• Journal of the Korea Safety Management & Science
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• v.13 no.1
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• pp.69-73
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• 2011

Questionnaire survey has been made for the above study. First, 65 question sheets have been distributed to railway operators and 55 sheets of them have been collected from them. SPSS 12.0 program package has been used to analyze those sheets concerning age, experience, school, background as a frequency analysis and t-test has been made to find out recognition level difference of a cheer response, depending on the operator's experience. T-verification has been made for two groups such as less than 10 years, and 10 years or more experience. Result from correlation analysis showed that there was no difference due to operators' experience.

• Proceedings of KOSOMES biannual meeting
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• 2017.11a
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• pp.130-130
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• 2017

• Journal of the Korea Safety Management & Science
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• v.15 no.4
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• pp.131-136
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• 2013

Automobile was first introduced in 1903 in South Korea, the masses of the car was carried out rapidly compared to other countries. However, many people were killed in a traffic accidents and economic loss was occurred due to the spread of the automobile. In South Korea, 2012, traffic accident occurred 223,656 times, 5,392 fatality, 344,565 injured people. In the last five years, about 224,000 accidents per year were occurring. In other words, 610 traffic accidents occur and about 15 people pass away in one day. In addition, the proportion of traffic accidents is first place in the OECD countries and it is very high in the world. Understand occurrence tendency of traffic accident, accident frequency rate of the driver who drives more than 10 years was higher than the novice driver. In addition, as a result of examining the cause of the traffic accident, breach of safe driving obligation appears highest case (125,391 times), and followed by signal violation, break safety distance. Therefore, the majority of traffic accidents occurred by the lack of safety awareness of the driver. In this study, prevent the loss of human life and property in traffic disaster, by establish disaster prevention measures that investigated by questionnaire survey and statistical data of the state of consciousness and driving posture in response to the driving history of the driver.

• Korean Journal of Agricultural Science
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• v.44 no.4
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• pp.620-635
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• 2017

This study was intended to identify the main factors responsible for the decline in purchase of imported agricultural and fish products after Japan's nuclear power plant accident in 2011 and to compare the effects on imported agricultural produce and imported fish products. Logit model and multiple regression model analyses were performed using consumers' survey data. Psychological and qualitative factors reflecting consumers' food safety awareness and purchasing preferences, which were extracted by Factor analysis, were included as the models' explanatory variables, along with socio-demographic and economic factors. The Logit estimation showed aged, married, and low-income households had significantly higher probability of reducing their purchases of imported agricultural and fish products. However, the multiple regression results pointed out that the actual rate of decrease of imported agricultural and fish products purchases were more significantly affected by non-socio demographic factors such as past experience of purchasing imported agricultural and fish products, future intention to purchasing Japanese agricultural and fish products, and the ratio of imported to domestic agricultural and fish products before the nuclear accident, as well as consumers' feeling of food insecurity and their purchasing preferences. Moreover, the results showed that Korean consumers have reacted more sensitively to the decline in imported fish products than imported agricultural produce after the nuclear accident based on the marginal effects of various socio-demographic and economic factors.

• Nuclear Engineering and Technology
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• v.45 no.6
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• pp.767-790
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• 2013

MAAP4 is a computer code that can simulate the response of a light water reactor power plant during severe accident sequences, including actions taken as part of accident management. The code quantitatively predicts the evolution of a severe accident starting from full power conditions given a set of system faults and initiating events through events such as core melt, reactor vessel failure, and containment failure. Furthermore, models are included in the code to represent the actions that could mitigate the accident by in-vessel cooling, external cooling of the reactor pressure vessel, or cooling the debris in containment. A key element tied to using a code like MAAP4 is an uncertainty analysis. The purpose of this paper is to present a MAAP4 based analysis to examine the sensitivity of a key parameter, in this case hydrogen production, to a set of model parameters that are related to a Level 2 PRA analysis. The Level 2 analysis examines those sequences that result in core melting and subsequent reactor pressure vessel failure and its impact on the containment. This paper identifies individual contributors and MAAP4 model parameters that statistically influence hydrogen production. Hydrogen generation was chosen because of its direct relationship to oxidation. With greater oxidation, more heat is added to the core region and relocation (core slump) should occur faster. This, in theory, would lead to shorter failure times and subsequent "hotter" debris pool on the containment floor.

