试论人因工程学应用于核电建设全过程

国内外已公布了许多用于核电厂的人因工程学标准或导则，但用于核电建设项目全过程的导则则尚未见到。经过全面调研，作者草拟了《人因工程学用于核电厂建设项目的实施导则（初稿）》。文章扼要论述了该导则的主要思想和内容，强调应将人因工程学渗透进核电建设全过程，阐明编制并实施“人因工程学应用大纲”的方法及各阶段实施要点，说明应当在各级工作组织中设置人因工程学专业小组或人因工程师负责有关具体工作等     

事故序列评估程序:核电厂事故后人的可靠性分析技术

核电厂事故后人的可靠性分析(HRA)是核电厂概率安全评价和核电厂安全运行的重要组成部分。人因可靠性分析事故序列评估程序技术(ASEP)是对于传统的人的失误率预测技术(THERP)方法的改进和规范。文章介绍了事故序列评估程序技术的应用程序和应用，并给出某核电厂的一个全厂断电(LOOP)应用实例。     

论人的可靠性研究的两种策略

文章通过考察人的可靠性研究的历史，认为人的可靠性研究实际上存在着两种策略，每种策略都有各自的对人的模型的假设，一种策略被称为“工程学可靠性研究策略”，它把人假设为与机器设备并无二致的普通零部件，故称之为“零部件人模型”，在这种假设下，人们发展了人的可靠性分析技术，与机器可靠性分析同出一辙；另一种策略被称为“行为学可靠性研究策略”，它几乎完整地考虑了人的自然和社会属性，人被看作是与机器完全不同的系统元素，这种人的模型称之为“个性人模型”，在这种人的模型假设下，人们发展了人的可靠性评估技术或称人员子系统可靠性评估技术，文章着重讨论了人的可靠性评估技术的步骤和重点     

核电厂HRA定性评价及应用

核电厂人的可靠性分析(HRA：Human Reliability Analysis)定性评价的目的是在定性分析的基础上,确定HRA边界条件和引入HRA模型的人因事件的数量,使得HRA的量化分析得以实施。定性评价的基本原则是确定边界假设条件,辨识出所有对安全和运行具有显著影响的人因事件序列。本文以某压水堆核电厂蒸汽传热管破裂(SGTR)为具体实例,详细分析了HRA定性评价过程,确定了分析始发事件题头的基本方法,为核电厂HRA的具体实施提供了理论指导和实践说明。     

核电厂事故后人因可靠性分析与操纵员绩效改善

核电厂人因可靠性分析（HRA）是核电厂概率安全评价（PSA）的重要组成部分，能够较好地评价和量化核电厂主控室（MCR）操纵员的行为。通过对国内某核电厂压水堆（PWR）进行HRA分析，对事故后操纵员行为进行分类和归组并对其进行量化分析，对核电厂事件进行基本人误概率和重要度排序。基于HRA分析，从管理的角度．提出对相对应的应急规程（EOP）进行改进，对于重要度较高的操纵员行为，核电厂应加强培训，改善操纵员绩效。     

工程和设计中人因工程学方法的适应性分析

目的 通过构建一个多维的人因工程学方法适应性分析模型,为人因工程领域研究人员在繁多的人因工程学方法中确定合适的方法解决工程和设计问题提供思路与指导.方法 调研人因工程学方法,构建了一个包含十一个大类76种人因工程学方法的方法集,然后从研究对象、信效度、资源成本以及时间成本四个维度对人因工程学方法的遴选过程展开分析,探讨了适应性分析模型各维度在应用过程中不同分析顺序、不同等级设定级别等对适应性分析的影响,通过案例探讨了该适应性分析方法在实际工作中的应用.结论 人因工程学方法适应性分析方法可以针对目标分析场景有效地筛选出合适的人因工程学研究方法,本方法具有简约直观的特点,在应用中不需要大量的计算,可以为人因工程学方法适应性分析提供方法筛选的思路.     

