• Journal of Energy Engineering
• /
• 제25권1호
• /
• pp.15-22
• /
• 2016

The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

• Proceedings of the KSME Conference
• /
• 대한기계학회 2001년도 춘계학술대회논문집E
• /
• pp.51-56
• /
• 2001

Vapor explosion is one of the most important problems encountered in severe accident management of nuclear power plants. In spite of many efforts, a lot of questions still remain for the fundamental understanding of vapor explosion phenomena. Therefore, KAERI launched a real material experiment called TROI using 20 kg of UO2 and ZrO2 to investigate the vapor explosion phenomena. In addition, a small-scale experiment with molten-tin/water system was performed to quantify the characteristics of vapor explosion and to understand the phenomenology of vapor explosion. A number of instruments were used to measure the physical change occurring during the vapor explosion. In this experiment, the vapor explosion generated by molten fuel water interaction is visualized using high speed camera and the pressure behavior accompanying the explosion is investigated.

• Proceedings of the Korea Concrete Institute Conference
• /
• 한국콘크리트학회 1998년도 봄 학술발표회논문집(II)
• /
• pp.725-730
• /
• 1998

In the nuclear power plant, steel or polymer liner plates are adopted to prohibit inner concrete surface contacting with gas or liquid materials. If there is an accident, the plate will be damaged, and concrete shall have final responsibility to safety requirements. In this paper, an experimental research was carried out to investigate the effects of construction joint and wet and loading condition on the permeability of concrete. The test results showed that leakage rate is decreased much more at the following cases than the others : (a)wet condition, (b)without a construction joint case, and (c)case subjected to external loads. It was noted that more reinforcement is required at the latter case.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• 제10권1호
• /
• pp.25-30
• /
• 2014

Korea Hydro & Nuclear Power Co.,LTD(KHNP) was strongly interested in promotion of employee's Safety Culture because it is needed to change the recognition of Safety Culture after the Fukushima accident and Kori-1 blackout event. So, KHNP developed the KHNP Safety Culture Definition, Principles and Attributes and shared them with all employees. By using them, Safety Culture Assessment for a site plant employees was carried out. Through the pilot Safety Culture Assessment in 2012, In 2013, it was expanded to 6 plants and various improvements had been obtained from that. KHNP has been developing a variety of training materials, Safety Culture posters, videos which was designed to give lessons about safety culture with a variety of event cases. And keep trying to form Safety Culture Circumstances In this study, statistic methods are used to verify the effectiveness of KHNP Safety Culture Principles and Safety Culture Assessment.

• Proceedings of the KSME Conference
• /
• 대한기계학회 2003년도 춘계학술대회
• /
• pp.1833-1838
• /
• 2003

In the nuclear power plant, emergency core coolant system(ECCS) is furnished at reactor coolant system(RCS) in order to cool down high temperature water in case of emergency. However, in this coolant system, thermal stratification phenomenon can be occurred due to coolant leaking in the check valve. The thermal stratification produces excessive thermal stresses at the pipe wall so as to yield thermal fatigue crack(TFC) accident. In the present study, when the turbulence penetration occurs in the branch piping, the maximum temperature differences of fluid at the pipe cross-sections of the T-branch with thermal stratification are examine

• Proceedings of the Korean Institute of Navigation and Port Research Conference
• /
• 한국항해항만학회 2019년도 추계학술대회
• /
• pp.211-212
• /
• 2019

Since nuclear power plant accident has occurred in Fukushima, marine pollution problem has been a hot issue due to discharging of contaminated water This paper deals in the marine environment monitoring sensor system. In this paper, we study on sensor and communication system to observe the various source of maritime pollution in realtime and transmit the measured date to observation center.

• Proceedings of the KIEE Conference
• /
• 대한전기학회 2002년도 춘계학술대회 논문집 전기기기 및 에너지변환시스템부문
• /
• pp.270-272
• /
• 2002

The safety of the present railway system has been established through a lot of experience from the railway accident. But nowaday scientific safety assessment methods are exactly required to improve the safety of railway system. In this study, we focused on the methodology of probabilistic risk assessment, which has been developed mainly in the field of nuclear power industry, and considered the process to adopt this method to railway system in order to establish a scientific and comprehensive way of safety assessment.

• Proceedings of the Korean Society for Technology of Plasticity Conference
• /
• 한국소성가공학회 2002년도 춘계학술대회 논문집
• /
• pp.98-102
• /
• 2002

As the nuclear power plant has been operated continuously and increased gradually, transportation and storage of spent fuel are seriously considered nowadays. The transportation cask which contains radioactive material needs to be inspected about structural safety. About safety verification, description of IAEA Safety Standards states that cask must withstand hypothetical accident conditions. In this paper, 9m free drop impact analysis was performed for transportation cask and impact limiter by using the finite element methods. Furthermore, we obtained the dynamic behavior of wood to as compared with safety test results, and verified the safety of transportation cask.

• Proceedings of the Membrane Society of Korea Conference
• /
• 한국막학회 1994년도 심포지움시리즈 Jan-94 기체분리막 기술 및 응용
• /
• pp.23-52
• /
• 1994

The development if separation technology is an important research subject as is clear from its role in the Japanese government's research abd development program for basic technology for the next generation (1981~1990). Japan is poor not only in mineral resources but also in energy resources and if a sudden change occurs in oil producing facility or an accident occurs in a nuclear power plant, then energy policy must undergo changes and economic foundations may collapse. Japan has already experienced this. Although, oil prices are stable at present and Japan can import oil at low cost due to the yen appreciation, Japan needs to promote development work for any new energy crisis that may come in the future. This has been the motive for gas separation membrane development in Japan.

• Journal of the Korean Society for Railway
• /
• 제10권1호
• /
• pp.7-15
• /
• 2007

Since human errors are being recognized as one of the primary issues in railway safety, there is a definite need for human error analysis techniques that can identify the types of errors and their causes and derive effective countermeasures to help reduce their future probability. But, for some reasons, there are not yet systematic procedures or techniques for analyzing human errors in the Korean railway industry. This paper introduces several techniques that have been developed and utilized for analyzing human errors in Korean and overseas nuclear power aviation railway, offshore oil industry, etc., and summarizes the strengths and weaknesses of each technique. Based on the Investigation of the techniques, the paper also discusses the implications for the development of a human error analysis system for the Korean railway industry.