品企业安全验收评价结论更加准确、客观,根据安全验收评价结论编制的原则和相关导则,从法律法规符合性、外部安全条件、总平面布局及建筑结构、主要生产装置设施、主要储存装置设施、公用工程和辅助设施、安全管理及从业人员条件和应急救援等八个方面建立了安全验收评价结论定量评估指标体系。基于层次分析法确定各级指标权重,建立了安全验收评价结论定量评估模型。为方便对安全验收评价结论进行准确、快速地评估,利用EXCEL软件建立了安全验收评价结论定量评估系统。该评估模型和评估系统可以客观、快速、准确地对危险化学品企业安全验收评价结论进行定量评估。     

航空装备研制风险的综合赋权-双基点法评估

为实现对航空预研项目技术风险的定量评估,建立技术风险评价指标体系,建立基于综合赋权和双基点方法的综合评估模型,采用层次分析法(AHP)求得主观权重,熵值赋权法求得客观权重,运用线性规划方法求得对2类权重加权的权值,构造综合权重;使用正负理想点间的投影距离代替传统的相对欧式距离对TOPSIS方法进行改进;实例分析中,通过对某航空预研项目5种不同的方案进行风险评估,得出各方案的优劣度,选出了较为优化的技术方案,该方法可用于指导其他装备研制风险的评估。     

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。     

基于AHP-FUZZ方法的高校节能评价方法

根据综合评价指标体系建立的原则,建立了高校节能评价指标体系。利用层次模糊(AHPFUZZ)综合评价方法,分别计算各指标权重和建立评判矩阵,根据加权平均的方式提出高校节能效果评价方法。评价方法对定性评估高校节能效果提供了定量计算依据,对评估实际节能工程改造效果具有指导作用。     

报警系统操作员的响应性能评价指标设计研究

为解决现有报警系统性能评估环节中,缺乏操作员响应性能评估方法和报警系统性能与操作员响应性能联系较少等问题,建立用一个定量指标来评价操作员响应性能的方法。对现有定量关键性能指标(KPI)的影响因素进行分析,并考察它们与操作员响应性能的联系。在此基础上,构建一个操作员响应性能综合评价定量指标的计算公式。用现场报警系统数据进行评价效果验证试验。结果表明,用这一指标评价操作员综合响应性能比用现有的KPI评价更准确和直观。     

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。     

基于云模型的管制员岗位工效学评价

通过对现有中国民航管制员岗位的工效学评价,减少管制员的人为差错,保障民航的安全运行,结合管制员岗位人机界面的特点,从人机界面构成要素和工效学角度,综合考虑各种影响管制员工作的因素,建立了管制员岗位工效学评价指标体系。基于云模型和模糊综合评价法构建了管制员岗位工效学评价模型,并应用该模型对某机场塔台管制员岗位的工效学现状进行了评价。该模型具有量化分析,评价结果直观的特点,能够反映出系统人机界面中存在的不足,为改进人机界面设计和减少管制员差错提供理论基础。     

基于模糊AHP模型的飞行评价体系

一种正确有效的飞行训练评估方法是保障飞行训练质量的必要前提和基础,而传统的评估方法多采用单一指标评价法或横向指标比较法,这种方法虽然简单易行,但没有充分考虑到评估体系自身的多样性,不能够真实反映飞行训练状态。本文提出了以模糊综合法为主体,专家评价、层次分析法相结合的综合评价方法,通过构造隶属度矩阵,建立飞行训练评估模型,克服了飞行教员评价的主观性,比较全面、客观的进行综合评估,量化计算过程,为真实、有效的飞行训练奠定基础。     

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.     

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。     

Human factors applied to alarm panel modernization of nuclear control room

Human factors deal with issues related to humans, their behavior and the physical aspect of the environment in which they work. A control room is a complex system where operators perform plant operation using control systems and carry out monitoring and administrative responsibilities. For safe operation of industrial installation, the performance of the control room crew plays an important role. In this respect, a well designed control room is crucial for safe and efficient operation. The aim of this paper is to propose a methodological framework applied to nuclear control room evaluation, through participatory ergonomics, using operator activity analysis and human factors questionnaire as aid tools. We describe a case study in which the methodology framework was used in the evaluation process of a nuclear control room. The information gathered made possible a series of recommendation for the adequacy of the control room design, assisting in the safety assessment of the nuclear plant operation and justifying the alarm panel modernization.     

用层次分析法分析核电站中影响人误的组织因素

应用层次分析法的基本原理,构建核电站中影响人误的组织因素AHP(层次分析法)模型,确定影响人误的组织因素的指标体系,将成对比较矩阵的特征向量作为组织因素的权重,确定了相关因子的影响力排序。研究结果显示:培训与交流反馈是影响人误的主要组织因素;强化质量监督与控制以及加强交流协作与技能培训,是减少核电站人误发生的重要举措。     

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.     

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.     

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。