大亚湾核电站执照运行事件原因趋势分析

对大亚湾核电站1993/2003年所有人因相关执照运行事件进行了原因分类、趋势分析,并重点分析了电站人员在遵守和执行规定与规程方面的不足,为核电站改善人的行为提供方向性参考。     

数据驱动的核电厂人因失误因果机理模型研究

为了辨识人因失误机理,采用组织定向的人因失误分析（OTHEA）技术对2010—2017年国内核电厂发生的137件人因事件报告进行分析,采用相关性和因子分析方法,辨识人因失误影响因素之间的相关关系,识别出触发人因失误的场景,在此基础上,建立人因失误因果机理模型,揭示人因失误机理。结果表明,影响人因失误主要的结合模式为：知识经验水平、信息显示质量、压力水平、注意力与警觉性、安全态度。知识经验水平主要受培训水平和交流水平的影响;信息显示质量主要受技术系统、人-机界面、规程、组织设计的影响;压力水平主要受任务、规程、人-机界面、技术系统、组织设计以及知识经验水平和信息显示质量的影响;注意力与警觉性主要受工作环境、工作组织管理以及信息显示质量的影响;安全态度主要受组织安全文化、工作组织管理以及操纵员的素质与能力的影响。上述研究可为核电厂人因失误的精准防控提供理论依据,提升核电厂的安全水平。     

The effects of local control station design variation on human performance and plant risk

A human factors analysis was performed to assess how selected design variations to local control stations (LCSs) in nuclear power plants affect both human performance and plant risk. Modifications in the design of individual control panels and changes in their functional centralization were considered. The analysis methodology was accomplished in four stages. First, a list of LCS human engineering design deficiencies was developed using data collected from a variety of sources including visits to nuclear power plants. From these data, a set of potential upgrades were defined to correct the deficiencies. Second, the effects of the upgrades on human error probabilities (HEPs) were determined using a computer-based methodology for soliciting expert judgement. Third, the HEPs were propagated through a plant probabilistic risk assessment, and new core melt frequencies were established. The results indicated that implementation of either type of upgrades would improve human performance and lower risk, although the effect of functional centralization on performance and risk was found to be greater than panel design.     

核电厂临时设备投运人员可靠性评估模型

核电厂临时设备作为严重事故缓解的重要设施,其接入工序大多较为复杂。为了分析核电厂人员在临时设备投运时的可靠性,通过研究福岛核事故后改进项所增设临时设备接入行为的特征,基于人因失误模式和影响分析,定义人因失误发生概率、人因失误影响程度、人因失误可恢复概率为风险因子,结合专家评价与模糊语言理论提出一种临时设备投运人员可靠性评估模型。以全厂断电事故下移动电源的接入任务为例,应用所建模型获得了该任务中的人误模式重要度排序及合理的风险见解,验证了模型的可行性。      

核电组织错误的表现与类型

通过访谈和事件再分析的方法，对影响核电安全的组织因素-组织错误进行探索。根据访谈记录和事件分析报告的编码，将得到的数据进行聚类分析，得到影响核电安全的5类组织因素。它们分别为：技术管理因素、非技术管理因素、信息界面、全局思想缺乏和组织计划。研究同时发现，相对于技术管理因素．非技术管理因素对系统安全的影响较大，因此，非技术培训对于系统的安全不可或缺。     

Analysis of gross error rates in operation of commercial nuclear power stations

Experience in operation of US commercial nuclear power plants is reviewed over a 25-moth period. The reports accumulated in that period on events of human error and component failure are examined to evaluate gross operator error rates. The impact of such errors on plant operation and safety is examined through the use of proper taxonomies of error, tasks and failures. Four categories of human errors are considered; namely, operator, maintenance, installation and administrative. The computed error rates are used to examine appropriate operator models for evaluation of operator reliability. Human error rates are found to be significant to a varying degree in both BWR and PWR. This emphasizes the import of considering human factors in safety and reliability analysis of nuclear systems. The results also indicate that human errors, and especially operator errors, do indeed follow the exponential reliability model.     

核电厂人因可靠性分析中的相关性分析方法研究

人因可靠性分析(HRA)是核电厂风险分析中的重要组成部分,其中人误事件的相关性分析是HRA中必不可少的内容,忽略人误事件间的相关性,将导致低估核电厂的风险水平。本文提出了一种基于D(邓)数和层次分析法-决策试行与评价实验室(AHP-DEMATEL)方法的相关性分析模型。首先,确定两事件间相关性的影响因素及其结构关系,并针对每个影响因素建立相关性等级的隶属度函数及其锚点;其次,利用AHP-DEMATEL方法来确定各影响因素的综合权重;最后,根据实际情况评估各因素的相关性等级并构建D数,并根据D数和综合权重计算出两人因事件的相关性程度及其可信度,通过算例验证了该模型及其方法的有效性。     

