• 제목/요약/키워드: Human Reliability

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Dependence assessment in human reliability analysis under uncertain and dynamic situations

  • Gao, Xianghao;Su, Xiaoyan;Qian, Hong;Pan, Xiaolei
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.948-958
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    • 2022
  • Since reliability and security of man-machine system increasingly depend on reliability of human, human reliability analysis (HRA) has attracted a lot of attention in many fields especially in nuclear engineering. Dependence assessment among human tasks is a important part in HRA which contributes to an appropriate evaluation result. Most of methods in HRA are based on experts' opinions which are subjective and uncertain. Also, the dependence influencing factors are usually considered to be constant, which is unrealistic. In this paper, a new model based on Dempster-Shafer evidence theory (DSET) and fuzzy number is proposed to handle the dependence between two tasks in HRA under uncertain and dynamic situations. First, the dependence influencing factors are identified and the judgments on the factors are represented as basic belief assignments (BBAs). Second, the BBAs of the factors that varying with time are reconstructed based on the correction BBA derived from time value. Then, BBAs of all factors are combined to gain the fused BBA. Finally, conditional human error probability (CHEP) is derived based on the fused BBA. The proposed method can deal with uncertainties in the judgments and dynamics of the dependence influencing factors. A case study is illustrated to show the effectiveness and the flexibility of the proposed method.

건설현장 임시전력 배선의 가설직무에 대한 인간신뢰성 평가 (Human Reliability Assessment for a Installation Task of Temporary Power Cables in Construction Fields)

  • 김두현;이종호;김상철
    • 한국안전학회지
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    • 제20권2호
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    • pp.61-66
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    • 2005
  • This paper presents an human reliability assessment(HRA) for a installation task of the temporary power cable in construction fields. HRA is evolved to ensure that the workers could reliably perform critical tasks such as a process of the temporary power cable. Human errors are extremely commonplace, with almost everyone committing at least some errors every day. The considerable parts of electric shock accidents in the construction field are caused by a series of human errors. Therefore it is required to analyze the human errors contained in the task causing electric shock event, the event tree analysis(ETA) is adopted in this paper, and particularly human reliability was estimated for a installation task of the temporary power cables. It was assumed that the error probabilities of the human actions may be obtained using the technique for human error rate prediction(THERP). The results show that the predominant task on reliability in the cable installation tasks is check-out tasks and the probability causing electric shock by human errors was calculated as $1.0\times10^{-9}$.

원자력발전소 비상운전 직무의 인간오류분석 및 평가 방법 AGAPE-ET의 개발 (AGAPE-ET: A Predictive Human Error Analysis Methodology for Emergency Tasks in Nuclear Power Plants)

  • 김재환;정원대
    • 한국안전학회지
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    • 제18권2호
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    • pp.104-118
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    • 2003
  • It has been criticized that conventional human reliability analysis (HRA) methodologies for probabilistic safety assessment (PSA) have been focused on the quantification of human error probability (HEP) without detailed analysis of human cognitive processes such as situation assessment or decision-making which are crticial to successful response to emergency situations. This paper introduces a new human reliability analysis (HRA) methodology, AGAPE-ET (A guidance And Procedure for Human Error Analysis for Emergency Tasks), focused on the qualitative error analysis of emergency tasks from the viewpoint of the performance of human cognitive function. The AGAPE-ET method is based on the simplified cognitive model and a taxonomy of influencing factors. By each cognitive function, error causes or error-likely situations have been identified considering the characteristics of the performance of each cognitive function and influencing mechanism of PIFs on the cognitive function. Then, overall human error analysis process is designed considering the cognitive demand of the required task. The application to an emergency task shows that the proposed method is useful to identify task vulnerabilities associated with the performance of emergency tasks.

Analysis Testing of Sociocultural Factors Influence on Human Reliability within Sociotechnical Systems: The Algerian Oil Companies

  • Laidoune, Abdelbaki;Rahal Gharbi, Med El Hadi
    • Safety and Health at Work
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    • 제7권3호
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    • pp.194-200
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    • 2016
  • Background: The influence of sociocultural factors on human reliability within an open sociotechnical systems is highlighted. The design of such systems is enhanced by experience feedback. Methods: The study was focused on a survey related to the observation of working cases, and by processing of incident/accident statistics and semistructured interviews in the qualitative part. In order to consolidate the study approach, we considered a schedule for the purpose of standard statistical measurements. We tried to be unbiased by supporting an exhaustive list of all worker categories including age, sex, educational level, prescribed task, accountability level, etc. The survey was reinforced by a schedule distributed to 300 workers belonging to two oil companies. This schedule comprises 30 items related to six main factors that influence human reliability. Results: Qualitative observations and schedule data processing had shown that the sociocultural factors can negatively and positively influence operator behaviors. Conclusion: The explored sociocultural factors influence the human reliability both in qualitative and quantitative manners. The proposed model shows how reliability can be enhanced by some measures such as experience feedback based on, for example, safety improvements, training, and information. With that is added the continuous systems improvements to improve sociocultural reality and to reduce negative behaviors.

Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

  • Zou, Yanhua;Zhang, Li;Dai, Licao;Li, Pengcheng;Qing, Tao
    • Nuclear Engineering and Technology
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    • 제49권2호
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    • pp.335-341
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    • 2017
  • The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

SPAD 인간 신뢰도 모델연구 (Stochastic Model for SPAD Human Reliability)

  • 이강원;정인수
    • 한국철도학회논문집
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    • 제11권1호
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    • pp.75-80
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    • 2008
  • 철도 시스템은 높은 수준의 안전성을 요구하고 있으며 열차속도와 교통량의 증가로 다양한 안전시스템이 도입되었다. 그러나 많은 철도 사고에서도 인간의 책임이 중요한 비중을 차지하고 있으며 철도 시스템의 안전은 여전히 신뢰성 있는 인간의 업무수행능력에 많이 좌우된다. 본 연구에서는 열차사고의 가장 중요한 원인으로 알려진 신호위반 진입(SAPD)에 대한 인간 신뢰도 모델을 제시하였다. 그리 신호 발생 과정과 운전자의 성능 특성을 고려하여 인간 신뢰도를 정량화 할 수 있는 수학적 표현식을 유도하였다.

표준 원자력발전소 확률론적 안전성 평가의 인간 신뢰도 분석 평가 (Evaluation of Human Reliability Analysis Results in Probabilistic Safety Assessment for Korea Standard Nuclear Power Plants)

  • 강대일;정원대;양준언
    • 한국안전학회지
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    • 제18권2호
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    • pp.98-103
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    • 2003
  • Based on ASME probabilistic risk assessment (PRA) and NEI PRA peer review guidance, we evaluate a human reliability analysis (HRA) in probabilistic safety assessment (PSA) for Korea standard nuclear power plants, Ulchin Unit 3&4, to improve it performed at under design. The HRA for Ulchin Unit 3&4 is assessed as higher than Grade I based on ASME PRA standard and as higher than Grade 2 based on NEI PRA peer review guidance. The major items to be improved identified through the evaluation process are the documentation, the systematic human reliability analysis, the participitation of operators in the works and review of HRA. We suggest the guidance on the identification and qualitative screening analysis for pre-accident human errors and solve some items to be improved using the suggested guidance.

A dynamic human reliability assessment approach for manned submersibles using PMV-CREAM

  • Zhang, Shuai;He, Weiping;Chen, Dengkai;Chu, Jianjie;Fan, Hao
    • International Journal of Naval Architecture and Ocean Engineering
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    • 제11권2호
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    • pp.782-795
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    • 2019
  • Safety is always acritical focus of exploration of ocean resources, and it is well recognized that human factor is one of the major causes of accidents and breakdowns. Our research developed a dynamic human reliability assessment approach, Predicted Mean Vote-Cognitive Reliability and Error Analysis Method (PMV-CREAM), that is applicable to monitoring the cognitive reliability of oceanauts during deep-sea missions. Taking into account the difficult and variable operating environment of manned submersibles, this paper analyzed the cognitive actions of oceanauts during the various procedures required by deep-sea missions, and calculated the PMV index using human factors and dynamic environmental data. The Cognitive Failure Probabilities (CFP) were calculated using the extended CREAM approach. Finally, the CFP were corrected using the PMV index. This PMV-CREAM hybrid model can be utilized to avoid human error in deep-sea research, thereby preventing injury and loss of life during undersea work. This paper verified the method with "Jiaolong" manned submersible 7,000 m dive test. The"Jiaolong" oceanauts CR(Corrected CFP) is dynamic from 3.0615E-3 to 4.2948E-3, the CR caused by the environment is 1.2333E-3. The result shown the PMV-CREAM method could describe the dynamic human reliability of manned submersible caused by thermal environment.

New method for dependence assessment in human reliability analysis based on linguistic hesitant fuzzy information

  • Zhang, Ling;Zhu, Yu-Jie;Hou, Lin-Xiu;Liu, Hu-Chen
    • Nuclear Engineering and Technology
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    • 제53권11호
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    • pp.3675-3684
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    • 2021
  • Human reliability analysis (HRA) is a proactive approach to model and evaluate human systematic errors, and has been extensively applied in various complicated systems. Dependence assessment among human errors plays a key role in the HRA, which relies heavily on the knowledge and experience of experts in real-world cases. Moreover, there are ofthen different types of uncertainty when experts use linguistic labels to evaluate the dependencies between human failure events. In this context, this paper aims to develop a new method based on linguistic hesitant fuzzy sets and the technique for human error rate prediction (THERP) technique to manage the dependence in HRA. This method handles the linguistic assessments given by experts according to the linguistic hesitant fuzzy sets, determines the weights of influential factors by an extended best-worst method, and confirms the degree of dependence between successive actions based on the THERP method. Finally, the effectiveness and practicality of the presented linguistic hesitant fuzzy THERP method are demonstrated through an empirical healthcare dependence analysis.

인간실수를 고려한 중복시스템의 신뢰도 분석 (Reliability of the redundant system with dependent human error)

  • 김명기;장순흥
    • 대한인간공학회지
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    • 제1권2호
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    • pp.11-15
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    • 1982
  • There is the possibility that human error during testing and maintenance brings about the failure of the system, the reliability of which depends on mechanical failure and human error. This paper deals with the calculation of the reliability of the redundant system with the dependent hunman error through Karnaugh Map. Two cases are considered. One is the reli- ability of the system neglecting the test interval of each component and the other is that considering the test interval of each component.

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