• 품질경영학회지
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• 제37권2호
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• pp.46-57
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• 2009

The traditional approach to economic design of control charts is based on the assumption that a process is monitored using a performance variable. However, various types of automatic test equipments recently introduced as a part of factory automation usually measure surrogate variables instead of performance variables that are costly to measure. In this article we propose a model for economic design of a control chart which uses a surrogate variable that is highly correlated with the performance variable. The optimum values of the design parameters are determined by maximizing the total average income per cycle time. Numerical studies are performed to compare the proposed $\bar{X}$ control charts with the traditional model using the examples in Panagos et al. (1985).

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.973-979
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• 2024

In the framework of the Generation IV research and development project, in which the French Commission of Alternative and Atomic Energies (CEA) is involved, a main objective for the design of Sodium-cooled Fast Reactor (SFR) is to meet the safety goals for severe accidents. Among the severe ones, the Unprotected Transient OverPower (UTOP) accidents can lead very quickly to a global melting of the core. UTOP accidents can be considered either as slow during a Control Rod Withdrawal (CRW) or as fast. The paper focuses on fast UTOP accidents, which occur in a few milliseconds, and three different scenarios are considered: rupture of the core support plate, uncontrolled passage of a gas bubble inside the core and core mechanical distortion such as a core flowering/compaction during an earthquake. Several levels and rates of reactivity insertions are also considered and the thermal-mechanical behavior of an ASTRID fuel pin from the ASTRID CFV core is simulated with the GERMINAL code. Two types of fuel pins are simulated, inner and outer core pins, and three different burn-up are considered. Moreover, the feedback from the CABRI programs on these type of transients is used in order to evaluate the failure mechanism in terms of kinetics of energy injection and fuel melting. The CABRI experiments complete the analysis made with GERMINAL calculations and have shown that three dominant mechanisms can be considered as responsible for pin failure or onset of pin degradation during ULOF/UTOP accident: molten cavity pressure loading, fuel-cladding mechanical interaction (FCMI) and fuel break-up. The study is one of the first step in fast UTOP accidents modelling with GERMINAL and it has shown that the code can already succeed in modelling these type of scenarios up to the sodium boiling point. The modeling of the radial propagation of the melting front, validated by comparison with CABRI tests, is already very efficient.

• 대한기계학회논문집A
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• 제36권10호
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• pp.1289-1295
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• 2012

수소를 대량으로 생산하기 위한 원자력수소생산시스템에서 공정열교환기는 초고온가스로로부터 생성된 초고온 열을 화학반응공정으로 전달하는 핵심기기이다. 한국원자력연구원에 구축되어 있는 소형가스루프에서 Hastelloy-X 로 제작된 소형 공정열교환기(PHE) 시제품에 대한 성능시험이 수행되고 있다. 그동안 소형 PHE 시제품에 대한 고온구조해석은 용접부의 기계적 물성변화를 고려하지 않은 해석이 주로 수행되었다. 본 연구에서는 계장화 압입시험으로부터 얻은 용접부 기계적 물성치를 이용하여 고온구조해석을 수행하고 그 결과를 분석하였다.

• 전력전자학회논문지
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• 제11권3호
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• pp.201-208
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• 2006

최근 에너지 절약에 대한 관심이 고조되면서 기존 광원보다 효율이 좋은 광원개발이 계속되고 있으며 그 대표적인 것이 고효율 및 고출력(high-power) LED이다. 고출력 LED의 개발로 인해 일부에서는 일반 조명용으로 사용하려는 연구가 진행 중이며 풍력과 태양광 발전을 이용한 야간 조명용 전원으로 사용하려는 연구도 진행되고 있다. 이에 본 논문에서는 조명용 광원으로 직류 전원을 이용한 고출력 LED의 사용 가능성을 확인하고자 하며 기존 방식에 비하여 보다 안정적이고 효율이 좋은 새로운 LED 전원구동장치를 제안한다. 제안된 방식은 기존 방식보다 리액터의 크기를 줄일 수 있었으며 효율이 개선됨을 확인하였다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1998년도 제13차 학술회의논문집
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• pp.295-300
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• 1998

In this paper, a real time diagnostic algorithm fur estimating the impact location by loose parts is proposed. It is composed of two modules such as the alarm discrimination module (ADM) and the impact-location estimation module(IEM). ADM decides whether the detected signal that triggers the alarm is the impact signal by loose parts or the noise signal. When the decision from ADM is concluded as the impact signal, the beginning time of burst-type signal, which the impact signal has usually such a form in time domain, provides the necessary data fur IEM. IEM by use of the arrival time method estimates the impact location of loose parts. The overall results of the estimated impact location are displayed on a computer monitor by the graphical mode and numerical data composed of the impact point, and thereby a plant operator can recognize easily the status of the impact event. This algorithm can perform the diagnosis process automatically and hence the operator's burden and the possible operator's error due to lack of expert knowledge of impact signals can be reduced remarkably. In order to validate the application of this method, the test experiment with a mock-up (flat board and reactor) system is performed. The experimental results show the efficiency of this algorithm even under high level noise and potential application to Loose Part Monitoring System (LPMS) for improving diagnosis capability in nuclear power plants.