核电厂数字化规程在屏之间布局方法及评价

面对数字化系统带来的挑战,以减少同一操纵员在屏之间的移动距离为目标,以核电厂数字化人机界面事故规程为研究对象,以人因可靠性为基础,提出事故规程布局的动态标识最短移动路径算法,并利用神经网络人因可靠性评价方法分析执行过程的可靠性。提出的方法通过实例进行了分析,实验表明提出的方法具有较好的性能,能解决核电厂数字化事故规程在屏之间的自动布局。     

考虑人因可靠性的RCM方法改进研究

为了弥补传统以可靠性为中心的维修方法中未对人因可靠性进行分析的不足,本文提出了考虑人因可靠性的改进维修方法.该方法将人机整合系统作为分析对象,利用人因可靠性的分析方法对维修过程中的人因进行评估,以提高人机整合系统的可靠性为目标,为企业的维护决策及优化提供更系统和有效的方法论支持.该方法在石化企业选定装置的成功应用证明了其有效性,应用效果明显优于改进前.     

人因工程在高通量工程试验堆（HFETR）主控室的应用

人因工程在高通量工程试验堆（ＨＦＥＴＲ）主控室的应用山松林杨树春（中国核动力研究设计院成都６１０００５）１引言人因工程学就是“使机器的设计、工作方法和工作环境的制定等适合于人的能力限度，人和机器为最佳配合的一门技术”。用人因工程学的观点来设计核反应堆...     

工程化人因可靠性分析方法探讨

人的可靠性分析是核电厂概率安全评价(PSA)的重要组成部分,如何在工程中实现HRA一直是人因研究的重点。本文基于事故序列评估程序技术(asep)的筛选HRA方法,包括事故前和事故后分析。提出工程化HRA的总体框架,包括定性分析,基本数据取值和计算过程。最后结合实例进行应用。     

The use of empirical data sources in HRA

This paper presents a review of available information related to human performance to support Human Reliability Analysis (HRA) performed for nuclear power plants (NPPs). A number of data sources are identified as potentially useful. These include NPP licensee event reports, augmented inspection team reports, operator requalification data, results from the literature in experimental psychology, and the Aviation Safety Reporting System. The paper discusses how utilizing such information improves our capability to model and quantify human performance. In particular, the paper discusses how information related to performance shaping factors can be extracted from empirical data to determine their size effect, their relative effects, as well as their interactions. The paper concludes that appropriate use of existing sources can help addressing some of the important issues we are currently facing in HRA.     

核电站安全分析方法与安全评价标准初探

文章首先陈述了核电站的安全性与安全分析的任务；其次，论文阐述了核电站２种分析方法，即确定论与概率风险分析法，后者是前者的发展，而两者的结合与优化构成了核电安全分析的完整体系；最后文章探讨了核电站的定量评价标准，包括个人、社会和经济的评价目标。     

An analysis of maintenance failures at a nuclear power plant

In this paper, a study of faults caused by maintenance activities is presented. The objective of the study was to draw conclusions on the unplanned effects of maintenance on nuclear power plant (NPP) safety and system availability. More than 4400 maintenance history reports from the years 1992–1994 of Olkiluoto BWR NPP were analysed together with the maintenance personnel. The human action induced faults were classified, e.g. according to their multiplicity and effects. This paper presents and discusses the results of a statistical analysis of the data. Instrumentation and electrical components appeared to be especially prone to human failures. Many human failures were found in safety related systems. Several failures also remained latent from outages to power operation. However, the safety significance of failures was generally small. Modifications were an important source of multiple human failures. Plant maintenance data is a good source of human reliability data and it should be used more in the future.     

