• Nuclear Engineering and Technology
• /
• v.54 no.4
• /
• pp.1153-1160
• /
• 2022

The application of video processing techniques are useful for the safety of nuclear power plants by tracking the people online on video to estimate the dose received by staff during work in nuclear plants. Nuclear reactors remotely visually controlled to evaluate the plant's condition using video processing techniques. Internal reactor components should be frequently inspected but in current scenario however involves human technicians, who review inspection videos and identify the costly, time-consuming and subjective cracks on metallic surfaces of underwater components. In case, if any frame of the inspection video degraded/corrupted/missed due to noise or any other factor, then it may cause serious safety issue. The problem of missing/degraded/corrupted video frame estimation is a challenging problem till date. In this paper a systematic literature review on video processing techniques is carried out, to perform their suitability analysis for NPP applications. The limitation of existing approaches are also identified along with a roadmap to overcome these limitations.

• Proceedings of the KSR Conference
• /
• 2011.10a
• /
• pp.2557-2562
• /
• 2011

The purpose of Overall Railroad Safety Audit(ORSA) is to prevent railroad accidents, and, every two years, to inspect and evaluate whether or not railroad operators faithfully adhere to railroad safety guidelines in accordance with the Railroad Safety Law. However despite of the many contributions of ORSA, due to lots of railroad accidents such as train failures and derailment caused track irregularity this year, it has been recently considered that ORSA will be renewed into Safety Certificates System as a complement. In order to guarantee railroad safety, new Safety Certificates must included appropriate safety standards considering current our country's railroad conditions. Therefore, in this study we're going to compare safety components of foreign audit system with those of Airlines field, based on ORSA's contents for years, to review Safety Management System and Safety Culture, as a result, we'd like to suggest to updated Railway Safety Standards.

• Proceedings of the KSR Conference
• /
• 2004.06a
• /
• pp.664-669
• /
• 2004

In rolling stock, wheels are one of the most important components to run on the track in safety. Especially, it is important that wheel profile cause the variation of dynamic characteristics and running safety. The purpose of this paper is to propose the wheel profile and to know the effectiveness of improved wheel profile by using microphones. We also performed analysis of running safety to know application of improved wheel profile before the test. In result, the improved wheel profile was stable in running safety and noise level was reduced.

• Proceedings of the KSR Conference
• /
• 2003.10b
• /
• pp.229-234
• /
• 2003

In this paper, the elemental components and improving purpose in advanced safety management system are reviewed to cope with a railway fire accident. And a considering procedure(V-cycle) of long-term plan for railway fire safety improvement is proposed. For the purpose of preventing recurrence of accident, items which have to be considered in the course of accident investigation and cause analysis are presented according to the stage of investigation activity.

• The Transactions of the Korean Institute of Power Electronics
• /
• v.21 no.3
• /
• pp.254-259
• /
• 2016

Recently, DC distribution systems have become a hot issue because of the increase in digital loads and DC generation systems according to the expansion of renewable energy technologies. To obtain the practical usage of DC electricity, safety should be guaranteed. The main concerns for safety are twofold: one side is human protection against electric shocks, and the other is facility protection from short faults. "Effects of current on human beings and livestock" (IEC 60479) defines a human body impedance model in electric shock conditions that consists of resistive components and capacitive components. Although the human body impedance model properly works in AC electricity, it does not well match with the electric shock behavior in DC electricity. In this study, the contradiction of the human body impedance model defined by IEC 60479 in case of DC electricity is shown through experiments for the human body. From the analysis of experimental results, a novel unified human body impedance model in electric shock conditions is proposed. This model consists of resistive components, capacitive components, and an inductance component. The proposed human impedance model matches well for AC and DC electricity environments in simulation and experiment.

