• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2001년도 춘계 학술대회 논문집
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• pp.153-156
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• 2001

We have developed CNS(Compact Nuclear Simulator) which can be used for the fundamental training of the nuclear power plant operators. The application software for CNS consists of simulation engine(analyzer code), instructor station software, and man-machine interface software. Each application software is regarded as one black box and the communication of black boxes is performed by the predefined shared memory variables. In this paper, we discuss our experience for CNS development.

• 시스템엔지니어링학술지
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• 제14권2호
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• pp.49-57
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• 2018

The main objective of this paper is come up with methodology approach for FPGA-based system in verification and validation lifecycle regarding software reliability using system engineering approach. The steps of both reverse engineering and re-engineering are carried out to implement an FPGA-based of safety critical system in Nuclear Power Plant. The reverse engineering methodology is applied to elicit the requirements of the system as well as gain understanding of the current life cycle and V&V activities of FPGA based-system. The re-engineering method is carried out to get a new methodology approach of software reliability, particularly Software Reliability Growth Model. For measure the software reliability of a given FPGA-based system, the following steps are executed as; requirements definition and measurement, evaluation of candidate reliability model, and the validation of the selected system. As conclusion, a new methodology approach for software reliability measurement using software reliability growth model is developed.

• Nuclear Engineering and Technology
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• 제50권4호
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• pp.570-581
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• 2018

Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrumentation and control systems. To guarantee NPP safety, the reliability of the software used in safetycritical instrumentation and control systems must be quantified and verified with proper test cases and test environment. In this study, a software testing method using a simulation-based software test bed is proposed. The test bed is developed by emulating the microprocessor architecture of the programmable logic controller used in NPP safety-critical applications and capturing its behavior at each machine instruction. The effectiveness of the proposed method is demonstrated via a case study. To represent the possible states of software input and the internal variables that contribute to generating a dedicated safety signal, the software test cases are developed in consideration of the digital characteristics of the target system and the plant dynamics. The method provides a practical way to conduct exhaustive software testing, which can prove the software to be error free and minimize the uncertainty in software reliability quantification. Compared with existing testing methods, it can effectively reduce the software testing effort by emulating the programmable logic controller behavior at the machine level.

• 한국시뮬레이션학회논문지
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• 제24권4호
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• pp.1-9
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• 2015

원자력 분야에서 안전관련(safety-related) 소프트웨어의 활용이 점차 확대됨에 따라서, 그에 상응하는 소프트웨어 안전과 신뢰도 향상을 위한 방안 연구가 지난 10여년 전부터 활발히 진행되고 있다. 원전 계측제어시스템(MMIS)은 원자력 발전소의 두뇌와 신경망에 해당하는 기능을 수행하고 있고 첨단 디지털 장비들로 구성된다. 따라서 원전 계측제어시스템의 소프트웨어 오류는 원자력 발전소 운전에 지장을 초래할 수 있고, 오동작으로 인한 발전소 정지로 경제적 손실을 초래할 수 있다. 소프트웨어 확인 및 검증(verification and validation, V&V)은 소프트웨어 품질을 향상시킬 수 있는 소프트웨어 공학의 분야로 알려져 있고, 원자력 산업계에서는 소프트웨어 생명주기에 따른 철저한 V&V 활동을 이행하고 준수할 것을 법규로 규정하고 있다. V&V 활동은 소프트웨어 전 생명주기에 따라 분석과 시험 활동들의 조합으로 다른 품질관련 공학 업무를 보완하는 역할을 한다. 본 논문에서는 명세 평가, 요건 추적, 소스코드 리뷰, 및 소프트웨어 시험을 통한 최적화된 안전관련 소프트웨어 V&V 방법론에 기반한 소프트웨어 품질 향상 방안과 단계별로 적합한 도구를 활용하여 효율성을 확보할 수 있는 방안을 제시하고자 한다. 제안된 방법론은 실제 신한울 1,2호기 원자력발전소 MMIS 시스템에 적용되어 입증되었다.

