• Journal of the Korea Safety Management & Science
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• v.25 no.2
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• pp.9-15
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• 2023

The Severe Disaster Punishment Act had recently been established in order to promote safety and health (OSH) management system for severe accident prevention. OSH management system is primarily designed based on risk assessments; however, companies in industries have been experiencing difficulties in hazard identification and selecting proper measures for risk assessments and accident prevention. This study intended to introduce an accident analysis method based on epidemiological model in finding hazard and preventive measures. The accident analysis method employed in this study was proposed by the U.S. Department of Energy. To demonstrate the effectiveness of the accident analysis method, this study applied it to two accident cases occurred in construction and manufacturing industries. The application process and results of this study can be utilized in improving OSH management system and preventing severe accidents.

• Nuclear Engineering and Technology
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• v.38 no.8
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• pp.733-752
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• 2006

Severe accidents in PWRs are characterized by a continuously changing geometry of the core due to chemical reactions, melting and mechanical failure of the rods and other structures. These local variations of the porosity and other parameters lead to multi-dimensionnal flows and heat transfers. In this paper, a comprehensive set of multi-dimensionnal models describing heat transfers, thermal-hydraulics and melt relocation in a reactor vessel is presented. Those models are suitable for the core description during a severe accident transient. A series of applications at the reactor scale shows the benefits of using such models.

• Journal of the Korean Society of Marine Environment & Safety
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• v.30 no.3
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• pp.275-282
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• 2024

To ensure a systematic and integrated approach to defense safety management, individual safety management regulations have been consolidated into the National Defense Safety Directive. However, despite being enacted after the enforcement of the Severe Accident Punishment Act, the National Defense Safety Directive does not incorporate the contents of the Serious Accident Punishment Act. This omission is likely to cause confusion in safety management. In this paper, a PDCA analysis of the Severe Accident Punishment Act and the National Defense Safety Directive was conducted to identify area for improvement and supplementation in the Directive. Chapter 3 proposes amendments to clearly define the scope and responsibilities of safety management, implement serious accident prevention measures and inspections, and establish the penalties for those involved. These amendments aim to ensure faithful compliance with the Severe Accident Punishment Act. Chapter 4 emphasizes the implementation and inspection of risk assessments to enhance the effectiveness of safety accident prevention and preparation, thereby ensuring the completeness of the PDCA cycle.

• Journal of the Society of Disaster Information
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• v.19 no.2
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• pp.372-382
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• 2023

Purpose: Suggests measures to improve the construction company's safety management system according to the enforcement of the Severe Accident Punishment Act. Method: The effectiveness of practice-oriented disaster prevention activities was analyzed through safety and health diagnosis of the level of safety and health management system for the countermeasures against the Severe Accident Punishment Act implemented at the construction site and headquarters. Result: The effect of reducing the accident rate and the advancement of the safety and health management system were analyzed by linking the Severe Accident Punishment Act with the safety and health management system, and a plan to improve the safety and health management system was presented through the analysis of the comprehensive results of safety activities before and after the implementation of the Severe Accident Punishment Act. Conclusion: The effect of practical performance measurement was manifested through the improvement of business owners' awareness, the expansion of investment for disaster prevention, and the quantification of disaster prevention activities according to the enforcement of the Severe Accident Punishment Act.

• Nuclear Engineering and Technology
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• v.48 no.4
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• pp.975-981
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• 2016

The containment response during the first 24 hours of a low-pressure severe accident scenario in a nuclear power plant with a two-loop Westinghouse-type pressurized water reactor was simulated with the CONTAIN 2.0 computer code. The accident considered in this study is a large-break loss-of-coolant accident, which is not successfully mitigated by the action of safety systems. The analysis includes pressure and temperature responses, as well as investigation into the influence of spray on the retention of fission products and the prevention of hydrogen combustion in the containment.

