• 멤브레인
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• 제4권1호
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• pp.9-29
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• 1994

The development of separation technology is an important research subject as is clear from its role in the Japanese government's research and 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. The study of gas permeation through polymer membranes, which is the basis for membranes for gas separation, at Japanese universities began many years ago, but interest in membranes for gas separation was aroused mainly by the Government. The development of gas separation membranes in Japan started with membranes for oxygen separation on an industrial scale.

• 대한인간공학회지
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• 제31권1호
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• pp.211-217
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• 2012

Objective: The aim of this study is to show a correct application procedure using the compact Korean anthropometric data application program called Korean Human Scale(KHS) for anthropometric design. Background: The nation-wide anthropometric survey project called 'Size Korea' developed KHS and distributed it to the public on the web site. But some insufficiency of the current web service of KHS misleads the users; they just put their own statue and pick up a meaningless data for a body dimension. Method: This study provides five steps to follow to read appropriate data from KHS for an anthropometric design. Results: As a case study, the depth dimension of the supervisory and control console used in the Korea nuclear power plant was determined following the procedure and compared with the console design guideline recommendation. Conclusion: The supplementary anthropometry table should be added on the web service of KHS for users to read a meaningful data for design. Application: If properly used, the KHS has a lot more potential application area than users can expect such as in control center design area.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2005년도 춘계 학술발표회 논문집
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• pp.464-470
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• 2005

The numerical analysis is carried out to identify the influence of design factors to shear capacity of cast-in-place (CIP) anchor in ACI 349 Code that is available for the design of fastening system at Nuclear Power Plant (NPP) in this study. The MASA program is used to develop the numerical analysis model and the developed numerical analysis model is verified on a basis of the various test data of CIP anchor. Both $l/d_o$ and $c_1/l$ we considered as design factors. As a result, the variation of $l/d_o$ has no influence on the shear capacity of CIP anchor but $c_1/l$ has a large influence on the shear capacity of CIP anchor, Therefore, it is proved that ACI 349 Code may give a non-conservative results compared with real shear capacity of CIP anchor according to $c_1/l$.

• 전기저널
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• 6호통권5호
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• pp.32-37
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• 1975

원자력 발전 계획에 채택은 현대적인 경영 및 산업상의 개념에서 얻을 수 있는 이점을 누릴 기회가 되는 것이므로 이러한 개념들은 발전소의 계획설계 제 허가 및 건설공사의 제반 과정에서 적용시킬 수가 있는 것이다. 따라서 이러한 현대적 개념의 적용 대상인 원자력발전소와 다른 공업제품에서 이 두가지 사이의 중요한 차이점은 1. 각 계통간에 복잡한 상호 관련성이 있다는 것. 2. 안전계통과 그의 해석에 고도의 신뢰성이 요구된다는 것. 그리고 3. 고가의 투자액이 소요된다는 것에 있다. 이러한 개념은 일단 채택 소화된 후에야 원자력발전소 후속기업무와 기타의 산업분야 및 산업경영에 까지 광범위하게 유익하도록 적용할 수가 있으며 이들의 적용은 생산성의 구체적인 증가를 유도함으로써 시간과 자본의 투자보상이 개선된다. 여기서는 주어진 시간이 제한되어 있으므로 이러한 개념중이 일부만을 골라서 개진한다.

• 한국압력기기공학회 논문집
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• 제6권1호
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• pp.9-15
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• 2010

This paper describes the Visual Tool for automatic ultrasonic examination that is under developing as a part of the project for development of automatic ultrasonic wave acquisition and analysis program. This tool that is supported by various image processing techniques will be adopted to detect the flaws in the component and piping welds in NPP. Visual Tool will enhance the integrity of nuclear power plant. The object of this paper is to address the Visual Tool which is developing for automatic ultrasonic inspection of welds in NPP.