• 한국산학기술학회논문지
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• 제8권2호
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• pp.226-231
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• 2007

본 논문은 핵발전소의 초음파 비파괴 평가를 수행하기 위하여 구현된 초음파 신호 분석 소프트웨어에 관한 것이다. 구현된 소프트웨어는 1차원 초음파 신호뿐만 아니라 이를 가공하여 B, C 및 D 스캔 영상으로의 확장이 가능하고 각 스캔 영상으로부터 의미 있는 파라메터를 측정할 수 있는 기능을 갖추고 있다. 구현된 소프트웨어는 이미 알고 있는 시편의 결함에 적용하여 프로그램의 정확성을 검증하였다.

• Nuclear Engineering and Technology
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• 제29권6호
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• pp.433-443
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• 1997

In this work, an analytic approach to the dependability of software in the operational phase is suggested with special attention to the hardware fault effects on the software behavior : The hardware faults considered are memory faults and the dependability measure in question is the reliability. The model is based on the simple reliability theory and the graph theory which represents the software with graph composed of nodes and arcs. Through proper transformation, the graph can be reduced to a simple two-node graph and the software reliability is derived from this graph. Using this model, we predict the reliability of an application software in the digital system (ILS) in the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. We also found that the effects of the hardware faults on the software failure should be considered for predicting the software dependability accurately in operation phase, especially for the software which is executed frequently. This modeling method is particularly attractive for the medium size programs such as the microprocessor-based nuclear safety logic program.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.1079-1080
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• 2005

• 방사성폐기물학회지
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• 제19권1호
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• pp.61-74
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• 2021

A paradigm shift in the government's energy policy was reflected in its declaration of early closure of old nuclear plants as well as cancellation of plans for the construction of new plants. To this end, unit 1 of Kori Nuclear Power Plant was permanently shut down and is set for decommission. Based on these changes, the off-site transport of spent fuels from nuclear power plants has become a critical issue. The purpose of this study is to develop an optimized method for transportation of spent fuels from Kori Nuclear Power Plant's units 1, 2, 3, and 4 to an assumed interim storage facility by simulating the scenarios using the Flexsim software, which is widely used in logistics and manufacturing applications. The results of the simulation suggest that the optimized transport methods may contribute to the development of delivery schedule of spent fuels in the near future. Furthermore, these methods can be applied to decommissioning plan of nuclear power plants.

• 한국산학기술학회:학술대회논문집
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• 한국산학기술학회 2006년도 춘계학술발표논문집
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• pp.217-222
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• 2006

This paper describes a development of ultrasonic examination analysis software to analyze steam generator of nuclear power plant. The developed software includes classical analysis method such as A, B, C and D-scan images. This software provides the information of shape, depth, size and position of flaws. To do such, we obtain raw data from specimens and/or real pipeline of power plants and, modify the obtained ultrasonic 1-dimensional data according to prepared software design schedule. The developed analysis software is applied to specimens containing various flaws with known dimensions. The results of applications showed that the developed software provided accurate and enhanced images of flaws on various specimens.

• 정보처리학회 논문지
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• 제13권5호
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• pp.227-235
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• 2024

원자력발전소에서 디지털 계측제어 시스템 비중이 높아지면서 원자력발전소에 대한 확률론적 안정성 평가 시 소프트웨어에 대한 신뢰도 평가가 중요해졌다. 원전 소프트웨어 신뢰도 추정을 위한 방법들이 몇 가지 제안 되었지만 해당 방법의 효과적 적용을 지원하는 도구 지원이 미비하였다. 본 연구에서는 소프트웨어 개발 품질 및 검증 품질과 같은 정성적 정보와 통계적 시험 결과와 같은 정량적 정보를 활용하여 원전 소프트웨어 신뢰도를 정량적으로 측정할 수 있는 자동화 도구를 설계하였고 구현하였다. 개발된 도구를 산업용 원자로 보호 시스템 사례에 적용한 결과, 개발된 도구가 원전 소프트웨어의 신뢰성 평가를 효과적으로 지원할 수 있음을 확인하였다.