核电厂HRA组织定向研究

概率安全评价(PSA)已经成为核电厂定量化安全评价的主要方法,人因可靠性分析(HRA)是其中重要组成部分.传统的HRA方法研究对象主要是"个体失误",而HRA的全面评估必须考虑"组织情景",HRA必须组织定向.分析了HRA各主要方法对于组织因素考虑的不足,提出了HRA组织定向的必要性和基本原则.在提出组织定向的假设条件基础上,建立了HRA(A、B、C类事故)与核电厂相关特定组织之间的映射模型.     

第二代人的可靠性分析方法的进展

在探讨第一代人的可靠性分析 (HRA)方法的局限性之后 ,笔者进而探讨第二代HRA方法的模型 ,建立在多种学科 (认知心理学、行为科学、可靠性工程等 )相互结合的基础上 ,又着重研究产生人的行为 /绩效的情景环境以及它们是如何影响人的行为 /动作的 ,并与工业系统的运行经验和现场或模拟机获得的信息紧密结合。重点介绍了以“失误分析技术”(ATHEANA)和“认知可靠性和失误分析方法”(CREAM)为代表的第二代HRA方法。它们是当前HRA领域中的具有应用和发展前景的新框架思想。     

复杂工业系统中班组人因失误分析

在复杂工业系统中 ,人因可靠性分析 (HRA)是预防和减少人因失误的有效方法。人在复杂工业系统中的生产活动 ,往往是由组织中班组成员集体完成的 ,完整的HRA必须充分考虑班组人误的产生。班组人误的产生有其自身的规律 ,如何合理地定义人员行为形成因子 (PSFs)是班组人因失误分析的难点 ,也是班组人因失误分析的重要手段 ,被广泛应用在核电厂 ,航空和造船工业领域的事故分析中。笔者详细分析和探讨了班组人因失误的定义、产生过程及相关的人的行为形成因子 ,以期能使大规模工业系统中的人因失误分析更加合理和完善。     

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.     

核电站事故前人因可靠性分析方法

人因可靠性分析 (HRA)已成为概率安全分析 (PSA)必不可少的内容 ,事故前人因事件可靠性分析对有效预防维修、调校工作中的人因失误有着重要作用 ,是人因可靠性分析的重要组成部分 ,对PSA最终计算结果有重要影响。笔者结合核电站人因可靠性分析的实际需求 ,运用了以THERP为主的人因失误概率评价方法 ,创建了事故前人因事件分析的基本程序、方法及分析文档模式 ,表述了程序化的事故前人因事件分析模式 ,为我国核电站事故前人因可靠性分析提供了完整和有效的分析方法 ,并有效用于秦山核电站的PSA。     

人的失误理论研究进展

人的失误理论研究已进入结合认知心理学并以人的失误动态过程为研究热点的阶段。笔者回顾了人的失误理论研究的进展,讨论了相关的人的认知行为类型、认知失误的基本概念和人的失误模型。例如适用于不同情景和应用条件的几种模型:刺激-调制-响应(S-O-R)模型;失误的决策阶梯(Step-ladder)模型;通用GEMS模型以及Worledge认知模型。由于人的行为的复杂性和难以预测性造成了人的可靠性分析(HRA)的困难,因此,对人的行为的深入了解必须从人的行为特性及其规律性入手,将人的可靠性分析与行为科学理论结合起来,揭示人的失误发生的内在规律。与此同时,重点分析了概率安全评价技术(PSA)中如何对人的失误事件进行定量估计;如何考虑人的心理因素影响的几种重要的人的失误理论模型,并对今后这该领域中的研究方向进行了讨论。     

地铁行车调度班组应急响应中的人因失误研究

为提高地铁系统应急响应过程的可靠性,有效避免和减少多班组动态交互的人因失误,构建行车调度应急响应循环模型查找可能的人因失误模式,提出减少行车调度班组人因失误的安全对策措施。适用于发现行车调度班组应急响应过程的薄弱环节,进行地铁系统人因可靠性分析(HRA),有利于提高地铁系统的安全运营管理。     