• Journal of the Korea Safety Management & Science
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• v.17 no.4
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• pp.23-33
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• 2015

Recently, the Ministry of Employment and Labor Management is a trend to strengthen all men death rate than the accident rate. Points reduction in the accident rate change orders related to credit rating score to +2 points in his plans as part of +1 point. In addition, according to the fancy linger RISK treatment in the event of a disaster site and fiction treatment to achieve accident-free during processing the scene interspersed with equity issues have been raised. In general disaster for the problem in the first two cases occurs when abnormal process according to the disaster site manager positions dismissal policy, each division headquarters itself, interspersed disasters performance compared to processing in accordance with the refrain, processing expenses in accordance with the composition of untreated industrial accident, costs and burdens partners FTC, there is a possibility that the issues raised, such as the Ministry of Employment and Labor. In response to domestic social practices focused on the construction site practices and prevention measures should be evaluated with respect to what.

• The Journal of the Convergence on Culture Technology
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• v.9 no.4
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• pp.543-548
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• 2023

Korea has achieved great economic growth, but the high rate of accidents in the industry still threatens the safety of workers and causes a lot of property loss. In order to lower the accident rate, the Occupational Safety and Health Act was fully revised in April 2020 and safety management was strengthened, but the number of deaths rather increased. In response, the government and the National Assembly implemented the Serious Accident Punishment Act in January 2022, but the effect has not been confirmed. So, this study conducted a questionnaire survey on how the safety awareness of construction site workers and managers was affected after the Serious Accident Punishment Act. and suggested measures to improve safety management.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.514-515
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• 2005

• Journal of the Korean Society of Safety
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• v.35 no.4
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• pp.84-91
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• 2020

The Korean nuclear industry developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code and this code adpots two-phase flows, two-fluid, three-field models which are comprised of gas, continuous liquid and droplet fields and has a capability to simulate three-dimensional model. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for accident management plan of nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification work for separate and integral effect experiments is required. In this reason, the goal of this work is to verify calculation capability of SPACE code for multiple failure accident. For this purpose, it was selected the experiment which was conducted to simulate a Multiple Steam Generator Tube Rupture(MSGTR) accident with Passive Auxiliary Feedwater System(PAFS) operation by Korea Atomic Energy Research Institute (KAERI) and focused that the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The MSGR accident has a unique feature of the penetration of the barrier between the Reactor Coolant System (RCS) and the secondary system resulting from multiple failure of steam generator U-tubes. The PAFS is one of the advanced safety features with passive cooling system to replace a conventional active auxiliary feedwater system. This system is passively capable of condensing steam generated in steam generator and feeding the condensed water to the steam generator by gravity. As the results of overall system transient response using SPACE code showed similar trends with the experimental results such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it could be concluded that the SPACE code has sufficient capability to simulate a MSGTR accident.

• Journal of Navigation and Port Research
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• v.41 no.3
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• pp.165-172
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• 2017

Current scenarios for marine spill accidents were developed based on probable maximum spill accidents. However,, accidents of similar scale to maximum spill accidents are virtually non-existent, and training or deployment of response equipment based on these scenarios can be cost prohibitive. Current scenarios require realism for practical use and need to be designed for purpose of use. In this study we developed scenarios that may replace current scenarios by using the HNS accident standard codes based on past accident cases. Scenarios were developed by modularizing the HNS accident standard code, that is classified into three scenarios: Maximum Frequency Scenario, Maximum Damage Scenario, and Maximum Vulnerability Scenario. The situation of an accident presented in each scenario developed in this process is much like a real accident, and therefore, it is has practical application.