企业安全生产中的人因管理

长期以来，企业对于安全管理的重点一直放在对物因的管理上而忽视了人因管理。事实上．绝大多数的事故都是由于人为原因造成的。加强安全生产中的人因管理，深入分析人的行为特征和心理状态。可以有效地消除事故隐患。降低或避免事故的发生。     

事故前人因失误研究

在安全评价中,人因失误特别是事故后人因失误越来越受到重视;但相对而言,事故前人因失误没有引起足够的重视。本通过对大量核电厂安全分析报告和运行事件报告的考察,系统地阐述了事故前人因失误对系统安全的显影响,并在此基础上,归纳出在核电站开展事故前人因(失误)分析的程序。该程序主要包括系统熟悉,定性分析,筛选,定量计算,与故障树的集成,敏感性分析与不确定性分析,形成分析档等几个步骤。     

核电厂操纵员人因失误影响因素分析

为研究核电厂操纵员的行为影响因素 (PIFs)以及它们间的关联关系,通过文献分析,从组织视角建立比较全面具体的PIFs分类体系。统计分析核电厂大量人因事件,识别影响操纵员人因失误的重要因素。基于人因事件样本数据,对PIFs进行相关性分析,研究PIFs之间的相互影响关系。研究表明:影响核电厂操纵员的主要因素为个体因素中的心理状态、素质和能力,情境环境因素中的规程、培训和组织管理等因素;个体因素受各种情境环境因素的影响,但不同的个体因素与各种情境环境因素的影响关系不同,如心理状态主要受人的素质和能力、技术系统等影响,而人的生理状态主要受工作环境、班组因素和组织结构等影响。     

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。     

基于人因失误分析的医院电气安全管理研究

医院是重点用电单位,用电的安全性和供电可靠性都比较高,但因不可抗力、供电系统故障、医院管理问题、人为失误等方面的原因,仍存在发生各类电气突发事件的风险。其中,由人的误操作或不安全行为因素而诱发的电气方面的突发事件已成为医院非医疗事故的主要原因。文章针对医院电气安全操作方面的人因失误,从个人和组织两个角度进行了失误原因的分析,认为人的失误既受个体因素的影响,也受环境、制度和管理水平的影响。在此基础上,提出完善相关规章制度建设、加强教育与培训等,从组织制度建设、人员技术素质提高等方面,提出预防与减少人因失误的措施与方法,提高供配电质量,为医院医疗工作提供有效的电气安全后勤保障。     

核电厂防人因失误管理有效性探讨

介绍了核电人因管理的发展历史,在国际核电业界防人因失误管理标准的基础上,结合部分国内外核电厂的防人因失误管理实践,探讨了影响核电厂人因管理的模型,对业界普遍存疑的概念进行了辨析,分析了影响人因管理有效性的关键因素,提出了提高核电厂防人因失误管理有效性的建议以及良好实践。     

核电厂调试人员职业压力对人因失误的影响路径

为了有效降低核电厂调试人员的职业压力和减少由人因失误造成的安全事故,针对我国核电厂建设中调试工作的特点,基于S-O-R人因失误理论逻辑,将核电厂调试人因失误划分为感知过程失误、识别判断过程失误、行动操作过程失误,引入焦虑情绪作为中间变量,构建核电厂调试人员职业压力对人因失误影响机制理论模型,并运用核电厂调试现场采集的问卷数据对模型进行验证与修正.结果表明:焦虑情绪在职业压力对人因失误影响过程中具有中介作用;职业压力对人因失误存在4条影响路径,路径1为职业压力—认知性焦虑—感知过程失误—识别判断过程失误—行动操作过程失误,路径2为职业压力—认知性焦虑—识别判断过程失误—行动操作过程失误,路径3为职业压力—躯体性焦虑—感知过程失误—识别判断过程失误—行动操作过程失误,路径4为职业压力—躯体性焦虑—行动操作过程失误.研究结论对预防和减少核电厂调试人因事件具有借鉴意义.     

