• 한국정보과학회논문지:소프트웨어및응용
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• 제32권2호
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• pp.108-118
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• 2005

원자력 발전소의 디지털 제어 시스템은 안전성이 중요시되는 safety-critical 소프트웨어로서 충분한 수준의 안전성을 보장하기 위해서 여러 기법들이 적용되고 있다. 특히, 정형명세 기법은 개발의 초기 단계에서 소프트웨어 요구 사항들을 명확하고 완전하게 명세하도록 유도함으로써 안전성을 크게 향상시킬 수 있는 기법으로 인정받고 있다. 본 논문에서는 정형명세 기법인 NuSCR을 이용해서 작성된 요구사항 명세로부터, 설계 단계의 내용으로 사용될 수 있는 PLC 기반의FBD 프로그램을 체계적으로 생성하는 기법을 제안하고 있다. 제안된 기법은 기존의 수동 명세 작업에서 발생할 수 있는 오류들을 크게 줄일 수 있으며, 소프트웨어의 개발 비용과 기간을 줄일 수 있다. 또한, 제안된 기법의 유용성을 증명하기 위해서, 현재 KNICS에서 개발 중인 DPPS RPS의 BP를 구성하는 트립 논리 중의 하나인 고정 설정치 상승 트립을 예제로 설명하고 있다.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1192-1205
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• 2016

Field programmable gate array (FPGA)-based systems are thought to be a practical option to replace certain obsolete instrumentation and control systems in nuclear power plants. An FPGA is a type of integrated circuit, which is programmed after being manufactured. FPGAs have some advantages over other electronic technologies, such as analog circuits, microprocessors, and Programmable Logic Controllers (PLCs), for nuclear instrumentation and control, and safety system applications. However, safety-related issues for FPGA-based systems remain to be verified. Owing to this, modeling FPGA-based systems for safety assessment has now become an important point of research. One potential methodology is the dynamic flowgraph methodology (DFM). It has been used for modeling software/hardware interactions in modern control systems. In this paper, FPGA logic was analyzed using DFM. Four aspects of FPGAs are investigated: the "IEEE 1164 standard," registers (D flip-flops), configurable logic blocks, and an FPGA-based signal compensator. The ModelSim simulations confirmed that DFM was able to accurately model those four FPGA properties, proving that DFM has the potential to be used in the modeling of FPGA-based systems. Furthermore, advantages of DFM over traditional reliability analysis methods and FPGA simulators are presented, along with a discussion of potential issues with using DFM for FPGA-based system modeling.

• 한국태양에너지학회 논문집
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• 제40권4호
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• pp.23-33
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• 2020

The loss in photovoltaic power due to hailstorms has been highlighted as a major issue in the sustained growth of the PV power plant industry. This study investigates the safety of a solar module by conducting a numerical analysis of a hail test according to the IEC 61215 standard. Our study aims to elucidate the detailed behavior between the ice and solar modules and the micro-cracks forming on solar modules during hailstorms. To analyze the impact of hail, we used the ANSYS AUTODYN software to evaluate the impact characteristics on a solar module with different front glass thicknesses. The simulations show that a solar module with a glass thickness of 4.0 mm results in excellent durability against hail. The results indicate the feasibility of using simulations to analyze and predict micro-cracks on solar modules tailored to various conditions, which can be used to develop new solar modules.

• 한국전자통신학회논문지
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• 제9권6호
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• pp.681-687
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• 2014

원자력 산업계는 최근 원전 계측제어계통 설비의 단종과 같은 예상치 못한 환경에 직면해오고 있으며, 이러한 문제를 근본적으로 해결하고자 노력하고 있다. IAEA, IEC, 등의 연구결과에 따르면, FPGA는 단종이 예상되는 제어계통에의 대체수단으로 주목받고 있다. FPGA가 원자력 플랜트의 PLC(Programmable Logic Controller)를 대체하기 위해서는 높은 건정성과 신뢰성을 가져야 한다. 따라서, FPGA 기반 제어기의 건전성과 신뢰성을 향상시키기 위하여 HDL 개발수명주기를 적용하여 개발하였다. 또한, 원전 계측제어계통에 적용하기 위하여 번인시험과 환경시험의 기기검증이 수행되었다. 시험수행결과, 352시간의 번인시험과 92시간의 환경시험 중에 정상적인 기능 및 성능을 수행함을 확인할 수 있었다.