• Journal of Radiation Protection and Research
• /
• v.45 no.1
• /
• pp.26-34
• /
• 2020

Background: We examined changes in red ginseng components after different doses of irradiation were applied. We also evaluated what housewives and teachers know about irradiated food, as well as their perceptions of and attitudes toward it. Materials and Methods: General nutrients and unique components of irradiated ginseng were then analyzed. Education on irradiated foods and red ginseng was provided to teachers and housewives on two occasions, and changes in their behaviors were evaluated via a qualitative survey. Results and Discussion: The ideal radiation dose to reduce the number of bacteria without changing the unique components of red ginseng is 7.5 kGy. Notably, after educational seminars on this topic, consumers' knowledge, attitudes toward, and perceptions of irradiated ginseng compared to non-irradiated red ginseng changed significantly. Conclusion: It is necessary to provide consumers with information on irradiated foods to promote the growth of the domestic food industry, and to improve public knowledge of the safety and effects associated with the irradiation of food.

• Journal of the Korean Society of Safety
• /
• v.21 no.6 s.78
• /
• pp.20-25
• /
• 2006

In the design of class 1 components to apply ASME code section III NB, a fatigue is considered as one of the important failure mechanisms. Fatigue analysis procedure and standard fatigue design curve(S-N curve) is suggested in ASME code, which had to be performed to meet the integrity of components at the design step. As the plant life extension for operating power plants and the long-lived plant design, however, are being progressed, the fact which the existing ASME fatigue design curve can not consider fatigue effects sufficiently comes to the fore. To find the technical solution for these problems, a number of researches and discussion are continued up to now. In this study, the detailed fatigue analyses using the 3 dimensional modeling for the fatigue-weakened components were performed to develop the optimized fatigue analysis procedure and their results are compared with other reference solutions.

• Journal of the Korean Society of Safety
• /
• v.25 no.6
• /
• pp.53-59
• /
• 2010

A fatigue damage caused by cyclic load is considered as one of the important failure mechanisms that threaten the integrity of structures and components in a nuclear power plant. In ASME code section III NB, the fatigue analysis procedure and standard S-N curves for the class 1 components are described and these criteria should be met at the design step of components. As the current ASME S-N curves are based on the very conservative assumptions such as a local stress concentration effect, immoderate transient frequencies and a constant Young's modulus, however, they can not precisely address the fatigue behavior of components. In order to find out the technical solution for these problems, a number of researches and discussion have been carried out continuously at home and abroad over the decades. In this study, detailed fatigue analyses for DVI nozzle with various mesh density of finite elements were performed to evaluate effect of stress concentration factors on the fatigue analysis procedure and the excessive conservatism of stress concentration factors are confirmed through the analysis results.

• The Korean Journal of Food And Nutrition
• /
• v.32 no.5
• /
• pp.401-407
• /
• 2019

This study compares and analyzes inorganic components of four different Pu-erh tea species consumed in Korea. The criteria for the inorganic components was based on the Royal Institute of Technology (KTH) recommendations. Out of the 19 general items: potassium, manganese, silicon and fluorine were detected in amounts exceeding the maximum allowable concentration by 5~23, 57~91, 1.6~1.8 and 9~18 times respectively. Out of the 15 potentially harmful elements: aluminum and nickel were exceeded the Maximum allowable concentration by 9~14 times and 0.8~1.2 times respectively. To reduce the concentration of inorganic elements in excess of the maximum allowable concentration, the extraction time of tea should be less than 1 minute in addition to limiting the amount. The amount of Pu-erh tea for extraction was about 0.1 g manganese, about 0.3 g potassium, about 0.5 g fluoride and about 2 g silicon. Therefore, the maximum amount of tea for extraction should be 0.1 g in regards to the safety of Pu-erh tea. Based on the recommended maximum daily intake of inorganic ingredients by the Ministry of Food and Drug Safety, it is desirable that the number of extractions be less than three.

• 연구논문집
• /
• s.25
• /
• pp.5-12
• /
• 1995

Mold platen are one of the most important structural components of the injection molding machine. Mold platen had been designed, and manufactured based on the experience and the method of trial and error. Recently, as the computer progress, the numerical simulation method using commercial finite element analysis code has been used to analyze the characteristics of components. It's a urgent problem to reduce the weight of mold platen while preserving the safety and reliability for the structual failure. Finite element analyses to establish basic design technologies and reducing the weight of mold platen were carried out. As result, we are obtained the about 10% reducing the weight for mold platen.