• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2013년도 추계학술대회 논문집
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• pp.856-857
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• 2013

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.93-100
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• 2016

Since the sodium-cooled fast reactor is operated in a hostile environment due to the use of liquid sodium as its coolant, advanced techniques for in-service inspection are required to periodically verify the integrity of the reactor. This paper presents the development of in-service inspection techniques for Proto-type Generation IV Sodium-cooled Fast Reactor. First, the 10 m long plate-type ultrasonic waveguide sensor has been developed for in-service inspection of reactor internals, and its feasibility was verified through several under-water and under-sodium experiments. Second, the combined inspection system for in-service inspection of ferromagnetic steam generator tubes has been developed. The remote field eddy current testing and magnetic flux leakage testing can be conducted simultaneously by using the developed inspection system, and the detectability was demonstrated through several damage detection experiments. Finally, the electro-magnetic acoustic transducer which can withstand high temperature and be installable in the remote operated vehicle has been developed for in-service inspection of the reactor vessel, and its detectability was investigated through damage detection experiments.

• 대한간호학회지
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• 제15권2호
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• pp.49-61
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• 1985

It is assumed that the more society advances in its complexity and development, the more people pay attention to their health and accordingly the more people tend to practice health protective behavior. Most of human behavior is based on social inter-actions. The concept in Locus of Control has been developed from social learning theory to help better understanding the social phenomena affecting human behavior. Multidimensional Health Locus of Control is consisted of three dimensions: Internal, Powerful Others and Chance. This study was conducted to find out the health protective behavior patterns of the people and its relationship with Health Locus of Control as an influencing factor to their behavior. All the subjects in this study were the ones of the bank employees in Seoul, Among the total of 1,430 bank employees, 761 were chosen as a sampled subjects. Questionnair survey was conducted from March 4 to March 13, 1985. Research instruments used in this study were two kinds, one was the Health Locus of Control Scale developed by Wallston & Wallston and the other was the Measuring Scale for Health Protective Behavior developed by the investigator. Analysis of data was done by using Descriptive Statistics, X²-test, t-test, ANOVA, Pearson's correlation coefficient. The results of this study are summarized as follows: The mean score of Internal was 24.1, Powerful others was 19.7 and Chance was 15.3 out of maximum range of 6-30 respectively. The mean score of Health Protective Behavior Scale fell as 53.2 out of a maximum range of 18-90. Internals were more likely closely related with sex, educational levels and religion, Powerful others were related with age, educational levels and the number of family members. Chances were related with edu cational levels. The older the subjects were, the more concerned about their health. They tended to practice more favorable health protective behaviors. Furthermore, married people tended to fay more attention to their health than single individuals. Also, the number of family members and religion affected their attitudes in the health protective behavior patterns. Internals and Powerful Others were related with health protective behaviors. If one believes he can do something about his health and others play a significant role on his health, he is more apt protective patterns more suitable for health and actually shows that he is better off.

• 한국가시화정보학회지
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• 제15권3호
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• pp.34-40
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• 2017

Within fractionating devices existing in separation and purification industries, sieve trays are widely used as tower internals and their choice is due to economical attractiveness. While operating a trayed distillation tower weeping phenomenon has a critical effect on the efficiency, in this case study a weeping phenomenon was undertaken by means of numerical model in a rectangular sieve tray. Eulerian-Eulerian Computational Fluid Dynamics (CFD) method was used and the obtained CFD results are in a good agreement with the experimental data in terms of weeping rate and pressure drop.

• 한국압력기기공학회 논문집
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• 제6권1호
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• pp.72-77
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• 2010

During the period of reinforcement work for the licensing renewal of CANDU NPP, the fuel channels, Calandria tubes and feeders of CANDU Reactor are replaced. The remote visual inspection of Calandria internal is also performed during the period of reinforcement work. This period is a unique opportunity to inspect the inside of the Calandria. The visual inspection for the Calandria vessel and its internals of Wolsong NPP Unit 1 was performed by Nuclear Engineering & Technology Institute(NETEC) of KHNP. To perform this inspection, NETEC developed equipment applied new technology such as the synchronization of 3D CAD, automatic alignment and control system. The inspection confirmed that the Calandria integrity of Wolsong NPP Unit 1 is perfect.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2005년도 추계 학술대회논문집
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• pp.45-47
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• 2005

We have investigated the mixing behavior of a tubular heat exchanger reactor using CFD and compared its mixing performance with different type of reactors such as jet mixer and continuous stirred tank reactor (CSTR). The mixedness in each reactor was quantified introducing a statistical average value, the coefficient of variation (CoV), which is a normalized standard deviation of concentration of a component over the whole fluid domain. Through the analysis of the flow pattern and turbulent energy distribution, we suggested a simple but effective way to improve the mixing performance of the tubular heat-exchanger reactor, which include the addition of the internals and/or the increase of the recycle flow rate. It was found that the CoV value of the tubular reactor could be nearly equivalent to that of CSTR by applying those two alternatives suggested here.

• 한국소음진동공학회논문집
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• 제21권11호
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• pp.1036-1042
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• 2011

APR1400 RVI CVAP using the non-prototype category II is being conducted to verify integrity of the RVI design and to secure the CVAP technology. The measurement programs are to confirm vibration analysis results for reactor internals during pre-operational and initial startup testing and to determine the safety margin. One of the important basis for the measurement programs is test acceptance criteria. Therefore, this paper is on establishment of response instrumentation test acceptance criteria for APR1400 RVI CVAP. The established acceptance criteria show that the stress criteria of APR1400 RVI are more conservative values than those of the valid prototype plant(Palo Verde unit 1) and, the displacement criteria of the inner barrel assembly and the upper guide structure were established to 0.03 in and 0.01 in, respectively.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.85-92
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• 2016

The operating temperature of VHTR components is much higher than that of conventional PWR due to high core outlet temperature of VHTR. Material requirements and technical issues of VHTR reactor components which are mainly dominated by high temperature service condition were discussed. The codification effort for high temperature material and design methodology are explained. The design class for VHTR components are classified as class A or B according to the recent ASME high temperature reactor design code. A separation of thermal boundary and pressure boundary is used for VHTR components as an elevated design solution. Key design characteristics for reactor pressure vessel, control rod, reactor internals, graphite reflector, circulator and intermediate heat exchanger were analysed. Thermo-mechanical analysis of the process heat exchanger, which was manufactured for test, is presented as an analysis example.

• 전산구조공학
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• 제9권1호
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• pp.47-54
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• 1996

원자로 내부구조물을 구성하고 있는 중요한 구조물 중의 하나인 제어봉집합체 보호구조물에 대한 랜덤진동의 응답을 구하였다. 제어봉집합체 보호구조물은 본래의 설계로부터 많은 설계변동이 있었고 이에 대하여 많은 우려가 제기되었던 바 본 논문에서는 정상상태에서의 랜덤하중에 대한 동적해석을 수행하여 그 응답을 구하였고 이들을 실험치와 비교, 검토하였으며 제어봉집합체 보호구조물이 구조적으로 안전함을 보였다.

• Structural Engineering and Mechanics
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• 제2권2호
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• pp.157-171
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• 1994

A general approach to the dynamic time-history analysis of the reactor core is presented in this paper as a part of the fuel assembly qualification program. Several detailed core models are set up to reflect the placement of the fuel assemblies within the core shroud. Peak horizontal responses are obtained for each model for the motions induced form earthquake. The dynamic responses such as fuel assembly deflected shapes and spacer grid impact loads are carefully investigated. Also, the sensitivity responses are obtained for the earthquake motions and the fuel assembly non-linear response characteristics are discussed.