• Nuclear Engineering and Technology
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• v.51 no.3
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• pp.723-730
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• 2019

Acquiring instrumentation signals generated from nuclear power plants (NPPs) is essential to maintain nuclear reactor integrity or to mitigate an abnormal state under normal operating conditions or severe accident circumstances. However, various safety-critical instrumentation signals from NPPs cannot be accurately measured on account of instrument degradation or failure under severe accident circumstances. Reactor vessel (RV) water level, which is an accident monitoring variable directly related to reactor cooling and prevention of core exposure, was predicted by applying a few signals to deep neural networks (DNNs) during severe accidents in NPPs. Signal data were obtained by simulating the postulated loss-of-coolant accidents at hot- and cold-legs, and steam generator tube rupture using modular accident analysis program code as actual NPP accidents rarely happen. To optimize the DNN model for RV water level prediction, a genetic algorithm was used to select the numbers of hidden layers and nodes. The proposed DNN model had a small root mean square error for RV water level prediction, and performed better than the cascaded fuzzy neural network model of the previous study. Consequently, the DNN model is considered to perform well enough to provide supporting information on the RV water level to operators.

• Journal of the Korea Safety Management & Science
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• v.25 no.2
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• pp.71-83
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• 2023

Since last year, the government has enforced the 'Act on the Punishment of Severe Accidents, Etc.' (hereafter referred to as the 'Serious Accident Punishment Act'), which punishes business owners and business managers who fail to fulfill their duty of safety measures with 'imprisonment of one year or more' and the Occupational Safety and Health Act. Based on this, various occupational safety and health policies were developed, including the operation of a system related to entrusting the work of safety managers. Despite these efforts, the effect of implementing the Severe Accident Punishment Act is a groundbreaking change in the current disaster prevention policy, which has increased by 0.02%P and 0.03‱P, respectively, from the previous year to 0.65% of the total accident rate and 1.10‱ of the death rate per 10,000 people as of 2022. As the need emerged, attention was paid to 'collaboration and governance with safety management institutions' in the 'Severe Disaster Reduction Roadmap' announced by the Ministry of Employment and Labor in November 2022. In this study, a meaningful result was derived by comparing and analyzing the industrial accident status of workplaces entrusted by "A" safety management institutions with the national average based on the industrial accident survey table, and the types of industrial accidents that occurred in consigned workplaces were selected as intensive management targets. The policy direction for industrial accident prevention was established. It is necessary to develop safety management work manuals based on the results of this study, expertise, discover best cases of risk assessment and develop guides, and educate and train consigned workers. In addition, it suggests that the government's guidance and supervision are needed to advance the professionalism of safety management entrusted tasks, and that safety management institutions should strengthen their roles and functions for preventing and reducing industrial accidents. However, due to difficulties in disclosing information of specialized safety management institutions, the limitation of the provision, collection, and viewing of research-related data to "A" specialized safety management institutions remains a limitation of the research. It seems likely that more thorough research will be conducted.

• Journal of the Korean Society of Safety
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• v.38 no.4
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• pp.15-22
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• 2023

LPG-related accidents, which account for half of all gas accidents in Korea, have not shown any sign of decrease over the past decade, partially owing to the lack of effective safety improvement measures. The purpose of this study was to identify the effectiveness of improvement measures by analyzing the traits of accidents in terms of human factors, and to seek more effective accident prevention strategies. In this study, 108 accident cases were collected and analyzed in the aspect of accident characteristics such as violation type, human factors, and so on. The results showed that the work procedures of suppliers and engineers related to LPG accidents seemed to be similar in outward appearance; however, specific accident causes and unsafe behaviors were different. Particularly, type and target of violations were different, which could be visually confirmed by the Principal Component Analysis (PCA) and the Quantification Techniques (QT). Furthermore, for engineers, insufficient supervision was a major influencing factor. In conclusion, because the accident characteristics of suppliers and engineers are different, differentiated accident prevention strategies should be implemented, which was discussed in this study.

• Nuclear Engineering and Technology
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• v.48 no.5
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• pp.1174-1183
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• 2016

Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.

• Journal of the Korea Safety Management & Science
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• v.6 no.4
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• pp.39-46
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• 2004

The Study lay Emphasised on to Investigate Human Related Causes of a Pointed End Equipment Accident and the Basic data for Analyzing Human-Error Prevention Program. Peter Son's Model of Human-Error Accident Causation and Cooper's Model of Safety Culture Were Applied to Analyze the Severe Cause of a Pointed End Equipment for Last 5 Years. Through to Analyzing the Cause of Equipment Accident of Human-Error, Expert's Opinion and Experience Theory Method was Reflected. The Analyses Showed What the Immature and Inexperient Error Were Major Causes of a Pointed and Equipment Accident. The Cause of Human-Error was Found with Respect to Human, Tasks, Acknowledge, Organization.