• 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.

• International Journal of Internet, Broadcasting and Communication
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• 제15권2호
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• pp.218-226
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• 2023

In Korea, we still use function point based cost estimations for software size and cost of a project. The current problem is that we make difficultly calculating function points with requirements and also have less accurate. That is, it is difficult for non-experts to analyze requirements and calculate function point values with them, and even experts often derive different function points. In addition, all stakeholders strongly make the validity and accuracy of the function point values of the project before /after the development is completed. There are methods for performing function point analysis using source code [1][2][3][4] and some researchers [5][6][7] attempt empirical verification of function points about the estimated cost. There is no research on automatic cost validation with source code after the final development is completed. In this paper, we propose automatically how to calculate Function Points based on natural language requirements before development and prove FP calculation based on the final source code after development. We expect validation by comparing the function scores calculated by forward engineering and reverse engineering methods.

• 정보과학회 컴퓨팅의 실제 논문지
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• 제23권6호
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• pp.335-342
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• 2017

원자력발전소 안전-필수 소프트웨어를 개발하고 검증 및 확인을 수행하여 규제기관으로부터 인허가를 받기 위하여 단순하게 문서를 읽고 검토해서는 개발, 구현 및 검증활동에 대한 신뢰성과 안전성 확보에 대하여 정확하게 판단하기가 쉽지 않다. 따라서 이러한 활동, 특히 안전보증 활동이 소프트웨어 결함이 허용가능한 수준인지 판단하기 위한 체계적인 평가기술이 필요하다. 본 연구에서는 원전 디지털 원자로보호계통의 비교논리 프로세서와 동시논리 프로세서를 대상으로 제작자가 수행한 개발 및 검증 결과물의 수준과 깊이를 평가하기 위해 안전진술(Safety case) 방법론을 적용하고 그 결과를 분석한다. 안전진술 방법론 적용으로 기존의 안전입증 방법을 효과적으로 보완할 수 있음을 확인하였다.

• 한국시뮬레이션학회논문지
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• 제27권1호
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• pp.25-32
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• 2018

본 논문은 모델 기반 내장형 소프트웨어의 자동 생성 코드에 대한 효율적인 신뢰성 시험 절차와 구체화된 동적 시험 방안에 대해서 제시하고 있다. 모델 정적/동적 시험 각각을 코드 정적/동적 시험 전에 수행함으로서 코드 신뢰성 시험 수행의 이점이 있음을 기술하였다. 또한, 모델과 코드의 신뢰성 시험 상관관계를 모델의 경우 Model Advisor와 Verification and Validation tool, 코드의 경우 Polyspace와 LDRA를 이용하여 살펴보고 제시한 절차대로 수행한 신뢰성 시험의 결과를 보여주고 있다.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.91-98
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• 2009

The "3+3 Process" for safety critical software for nuclear power plants' I&C (Instrumentation and Control system) has been developed in this work. The main idea of the "3+3 Process" is both to simplify the software development and safety analysis in three steps to fulfill the requirements of a software safety plan [1]. The "3-Step" software development process consists of formal modeling and simulation, automated code generation and coverage analysis between the model and the generated source codes. The "3-Step" safety analysis consists of HAZOP (hazard and operability analysis), FTA (fault tree analysis), and DV (design validation). Put together, these steps are called the "3+3 Process". This scheme of development and safety analysis minimizes the V&V work while increasing the safety and reliability of the software product. For assessment of this process, validation has been done through prototyping of the SDS (safety shut-down system) #1 for PHWR (Pressurized Heavy Water Reactor).

• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2001년도 춘계학술대회
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• pp.77-81
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• 2001

Burn-in is a test procedure to find and eliminate the inherent initial failure of a product during or at the final stage of production process. Software testing is the validation and verification process which is used to cut off the faults from a software. The two have the common function and objective of "debugging". This article summarizes some significant models on the optimal hardware and software burn-in time, and provides the relevant paper lists. The need for the development of the unified burn-in policy of a hardware-software system is addressed.addressed.

• 산업경영시스템학회지
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• 제19권38호
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• pp.61-68
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• 1996

Quality Assurance Principles must be effectively implemented in developments and in use of safety critical software in nuclear industry. Brief definitions related to computer software and quality assurance were defined and several methods for evaluating software quality were proposed herewith. Independent verification and validation was suggested to assure the quality of safety critical software.

• 한국우주과학회:학술대회논문집(한국우주과학회보)
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• 한국우주과학회 2006년도 한국우주과학회보 제15권2호
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• pp.155-155
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• 2006

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.115.1-115
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• 1999

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 D
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• pp.2489-2491
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• 2005

Currently, Programmable Logic Contorller(PLC) uses Real Time Operation System(RTOS) as basic OS. RTOS executes defined results as to defined time. General features of RTOS emphasize the priority in each task, high-speed process of external interrupt, task scheduling, synchronization in task, the limitation of memory capacity. For safety critical placement, PLC software needs Verification and Validation(V&V). For example, nuclear power plant. In this paper, PLC RTOS is verified by formal methods. Particularly, formal method V&V uses verification tool called 'STATEMATE', and shows the results.