• Journal of Welding and Joining
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• 제11권4호
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• pp.103-111
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• 1993

Recently, several high-tensile steels(e.g. 80kg and above, $2^{1/4}Cr$-1Mo)having good quality to high temperature and pressure-resistance are widely used to construct petroleum-plant and pressure vessel of heat or nuclear-power plant. However, in the steels, reheating crack at grain boundaries of the heat affected zone(HAZ) occures during post welding heat treatment(PWHT)to remove welding residual stress. In order to study theoretically the characteristics of reheating crack created by PWHT, the computer program of three-dimensional thermal-elasto-plasto-creep analysis based on finite element method are developed, and then the mechanical behavior(history of creep strain accumulation and stress relaxation, etc)of welded join in thick plate during PWTH is clarified by the numerical results.

• 비파괴검사학회지
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• 제13권2호
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• pp.48-60
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• 1993

1974년에 유럽에서 시작된 PISC(Program for the Inspection of Steel Components ; PISC-I, II, III) 수행결과나 1980년대초 실시된 미국의 BWR 원전 배관계통의 입계응력부식균열(IGSCC ; Intergranular Stress Corrosion Cracks)검사결과에서 나타난 바와 같이 기존의 규격 요건과 절차에 따른 원자력발전소 기기에 대한 초음파탐상검사는 그 실효성에 많은 문제점이 제기되었다. 따라서, 원전기기의 건전성 및 초음파탐상검사 결과의 신뢰도를 보증하기 위한 각종 연구가 진행되고 여러 방안이 모색되어 왔다. 그 결과, 원전 가동중검사 규격에 "초음파탐상검사자 자격인정 요건"과 "초음파탐상검사 시스템(검사자, 장비 및 절차서)에 대한 기량검증 요건"이 새로이 부가되었다. 본고에서는 초음파탐상검사 결과의 신뢰도 확보에 있어 필수불가결한 요건인 원전기기 초음파 탐상검사 시스템에 대한 기량검증 요건을 자세히 기술한다.

• International Journal of Safety
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• 제2권1호
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• pp.50-56
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• 2003

There are a lot of uncertainties in the severe accident phenomena and scenarios in nuclear power plants (NPPs) and one of the major issues for severe accident management is the reduction of these uncertainties. The severe accident management aid system using Probabilistic Safety Assessments (PSA) technology is developed for the management staff in order to reduce the uncertainties. The developed system includes the graphical display for plant and equipment status, previous research results by a knowledge-base technique, and the expected plant behavior using PSA. The plant model used in this paper is oriented to identify plant response and vulnerabilities via analyzing the quantified results, and to set up a framework for an accident management program based on these analysis results. Therefore the developed system may playa central role of information source for decision-making for severe accident management, and will be used as a training tool for severe accident management.

• 한국게임학회 논문지
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• 제2권2호
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• pp.46-51
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• 2002

In this study, a real-time simulation method for the phenomena, which are too complex to be simulated during real-time computer games, was proposed based on the neural network. The procedure of proposed method is to 1) obtain correlation data between input parameters and output parameters by mathematical modeling, code analyses, and so on, 2) train the neural network with the correlation data, 3) and insert the trained neural network in a game program as a simulation module. For the case that the number of the input and output parameters is too high to be analyzed, a method was proposed to omit parameters of little importance. The method was successfully applied to severe accidents of nuclear power plants, reflecting that the method was very effective in real time simulation of complex phenomena.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2006년도 정기 학술대회 논문집
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• pp.575-580
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• 2006

Air-operated valves are extensively used for process control and system isolation functions in nuclear power plant, where the safety is primary issue. The purpose of this study is to develop structural analysis code of various air-operated valves such as globe valve, gate valve, and butterfly valve. The thrust formula is derived for valve with the expected weak areas. The expected weak areas are referred from EPRI data. The structural stress analysis is carried out by analytical and commercial FEM code, ANSYS 8.0. The numerical results are compared together and verified on program procedures.