核电厂人因失误分析与人因失误动态作用模型

分析了核电厂人因失误动态影响因素和人因失误特性,并结合人的生理、心理因素分析了核电厂人因失误的分布规律。最后以现在运行的核电厂为依据,提出了核电厂人因失误动态作用模型。该模型可以更好地总结人因失误经验,使得人因研究成果在核电厂得到更直接的应用,更有效地减少人因失误。     

Analysis of human-induced initiating events in a multi-unit loss of offsite power scenario

ABSTRACT

Human-induced initiators (category-B actions) are the initiators that are caused by human errors and are rarely explicitly identified and modeled in probabilistic safety assessments (PSAs). The current concern over the safety of multi-unit nuclear power sites is also a motivation for this research. This study proposes a novel process for identifying and quantifying category-B actions and ultimately, how to derive a human-induced initiating event frequency in a multi-unit scenario. Hence, this study fundamentally applies a scenario–system–action search scheme using maintenance and testing procedures, quantifies the human error probability by using the cause-based decision tree and technique for human error rate prediction method, models category-B human actions in the developed fault trees, and derives the human-induced initiating event frequency. The procedure, which is used in this approach, essentially involves system analysis, fault tree development, human error identification, screening, and quantification. The multi-unit loss of offsite power is used as an example accident situation which illustrates the application of the suggested method. Hence, the human-induced initiating event frequency for the loss of off-site power scenario for two units is derived. The application of this method would advance the efforts concerning multi-unit nuclear power plant (NPP) site risk analysis.     

SPAR-H方法在数字化核电厂人因可靠性分析中的应用研究

标准化核电厂人因风险分析（SPAR-H）方法在数字化核电厂的适用性尚未得到充分研究。本研究通过对核电厂数字化后操纵员行为特征的研究和SPAR-H方法在岭东核电厂中的具体应用,分析得出SPAR-H方法应用于数字化核电厂时存在分析结果过度保守、认知过程不够完整、部分行为形成因子（PSF）过于敏感等不足,并针对以上不足对SPAR-H方法提出明确PSF水平的判断标准、完善SPAR-H方法的认知模型、建立人因数据库等改进建议,从而使SPAR-H方法更适用于数字化核电厂的人因可靠性分析。      

核电汽轮机热力系统的主导因素变工况建模方法研究

核电汽轮机土要工作在湿蒸汽区，确定其热经济性的难点在于蒸汽干度的确定。为避免这一难题，本文提出了将机理建模与对象实际运行数据相结合的“主导因素”建模方法，即以描述机理过程的理论公式为主体，通过分析实际运行数据与理论公式的偏差，提炼出在大负荷范围内影响偏差的主要因素及其与偏差的函数关系仿真计算结果表明，该方法能够比较准确的描述对象系统的运行工况。     

The Third International Conference on Nuclear Fuel Reprocessing and Waste Management (RECOD '91)

The purpose of this study is to assess the organizational types and the job stress factors that affect procedure-based job performances in nuclear power plants. We derived 24 organizational factors affecting job stress level in nuclear power plants from the job stress analysis models developed by NIOSH, JDI, and IOR. Considering the safety characteristics in the operating tasks of nuclear power plants, we identified the job contents and characteristics through the analyses of job assignments that appeared in the organizational chart and the results of an activity-based costing. By using questionnaire surveys and structured interviews with the plant personnel and expert panels, we assessed 70 jobs among the 777 jobs managed officially in accordance with the procedures. They consist of the representative jobs of each department and are directly related to safety. We utilized the organizational personality type indicators to characterize the personality types of each organization in nuclear power plants.     

认知失误定量分析方法及其在PSA中的应用

认知可靠性和失误分析方法(CREAM)是第二代人的可靠性分析方法中的代表方法之一.以CREAM的核心思想为基础,对定量分析方法进行了改进,给出了共同绩效条件(CPC)对人的可靠性影响的量化指数.提出了用环境影响指数来定量计算情景环境迫使人的认知失误的发生概率,给出了概率安全评价(PSA)中人误概率的分析方法,并用于诊断核电站蒸汽发生器传热管破裂和蒸汽发生器隔离时的人误概率分析.     