• 시스템엔지니어링학술지
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• 제9권1호
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• pp.33-45
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• 2013

Systems Engineering Approach was applied to the development of operator-support core management system based on the on-site operation experience and document of core management procedures, which is for enhancing operability and safety in PHWR (Pressurized Heavy Water Reactor) operation. The dissertation and definition of the system were given on th basis of investigating and analyzing the core management procedures. Fuel management, detector calibration, safety management, core power distribution monitoring, and integrated data management were defined as main user's requirements. From the requirements, 11 upper functional requirements were extracted by considering the on-site operation experience and investigating documents of core management procedures. Detailed requirements of the system which were produced by analyzing the upper functional requirements were identified by interviewing members who have responsibility of the core management procedures, which were written in SRS (Software Requirement Specification) document by using IEEE 830 template. The system was designed on the basis of the SRS and analysis in terms of nuclear engineering, and then tested by simulation using on-site data as a example. A model of core power monitoring related to the core management was suggested and a standard process for the core management was also suggested. And extraction, analysis, and documentation of the requirements were suggested as a case in terms of systems engineering.

• 방사성폐기물학회지
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• 제9권2호
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• pp.107-111
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• 2011

해체의 최종단계는 대상 부지 및 건물을 규제로부터 제외하는 것이다. MARSSIM은 부지를 개방하기 위한 최종현황조사를 수행함에 있어 요구되는 자료의 수집 등의 다양한 요건을 만족키기 위한 총괄적인 지침을 제공한다. 연구로 해체 후 부지 및 건물의 최종현황조사를 위해 MARSSIM에서 제시하고 있는 방법을 적용하였다. 연구로 부지의 특성을 반영한 개방기준을 도출하기 위해 RESRAD 및 RESRAD-Build 전산코드를 이용하여 부지 및 건물에 대해서 계산하였다. 부지 및 건물의 조사설계(Survey Design)를 위해서 잠재적 오염도 및 측정 결과를 활용하여 조사구역을 구분하였고, 개략조사 및 특성조사를 통해 수집된 다양한 결과에 기초하여 통계학적 검사를 통해 조사구역 별로 요구되는 시료의 수를 산정하게 된다. 측정된 결과에 기초하여 연구로 최종 개방기준에 만족하는 것으로 평가되었다.

• 대한기계학회논문집A
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• 제26권6호
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• pp.1069-1076
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• 2002

The high temperature creep behavior of heat machine systems such as aircraft engines, boilers and turbines in power plants and nuclear reactor components have been considered as an important and needful fact. There are considerable research results available for the design of high temperature tube materials in power plants. However, few studies on the Initial Strain Method (ISM) capable of securing repair, maintenance, cost loss and life loss have been made. In this method, 3 long time prediction Of high temperature creep characteristics can be dramatically induced through a short time experiment. The purpose of present study is to investigate the high temperature creep lift of Udimet 720, SCM 440-STD61 and 1Cr-0.5Mo steel using the ISM. The creep test was performed at 40$0^{\circ}C$ to $700^{\circ}C$ under a pure loading. In the prediction of creep life for each materials, the equation of ISM was superior of Larson-Miller Parameter(LMP). Especially, the long time prediction of creep life was identified to improve the reliability.

• Transactions on Control, Automation and Systems Engineering
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• 제1권2호
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• pp.141-146
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• 1999

This paper describes the communication method of an auto-startup system. The Auto-Startup system is designed to operate a nuclear power plant automatically during the startup operation . In general , the operations during startup in existing plant have only been manually controlled by the operator. The manual operation caused to the operator mistake. The Auto-Startup system consists of the Distributed Control System(DCS) and G2 (Expert System). Also, Functional Test Facility(FTF) provides the plant's real-data for an Auto-Startup system. So, it is necessary to develop the communication method between these systems. We developed two methods ; one is a network and the other is a hardwire line. To communicate between these systems (DCS-G2 and DCS-FTF) , we developed the communication program. In case of DCS-FTF, we used the TCP/IP and VXI. BUt, in case of DCS-G2 , we , what it called , developed the bridge program using the GSI(G2 Standard Interface). We test to check the function of the important parameter, in time, for analysis of the developed communication method. The results are a good performance when we check the communication time of important parameter. We conclude that Auto-startup system could save heat-up time about at least 5 hours and reduced the change of the reactor operation and trip.

• 비파괴검사학회지
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• 제24권4호
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• pp.384-389
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• 2004

원자력발전소 운전에 따른 경년열화 등에 의하여 원자력발전소 주요 기기 및 재료 등에 손상 발생 가능성이 있어 원자력법 및 관련 기술기준에서는 비파괴검사 방법을 이용하여 원자력발전소 주요 기기 및 배관의 용접부 등 취약 부위에 대한 건전성을 주기적으로 평가토록하고 있다. 이에 따라, 영광 6호기 가동중검사는 기기, 배관 및 구조물 비파괴검사, 압력용기 자동 초음파탐상검사, 원자로 내부 구조물 육안검사 및 증기발생기 전열관 와전류탐상검사로 구분하여 수행하였다. 원자력발전소 계통의 주요기기에 대한 비파괴검사 결과, 기기, 배관 및 구조물과 원자로 압력용기 용접부에 대해서는 특이 사항 발생 없이 적용 규격에 만족되고 건전한 것으로 최종 평가되었다. 특히, 배관 용접부에 대한 초음파탐상검사는 영광 5호기에서와 마찬가지로 ASME Code Sec. XI 1995년도 판에 따라 기량검증(Performance Demonstration : PD) 방법을 적용함으로써 검사 신뢰도를 확보하였다는데 큰 의미가 있다.