• Proceedings of the KSR Conference
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• 2006.11b
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• pp.1140-1145
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• 2006

The railway human reliability analysis (R-HRA) plays a role of identifying and assessing human failure events in the framework of the probabilistic risk assessment (PRA) of the railway systems. This paper reviews three existing HRA methods including the K-HRA (THERP/ASEP-based) method, the HEART method, the RSSB-HRA method, and introduces a case study that was performed to select an appropriate method for a railway risk assessment. The case is the signal passed at danger (SPAD) events, which are caused from a variety of factors. From the case study, the strengths and limitations of each method were derived and compared with each other from the viewpoint of the applicability to the railway industry.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.175-175
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• 1998

• 한국가스학회:학술대회논문집
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• 2005.05a
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• pp.197-197
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• 2005

• Journal of the Ergonomics Society of Korea
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• v.22 no.1
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• pp.31-42
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• 2003

This study describes a modification of the technique for human error analysis in nuclear power plants (NPPs) which adopts advanced Man-Machine Interface (MMI) features based on computerized working environment, such as LCOs. Flat Panels. Large Wall Board, and computerized procedures. Firstly, the state of the art on human error analysis methods and efforts were briefly reviewed. Human error analysis method applied to NPP design has been THERP and ASEP mainly utilizing Swain's HRA handbook, which has not been facilitated enough to put the varied characteristics of MMI into HRA process. The basic concepts on human errors and the system safety approach were revisited, and adopted the process of FMEA with the new definition of Error Segment (ESJ. A modified human error analysis process was suggested. Then, the suggested method was applied to the failure of manual pump actuation through LCD touch screen in loss of feed water event in order to verify the applicability of the proposed method in practices. The example showed that the method become more facilitated to consider the concerns of the introduction of advanced MMI devices, and to integrate human error analysis process not only into HRA/PRA but also into the MMI and interface design. Finally, the possible extensions and further efforts required to obtain the applicability of the suggested method were discussed.

• Journal of the Ergonomics Society of Korea
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• v.33 no.1
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• pp.1-14
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• 2014

Objective: The purpose of this study is to select the methodology for SMR HRA which has characteristics that are different from existing nuclear power plants and digital-based plants. Background: We must assure safety to preoccupy export of technology to developing countries or countries interested in nuclear application. And we can be an advanced country in nuclear technology by securing original technology in the field of SMR such as SMART. Method: THERP, which is the most representative HRA methodology among all, and RARA, which is the latest HRA methodology. This study compared and evaluated THERP and RARA. Results: As a result of applying THERP and RARA methodologies which are based on LOCA EOG task analysis result, this research concluded that RARA has higher personal errors than THERP. Conclusion: This study needs validation for LOCA, emergency operations, normal and abnormal scenarios since HRA methodology was only focused on LOCA scenario. Application: The results of this study can apply as base line data when designing MMIS, which is the main control room of SMART, and when building a simulator.

• Nuclear Engineering and Technology
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• v.51 no.1
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• pp.104-115
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• 2019

Since the Fukushima Daiichi accident, there has been an emphasis on the risk resulting from multi-unit accidents. Human reliability analysis (HRA) is one of the important issues in multi-unit probabilistic safety assessment (MUPSA). Hence, there is a need to properly identify all the human and organizational factors relevant to a multi-unit incident scenario in a nuclear power plant (NPP). This study identifies and categorizes the human and organizational factors relevant to a multi-unit incident scenario of NPPs based on a review of relevant literature. These factors are then analyzed to ascertain all possible unit-to-unit interactions that need to be considered in the multi-unit HRA and the pattern of interactions. The human and organizational factors are classified into five categories: organization, work device, task, performance shaping factors, and environmental factors. The identification and classification of these factors will significantly contribute to the development of adequate strategies and guidelines for managing multi-unit accidents. This study is a necessary initial step in developing an effective HRA method for multiple NPP units in a site.