核电厂运行中的人为失误

从核电厂运行经验中说明了研究人为失误的重要性;并根据大量人为失误事件的统计分析,阐述了人为失误的各种根原因及各种失误模式的相对显著性。根原因中主要是规程、工作场所、通讯和培训等四方面的缺陷,而失误模式则以疏忽遗漏、寻错位置、定量错误等最为常见。由此对我国核电厂人为失误研究工作提出了建议。     

Characteristics of test and maintenance human errors leading to unplanned reactor trips in nuclear power plants

The test and maintenance (T&M) human errors involved in unplanned reactor trip events in Korean nuclear power plants were analyzed according to James Reason's basic error types, and the characteristics of the T&M human errors by error type were delineated by the distinctive nature of major contributing factors, error modes, and the predictivity of possible errors. Human errors due to a planning failure where a work procedure is provided are dominated by the activities during low-power states or startup operations, and human errors due to a planning failure where a work procedure does not exist are dominated by corrective maintenance activities during full-power states. Human errors during execution of a planned work sequence show conspicuous error patterns; four error modes such as ‘wrong object’, ‘omission’, ‘too little’, and ‘wrong action’ appeared to be dominant. In view of a human error predictivity, human errors due to a planning failure is deemed to be very difficult to identify in advance, while human errors during execution are sufficiently predictable by using human error prediction or human reliability analysis methods with adequate resources.     

核电厂数字化主控室操纵员行为形成因子评价模型

由于人因可靠性分析(HRA)方法中用于量化基本人因失误概率(HEP)的行为形成因子（PSF）数目众多,且一般是通过专家评判,从而带有主观性、模糊性和不确定性。本文提出一种利用相关系数矩阵、图的距离分类和主成分分析法相结合的方法构建核电厂数字化主控室操纵员PSF的评价模型,其目的是识别不同类型的人因事件中主要影响人因绩效的PSF,以供决策减少人因失误。对某核电厂的179起人因事件报告进行实验,结果表明该评价模型能对核电厂数字化主控室操纵员的PSF进行有效评价。     

一种基于HRA的数字化人-机界面评价方法研究

为识别数字化人-机界面中可能诱发人因失误或弱化操纵员绩效的设计缺陷,建立了一种基于HRA的人-机界面评价方法：HCR+CREAM+HEC。首先,采用HCR方法从事件整体中识别出失误概率高的风险场景;然后,针对高风险场景采用CREAM方法确定各种失误模式及其失误概率,并对失误概率进行排序;最后,依据数字化人-机界面特征建立人因工程检查表,对失误概率高的人-机界面进行审查,以识别人-机界面设计中存在的缺陷,并提出改进建议。结果表明,该方法能快速有效地识别出数字化人-机界面设计中存在的容易诱发人因失误的缺陷,通过设计优化提高核电站数字控制系统运行的安全性。     

关于核电厂火灾概率风险的研究

火灾是核电厂安全面临的重要威胁之一。应用概率风险评价(PRA)方法对其进行分析,能找出电厂薄弱环节,优化电厂的设计。通过研究国际广泛使用的火灾PRA方法,以典型的二代压水堆核电厂为对象,开展了火灾概率风险分析,计算得到了火灾引起的堆芯损坏频率(CDF)为4.03×10-6(堆·年)-1。在此基础上,开展了敏感性分析,讨论了人因事件和定量筛选值对结果的影响。     

Human reliability analysis for operators in the digital main control rooms of nuclear power plants

ABSTRACT

As the main control room of nuclear power plants (NPPs) has been gradually digitized, new human reliability problems may emerge because of a series of new changes in the cognitive processes, behavioral patterns, and error mechanisms of operators. Aiming to address this situation, this paper proposes a method as guidance for human reliability analysis (HRA) of different cognitive Stages. This method first constructs the influencing factors of three cognitive processes, including monitoring, decision-making, and execution of actions, and then evaluates the weights of these influencing factors through an analytic hierarchy process (AHP). In this study, the parameters used in the proposed HRA method were determined by analyzing the test data obtained from a simulation model, and the results demonstrated the rationality and feasibility of the proposed method. A case example using this HRA method was given in which the human error probabilities at three stages in a nuclear power plant (NPP) steam generator tube ruptures (SGTR) accident were obtained. In summary, the proposed method is a simple and feasible HRA tool that can be applied in digital NPP main control rooms (MCRs).     

Optimization of periodic testing frequency of a reactor protection system based on a risk-cost model and public risk perception

Techniques for optimizing the frequency of periodic surveillance testing of nuclear power plant (NPP) safety systems have been receiving increased attention and growing importance because of the need to reduce system unavailability and maintenance cost. Economic losses from maintenance human errors should be included in estimating periodic testing and maintenance costs because the losses increase with maintenance human errors. This paper proposes a method for optimizing periodic testing intervals of a digital reactor protection system by balancing risk and cost of periodic surveillance tests, in which maintenance human error and public risk perception have been reflected. The risk and costs were estimated from both plant operator and socio-economic standpoints. This model determines the optimal testing frequency for the minimum value of an objective function that consists of all costs, including the monetary values of the consequence of maintenance human errors and reactor core damage. We present a case study using our model for the OPR1000 plant. The study results show the significance of reducing human errors in periodic testing and maintenance. The proposed method is expected to be useful to NPP operators as well as regulators for evaluating the optimal periodic testing frequency of a nuclear reactor protection system and for obtaining information needed in decision making processes.