核电站安全分析方法与安全评价标准初探

文章首先陈述了核电站的安全性与安全分析的任务 ;其次 ,论文阐述了核电站 2种分析方法 ,即确定论与概率风险分析法 ,后者是前者的发展 ,而两者的结合与优化构成了核电安全分析的完整体系 ;最后文章探讨了核电站的定量评价标准 ,包括个人、社会和经济的评价目标。     

A computational model for evaluating the effects of attention, memory, and mental models on situation assessment of nuclear power plant operators

Operators in nuclear power plants have to acquire information from human system interfaces (HSIs) and the environment in order to create, update, and confirm their understanding of a plant state, as failures of situation assessment may cause wrong decisions for process control and finally errors of commission in nuclear power plants. A few computational models that can be used to predict and quantify the situation awareness of operators have been suggested. However, these models do not sufficiently consider human characteristics for nuclear power plant operators.In this paper, we propose a computational model for situation assessment of nuclear power plant operators using a Bayesian network. This model incorporates human factors significantly affecting operators’ situation assessment, such as attention, working memory decay, and mental model.As this proposed model provides quantitative results of situation assessment and diagnostic performance, we expect that this model can be used in the design and evaluation of human system interfaces as well as the prediction of situation awareness errors in the human reliability analysis.     

Development of a dynamical systems model of plant programmatic performance on nuclear power plant safety risk

Application of probabilistic risk assessment (PRA) techniques to model nuclear power plant accident sequences has provided a significant contribution to understanding the potential initiating events, equipment failures and operator errors that can lead to core damage accidents. Application of the lessons learned from these analyses has resulted in significant improvements in plant operation and safety. However, this approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. The research described in this paper presents an alternative approach to addressing this issue. In this paper we propose a dynamical systems model that describes the interaction of important plant processes on nuclear safety risk. We discuss development of the mathematical model including the identification and interpretation of significant inter-process interactions. Next, we review the techniques applicable to analysis of nonlinear dynamical systems that are utilized in the characterization of the model. This is followed by a preliminary analysis of the model that demonstrates that its dynamical evolution displays features that have been observed at commercially operating plants. From this analysis, several significant insights are presented with respect to the effective control of nuclear safety risk. As an important example, analysis of the model dynamics indicates that significant benefits in effectively managing risk are obtained by integrating the plant operation and work management processes such that decisions are made utilizing a multidisciplinary and collaborative approach. We note that although the model was developed specifically to be applicable to nuclear power plants, many of the insights and conclusions obtained are likely applicable to other process industries.     

The MDTA-based method for assessing diagnosis failures and their risk impacts in nuclear power plants

In the emergency situations of nuclear power plants (NPPs), a diagnosis of the occurring events along an accident progression or as initiating events is crucial for managing or controlling a plant to a safe and stable condition. If the operators fail to diagnose the occurring event(s), their responses to a given event can eventually become inappropriate or inadequate. This paper presents an analytical method for assessing the potential for a diagnosis failure (or misdiagnosis) and its consequences for human behaviour and plant safety. The method largely comprises of three steps as follows: (1) Analysis of the potential for a diagnosis failure, (2) Identification of the human failure events (HFEs) that might be induced due to a diagnosis failure, and (3) Quantification of the HFEs and their modeling into a PSA model. The paper also presents a pilot application of the proposed method to the small loss of coolant accident of a Korean NPP.     

Human error data collection as a precursor to the development of a human reliability assessment capability in air traffic management

Quantified risk and safety assessments are now required for safety cases for European air traffic management (ATM) services. Since ATM is highly human-dependent for its safety, this suggests a need for formal human reliability assessment (HRA), as carried out in other industries such as nuclear power. Since the fundamental aspect of HRA is human error data, in the form of human error probabilities (HEPs), it was decided to take a first step towards development of an ATM HRA approach by deriving some HEPs in an ATM context.This paper reports a study, which collected HEPs via analysing the results of a real-time simulation involving air traffic controllers (ATCOs) and pilots, with a focus on communication errors. This study did indeed derive HEPs that were found to be concordant with other known communication human error data. This is a first step, and shows promise for HRA in ATM, since HEPs have been derived which could be used in safety assessments, although these HEPs are for only one (albeit critical) aspect of ATCOs’ tasks (communications). The paper discusses options and potential ways forward for the development of a full HRA capability in ATM.