• The Journal of Asian Finance, Economics and Business
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• v.8 no.7
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• pp.129-137
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• 2021

This paper aims to analyze whether company characteristics are potential determinants of human resource accounting (HRA) disclosure practices by Vietnamese listed companies. It examines the human resource disclosure level of 204 companies by content analysis of these companies' annual reports. The study has relied on a multiple linear regression to test the association between a number of corporate attributes and the extent of human resource disclosure in companies' annual reports. The extent of human resource disclosure was measured using unweighted human resource disclosure index. The explanatory variables considered in this study were firm size, firm age, profitability, leverage, industry profile, and auditor type. The results revealed that the most influential variable for explaining firms' variation in human resource disclosure is firm size followed by firm age and profitability. Thus, it can be concluded that firm size, firm age and profitability are major predictors that may affect the variety of HRA disclosure practices on firms listed in the Vietnam Stock Exchange. However, neither industry profile nor auditor type seems to explain differences in human resource disclosure practices between Vietnamese listed firms, indicating that company's industry profile and auditor type are not a matter for the company to disclose HRA information.

• Nuclear Engineering and Technology
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• v.54 no.3
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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.

• Journal of the Korean Society of Safety
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• v.38 no.6
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• pp.72-78
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• 2023

The purpose of this paper is to derive a quantified approach for Operator Manual Actions (OMAs) based on the existing fire Human Reliability Analysis (HRA) methodology developed by the Korea Atomic Energy Research Institute (KAERI). The existing fire HRA method was reviewed, and supplementary considerations for OMA quantification were established through a comparative analysis with NUREG-1852 criteria and the review of the existing literature. The OMA quantification approach involves a timeline that considers the occurrence of Multiple Spurious Operations (MSOs) during a Main Control Room Abandonment (MCRA) determination and movement towards the Remote Shutdown Panel (RSP) in the event of a Main Control Room (MCR) fire. The derived failure probability of an OMA from the approach proposed in this paper is expected to enhance the understanding of its reliability. Therefore, it allows moving beyond the deterministic classification of "reliable" or "unreliable" in NUREG-1852. Also, in the event of a nuclear power plant fire where multiple OMAs are required within a critical time range, it is anticipated that the OMA failure probability could serve as a criterion for prioritizing OMAs and determining their order of importance.

• Physical Therapy Rehabilitation Science
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• v.5 no.4
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• pp.185-192
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• 2016

Objective: The purpose of this study was to find the limited patterns of middle-aged women in selective functional movement evaluation and analyze the effects of pattern improvement exercises and general control groups on the Health Risk Appraisal (HRA). Design: Randomized controlled trial. Methods: The 31 subjects were physically healthy middle-aged women aged 40-59 living in Seoul, The subjects were randomly divided into an experimental group and a control group. Forty-three physically healthy women were originally recruited and randomly assigned to either the experimental group (n=22) or the control group (n=21). However, due to lack of participation, a total of seventeen subjects in the exercise group and fourteen subjects in the control group participated in the study. All subjects were tested using Selective Functional Movement Assessment (SFMA) and HRA for the baseline measurement and joined an exercise program of their group for one hour per session, twice a week for four weeks. The experimental group was provided with the corrective exercises and the control group was given the general fitness program. A follow-up test was conducted after eight weeks from the baseline measurement. Results: Both experimental and control group showed significant changes in SFMA and HRA scores (p<0.05). In the experimental group and control groups, the SFMA and HRA showed significant improvement from baseline to 4 weeks (p<0.05). Also, in the experimental group, the SFMA was significantly improved from baseline to 8 weeks (p<0.05). For the experimental group, there was a significant improvement in SFMA after 4 weeks compared to the control group (p<0.05). Conclusions: The corrective exercise in the experimental group had a positive effect on the SFMA score as well as the general squat exercise in the control group. The corrective exercise and general control group had the same positive effect on the HRA score.