人的失误与人因工程学在核电厂安全性的应用

叙述了人的失误与人因工程学在核电厂安全性应用的重要性，根据统计资料分析了人的失误、失误模式与失误原因，最后综述了人因工程学原则在核电厂的设计、运行管理中的应用。     

人因失误的机理及其可靠性研究

随着科技的发展 ,在系统安全中 ,机器设备可靠性越来越高 ,由于人本身的复杂性 ,人因失误变得愈来愈严重。本文基于人行为的原理 ,对人因失误的机理、影响人失误的因素、人行为的模型和失误模型及其可靠性的量化进行了分析 ,建立了计算人可靠性的威布尔分布模型 ,并对其参数进行了讨论 ,可用此来评价人的可靠性。     

PSA中人因失误模型化研究

主要研究PSA模型如何考虑人因失误的影响,系统地提出如何在电厂系统模型中建立相对应的人因失误分析模型。利用事件树把系统故障和人因失误相结合的方法,探讨如何最大可能地真实描述事故后的操纵员行为,确定重要人因事件发展序列以及根据系统响应确定合理可分析的人因题头,建立完整的人因失误模型化的体系,并以实例说明具体分析过程。此项研究能够较好地描述硬件可靠性和人因可靠性之间的关联关系,降低HRA出力并满足PSA对于事故后人员行为的概率分析需求。     

人因可靠性分析方法

回顾了人因可靠性分析 (HRA)的发展历史 ;汇总了近几十年来的各种人因可靠性分析方法 ;详细介绍了人的失误率预测技术 (THERP)、人的认知可靠性模型 (HCR)、成功似然指数法 (SL IM)的背景、使用步骤、特性等 ;分析了 THERP+ HCR的优势 ,并给出了一个应用实例。最后 ,指出了目前 HRA方法的不足并预测了 HRA的发展趋势     

Human error analysis in furnace start-up operation using HEART under intuitionistic fuzzy environment

To address human error in system reliability, Human Reliability Analysis (HRA) is an essential issue. Human Error Assessment and Reduction Technique (HEART) as a rather straightforward technique for HRA has successfully been used in many areas to predict human error probability (HEP). However, knowledge acquisition of experts during assessed proportion of affect (APOA) calculation is subjected to vagueness and ambiguity. To overcome this challenge, in this paper Intuitionistic Fuzzy (IF) set due to their advantage to represent more fuzzy information than a classical fuzzy set adopted through APOA calculation. To demonstrate this hybrid approach short for, IF-HEART, the furnace start-up operation is handled, since analysis shows that most of explosions and losses occur during furnace start-ups operation. Further, a sensitivity analysis is carried out to approve the proposed integrated approach. In addition to its academic contribution, the results of the paper enable to improve the overall safety level of a furnace by taking into account potential human error.     

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.     

A fuzzy Bayesian network approach to improve the quantification of organizational influences in HRA frameworks

Organizational factors are the major root causes of human errors, while there have been no formal causal model of human behavior to model the effects of organizational factors on human reliability. The purpose of this paper is to develop a fuzzy Bayesian network (BN) approach to improve the quantification of organizational influences in HRA (human reliability analysis) frameworks. Firstly, a conceptual causal framework is built to analyze the causal relationships between organizational factors and human reliability or human error. Then, the probability inference model for HRA is built by combining the conceptual causal framework with BN to implement causal and diagnostic inference. Finally, a case example is presented to demonstrate the specific application of the proposed methodology. The results show that the proposed methodology of combining the conceptual causal model with BN approach can not only qualitatively model the causal relationships between organizational factors and human reliability but also can quantitatively measure human operational reliability, and identify the most likely root causes or the prioritization of root causes causing human error.     

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.