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.     

人因失误机理及原因因素研究

在复杂社会技术系统中,人因失误已成为引发事故的最主要原因之一.给出了国内外学者对人因失误的定义.从个体和组织层次上分析了人因失误的机理,并基于此失误机理分析了人误原因因素,给出了个体和组织层次下的原因因素图.     

煤矿人因组织错误事故致因研究

本文应用编码故障树分析法,从人因组织错误的角度,对煤矿事故致因进行剖析。在综合安全管理学、心理学、组织行为学等学科的基础上,尝试构建煤矿人因组织错误事故模型。     

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.     

Safety assessment for accident of cooling loop failure (ACLF) in lunar nuclear power reactor (LNPR)

The safety assessment of an accident in the lunar base power plant is investigated for the stability of the operation. The lunar surface reactor is modeled for this study. The accident of cooling loop failure (ACLF) is one of the important scenarios for the virtual case in the moon nuclear power plant (NPP). The newly designed lunar nuclear power reactor (LNPR) is suggested for the commercial purpose. The system dynamics (SD) is used for the simulation of the safety assessment. The cyclic variation of the lunar surface temperature can affect to the physical situation of the coolant, which is expressed by the time step. The result shows the performance possibility of the long term cooling increases slightly in the short period of the time step. The dynamical simulation of the lunar environment is performed for the conceptual design of the NPP.     

核电厂起重机安全监控管理系统的应用

本文从法规的要求和核电厂设备运行管理需求两方面介绍核电厂起重机增加安全监控管理系统的必要性,并以核电厂主行车安全监控管理系统为例,介绍了核电厂起重机安全监控管理系统的基本原理和系统构造,阐述了核电厂安全监控管理系统在国标要求基础上进行的设计提升和应用情况,为行业起重机尤其后续新建核电厂起重机安全监控管理系统的设计、验收...     

从材料的冲击损伤研究看核电厂的安全防护

论述了核电厂对外来冲击物的安全防护及其与材料受到冲击损伤之间的关系,讨论了材料在外来物冲击作用下的损伤行为、模式及破坏预测的方法,笔者就材料及其结构的冲击损伤研究提出了建议     

Safety in shipping: the human element

INTRODUCTION: There are numerous diverse papers that have addressed issues within maritime safety; to date there has been no comprehensive review of this literature to aggregate the causal factors within accidents in shipping and surmise current knowledge. METHODS: This paper reviewed the literature on safety in three key areas: common themes of accidents, the influence of human error, and interventions to make shipping safer. The review included 20 studies of seafaring across the following areas: fatigue, stress, health, situation awareness, teamwork, decision-making, communication, automation, and safety culture. RESULTS: The review identifies the relative contributions of individual and organizational factors in shipping accidents, and also presents the methodological issues with previous research. CONCLUSIONS: The paper concludes that monitoring and modifying the human factors issues presented in this paper could contribute to maritime safety performance. IMPACT ON INDUSTRY: This review illustrates which human factors issues are prevalent in incidents therefore this gives shipping practitioners a focus for interventions.     

Assessing safety culture in the Spanish nuclear industry through the use of working groups

This paper presents the design and the implementation of a methodology for measuring and improving safety culture at a nuclear power plant (NPP). The study has involved the completion of a pilot project aimed at seeing how to make use of the RADAR logic (Results, Approach, Deployment, Assessment and Review) of the EFQM model as a tool for the self assessment of safety culture in a nuclear power plant. The work was aimed at finding evidence of the safety culture that was in place at the plant and at identifying both the strengths of that culture and any areas in which it could be improved. The score obtained from an analysis of those strengths and areas for improvement has made it possible to prioritise the actions to be taken. The identification of perceptions and evidence, the agreement on the strong points and areas for improvement and the quantification of the safety culture have been performed by groups comprising volunteers who work at the NPP. The advantages of this methodology are assessed in the paper.