• Proceedings of the Safety Management and Science Conference
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• 2004.05a
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• pp.33-39
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• 2004

The chemical factory deals with dangerous element and more advance, human-error analyzes and becomes effective research for the country and region, this paper analyes the form of work-miss on human-error according to a safety accident for domestic chemical factory from 1999-2002. It include the present contents and raise issues human knowledge, behavior, judgment, sensibility as an important counterplan that makes the safety solution of work miss. For the point of view of human knowledge, it takes color standard for works to be effective in work place. for behavior, the test has been for risk point of work place and infra worker movement, also the workers performed professional work as classify according to work. for judgement, the valuation sheet is reflected to minimize the human -error and the 3rd supervisor does a cross-check audit beforehand. For sensibility, it is applicable for human relations, information, communication by program to the consciousness and an attitude of worker-supervisor.

• Proceedings of the KIEE Conference
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• 1998.07c
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• pp.1170-1172
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• 1998

The electrical power of nuclear power plant consists of Safety related power systems and Non-Safety related power systems. The safety related power systems are designed to have sufficient capacity to safely shut down the unit and to mitigate the effects of an accident assuming loss of off-site power. This paper presents the operation scheme of the safety related power system for several plant conditions in Korean Next Generation Reactor and reviews the diversity of power supply to the safety related bus.

• Nuclear Engineering and Technology
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• v.43 no.2
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• pp.175-186
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• 2011

Previous evaluations of the safety of the Ulchin Nuclear Power Plant in the event of a tsunami have the shortcoming of uncertainty of the tsunami sources. To address this uncertainty, maximum and minimum wave heights at the intake of Ulchin NPP have been estimated through a parametric study, and then assessment of the safety margin for the intake has been carried out. From the simulation results for the Ulchin NPP site, it can be seen that the coefficient of eddy viscosity considerably affects wave height at the inside of the breakwater. In addition, assessment of the safety margin shows that almost all of the intake water pumps have a safety margin over 2 m, and Ulchin NPP site seems to be safe in the event of a tsunami according to this parametric study, although parts of the CWPs rarely have a margin for the minimum wave height.

• Nuclear Engineering and Technology
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• v.51 no.5
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• pp.1289-1296
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• 2019

Non-functional requirements plays a critical role in designing variety of applications domain ranges from safety-critical systems to simple gaming applications. Performance is one of the crucial non-functional requirement, especially in control and safety systems, that validates the design. System risk can be quantified as a product of probability of system failure and severity of its impact. In this paper, we devise a technique to do the performance analysis of safety critical and control systems and to estimate performance based risk factor. The technique elaborates Petri nets to estimate performability to ensure system dependability requirements. We illustrate the technique on a case study of Nuclear Power Plant system. The technique has been validated on 17 safety critical and control systems of Nuclear Power Plant.

• Journal of the Korean Society of Safety
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• v.29 no.4
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• pp.132-139
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• 2014

According to the increase of foreign laborers at domestic construction sites, it's necessary to research in terms of the unsafe acts of both Korean and foreign laborers in order to prevent construction disasters. The objective of this study is to clarify the characteristics and the improvement priority of the unsafe acts using IPA(Importance-Performance Analysis). The result of this study showed which items of unsafe acts are identify difference between Korean and foreign laborers. Moreover, the result of IPA also showed items of unsafe acts that needed the immediate improvement for each one. Especially there are two items, i.e. equipment malfunction and wrong handling of hand tools, which both Korean and foreign laborers think simultaneous those needs improvement. The results can be utilized to plan and to improve the safety management and education at a site considering the characteristics of foreign laborers.

• Safety and Health at Work
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• v.10 no.1
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• pp.54-60
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• 2019

Background: Increasing the establishment of integrated management systems (IMSs) is done with the purpose of leaving traditional management methods and replacing them with modern management methods. Thus, the present study sought to analyze the events and investigate the impact of IMS on health and safety performance indices in an Iranian combined cycle power plants. Methods: This case study was conducted in 2012 in all units of the Yazd Combined Cycle Power Plant on accident victims before and after the implementation of IMS. For data analysis and prediction of indices after the implementation of IMS, descriptive statistics and Kolmogorov-Smirnov test, Chi-square, linear regression, and Cubic tests were conducted using SPSS software. Results: The number of people employed in the power plant in an 8-year period (2004-2011) was 1,189, and 287 cases of work-related accidents were recorded. The highest accident frequency rate and accident severity rate were in 2004 (32.65) and 2008 (209), respectively. Safe T-score reached to below -3 during 2010-2011. In addition, given the regression results, the relation between all predictor variables with outcomes was significant (p < 0.05), except for the variable $X^1$ belonging to the accident severity rate index. Conclusion: The implementation of safety programs especially that of IMS and its annual audits has had a significant impact on reducing accident indices and improving safety within the study period. Accordingly, health and safety management systems are appropriate tools for reducing accident rate, and the use of regression models and accident indices is also a suitable way for monitoring safety performance.

• Korean Journal of Veterinary Research
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• v.54 no.3
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• pp.151-157
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• 2014

A nationwide survey on radiation safety management in Korean animal hospitals was conducted. By 2013, 53 radiation generators were registered as veterinary medical devices (41 X-ray generators and 12 computed tomography scanners). Additionally there were six approved laboratories for radiation equipment and protection facility, and five approved laboratories for radiation exposure of employees, respectively. By March 2013, 2,030 out of 3,829 animal hospitals operated radiation-generating devices. Among these devices, 389 (19.2%) out of 2,030 were not labeled with the model name and 746 (36.7%) were not labeled with production dates. Thus, most veterinary X-ray generators were outdated (42.6%) and needed replacements. When periodic inspections of 2,018 animal hospitals were performed after revision of the Veterinarians Act in 2011, the hospitals were found to be equipped with appropriate radiation generators and protection facilities. Among 2,545 employees exposed to radiation at the hospitals, 93.9% were veterinarians, 4.3% were animal nurse technicians, and 18% held other positions. Among 169 employees supervised by administrators, none of those had a weekly maximum operating load that exceeded $10mA{\cdot}min$. This study suggests that the radiation safety management system of animal hospitals was general good.

• Nuclear Engineering and Technology
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• v.54 no.5
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• pp.1698-1711
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• 2022

A combined safety approach, which uses a best-estimate computer code and adopts conservative assumptions for safety systems availability, is developed and applied to the safety margin evaluation for the Loss of Condenser Vacuum (LOCV) of the 1000 MWe Korean Nuclear Power Plant. The Multi-dimensional Analysis of Reactor Safety-KINS standard (MARS-KS) code is selected as a best-estimate code and the PAPIRUS program is used to obtain different initial operational conditions through random sampling of control variables. During an LOCV event, fuel integrity is not threatened by the increase in Departure from Nuclear Boiling Ratio (DNBR). However, the high pressure in the primary coolant system and the secondary system might affect the system integrity. Thus, the peak pressure becomes a major safety concern. Transient analyses are performed for 124 cases of different initial conditions and the most conservative case, which results in the highest system pressure is selected. It is found the suggested methodology gives similar peak pressures when compared to those predicted from existing methodologies. The proposed approach is expected to minimize the time and efforts required to identify the conservative plant conditions in the existing conservative safety methodologies.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.1319-1320
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.693-694
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• 2005