• Structural Engineering and Mechanics
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• 제76권3호
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• pp.367-378
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• 2020

This paper presents a new design concept for ocean nuclear power plants (ONPPs) using a tension leg platform (TLP). The system-integrated modular advanced reactor, which is one of the successful small modular reactors, is mounted for demonstration. The authors define the design requirements and parameters, modularize and rearrange the nuclear and other facilities, and propose a new total general arrangement. The most fundamental level of design results for the platform and tendon system are provided, and the construction procedure and safety features are discussed. The integrated passive safety system developed for the gravity based structure-type ONPP is also available in the TLP-type ONPP with minor modifications. The safety system fully utilizes the benefits of the ocean environment, and enhances the safety features of the proposed concept. For the verification of the design concept, hydrodynamic analyses are performed using the commercial software ANSYS AQWA with the Pierson-Moskowitz and JONSWAP wave spectra that represent various ocean environments and the results are discussed.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2004년도 추계학술대회논문집
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• pp.755-762
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• 2004

In our country, when the replacement for individual components of equipment in nuclear power plants is required, establishment of individual criteria i.e. Required Response Spectra(RRS) of seismic test/analysis for the component is very difficult because of the absence of Test Response Spectra(TRS) for the individual component to be replaced, from the existing qualification documents. In this case, it is required to perform the structural analysis for the nuclear equipment including the components to be replaced. After the structural analysis, Analysis Response Spectra(ARS) at the point of the component shall be generated and used for seismic test of the component. However, as of today, no standard program authorized for the response spectra generation by using the structural analysis exists in korea. Because of above reason, the STAR-Egs computer program was developed by using the method which calculates directly the expected response spectrum(frequency vs. acceleration type) of the selected points in the nuclear equipment with input spectrum(Required Response Spectra, RRS), based on the dynamic characteristics of the Finite Element(FE) model that is equivalent to the nuclear equipment. The STAR-Egs controls ANSYS/I-DEAS commercial software and automatically extract modal parameters of the FE model. The STAR-Egs calculates response spectrum using the established algorithm based on the extracted modal parameters, too. Reliance on the calculation result of the STAR-Egs was verified through comparison output with the result of MATLAB commercial software based on the identical algorithm. Moreover, actual seismic testing was performed as per IEEE344-1987 for the purpose of program verification by comparison of the FE analysis results.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2009년도 춘계학술대회
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• pp.849-853
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• 2009

발전기는 차량용에서부터 항공, 선박용등 이동 장치에서 사용될 뿐만 아니라, 화력, 수력, 원자력 발전소 등 기간 산업에서도 사용되고 있다. 이러한 교류 발전기는 차량이나 선박, 항공기 등에서 전기를 생산하는 아주 중요한 역할을 한다. 특히, 선박에서는 항해 중 발생할 수 있는 발전기 고장에 대비하여 비상용 발전 시스템을 장착하고 있다. 따라서 발전기 시스템을 항상 모니터링하여 발전기 이상 발생 시 비상 발전기를 가동할 수 있어야 한다. 본 연구는 비상용 디젤 엔진 발전기를 위한 제어기 및 각종 소프트웨어 설계에 관한 연구이다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1997년도 하계학술대회 논문집 D
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• pp.948-950
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• 1997

This paper presents a basic interposing logic program to control nuclear power plant. In this paper we select a target control loop among the whole interposing modules, develop logic algorithm and functional software to compose target control loop. After that we carry out V&V(Verification and Validation) into the developed logic program to improve quality and reliability.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1998년도 하계학술대회 논문집 C
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• pp.1241-1243
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• 1998

This paper presents a basic interposing module system to control nuclear power plant. In this paper, the system consists of master and loop controller. Also that we developed communication module and control logic software.

• 산업공학
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• 제23권1호
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• pp.68-77
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• 2010

Digital reactor protection system which consists of many identical modules, is fault- tolerant to provide high safety. The modules themselves including DSP(digital signal processing) card are also fault-tolerant in nature. This paper assesses the safety for being-designed digital reactor protection system of 2-out-of-4 G structure with lockout. Some interesting design alternatives are compared. Fault tree analysis for assessing system safety is performed by Relex software. The selected reactor protection system fully satisfies EPRIURD stipulation of mean failure time of 50 years.