• International Journal of Safety
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• 제3권1호
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• pp.38-46
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• 2004

This paper introduces the software life-cycle V&V (verification and validation) tasks for the KNICS (Korea nuclear instrumentation and control system) project. The objectives of the V&V tasks are mainly to develop a programmable logic controller (PLC) for safety critical instrumentation and control (I&C) systems, and then to apply the PLC to developing the prototype of an engineered safety features-component control system (ESF-CCS) in nuclear power plants. As preparative works for the software V&V, various kinds of software plans and V&V task procedures have been developed according to the software life-cycle management. A number of software V&V tools have been adopted or developed to efficiently support the V&V tasks. The V&V techniques employed in this work include a checklist-based review and inspection, a requirement traceability analysis, formal verification, and life-cycle based software testing.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.185-187
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• 2005

The reactor protection system is the most important function for the safe operation of nuclear powerplants (NPPs) in that such system protects a nuclear reactor tore whose damage can cause an enormous disaster to the nuclear facility and the public. A digital reactor protection system (DRPS) is being developed in KAERI for use in the newly-constructed NPPs and also for replacing the existing analog-type reactor Protection systems. In this paper, an software verification and validation (V&V) activities for DRPS, which are independent of the DRPS development processes, are described according to the software development life cycle. The main activities of DRPS V&V processes are the software planning documentations, the verification of software requirements specification (SRS) and software design specification (SDS), the verification of codes, the tests of the integrated software and system. Moreover, the software safety analysis and the software configuration management are involved in the DRPS V&V processes. All of the V&V activities are described, in detail, in this paper.

• 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.

• 한국품질경영학회:학술대회논문집
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• 한국품질경영학회 2004년도 품질경영모델을 통한 가치 창출
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• pp.114-119
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• 2004

Software verification and validation(V&V) is a means to develop high-quality software and assure safety and reliability for software. Also, we can achieve the desired software quality through systematic V&V activities. The software to be applied safety critical system like nuclear power plants is required to setup the V&V methodology that comply with licensing requirements for nuclear power plants and should be performed V&V activities according to it. In this paper, we classified safety-critical, safety-related and non-safety for software according to safety function to be peformed and define V&V activities to be applied software grade. Also, we defined V&V activities, procedures and documentation for each phase of software development life cycle and showed techniques and management to perform V&V. Finally, we propose the V&V framework to be applied software development of SMART(System-integrated Modular Advanced ReacTor) MMIS (Man-Machine Interface System) and to comply with domestic licensing requirements.

• 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.

• 시스템엔지니어링학술지
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• 제19권1호
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• pp.56-63
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• 2023

For the success of system development, it is necessary to systematically manage the requirements that are the basis of system development and its verification results. In order to follow the principles of SE(Systems Engineering)-based V&V(Verification&Validation) process, requirements can be managed by securing the requirements and their establishments, design compliances, and verification compliances according to the system development lifecycle. Especially, in a large-complex system research and development project, such as a space launch vehicle development project, many participants establish, verify, and validate numerous requirements together during the project. Therefore, logical and systematic requirements management, including guarantee of data integrity, change history, and traceability, is very important for multiple participants to utilize numerous requirements together without errors. This paper introduces the practical requirements and verification management for the requirements-based development process in the space launch vehicle development project.

• 한국항행학회논문지
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• 제21권2호
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• pp.155-162
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• 2017

최근 국내에서 항공 관련 안전필수시스템들이 개발되었지만 이들 완성품들은 규정된 요구사항들을 충족시키지 못하여 실용화 또는 상용화 되지 못하였다. 현대 항공 기술의 복잡도가 높아짐에 따라 기존의 검증 및 확인 기술로는 시스템에 잠재된 리스크를 식별하고 줄이는데 어려움이 많다. 이러한 단점들을 극복하기 위해 선진국에서는 독립적 검증 및 확인이라는 새로운 기법에 관심이 모아지고 있다. 이 독립적 검증 및 확인의 효과도에 관한 학술적 연구는 국내에는 전무하고, 국외에서 조차도 매우 희소하게 수행되고 있다. 따라서 본 논문에서는 항공선진기관에서 수행한 항공 안전필수시스템에 대한 독립적 검증 및 확인의 응용 연구들을 조사하여 사업에 미치는 여러 가지 효과들을 분석해 본 결과, IV&V는 조기 오류 검출율을 높이고, 내재된 리스크도 조기에 완화하며, 개발 수명주기 후반에 나타나는 재작업 확률을 줄여서 개발 일정 및 비용의 증가를 획기적으로 막아주는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제51권2호
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• pp.356-368
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• 2019

This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for a pressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion code RAST-K 2.0 have been developed by a computational reactor physics and experiment laboratory (CORE) of Ulsan National Institute of Science and Technology (UNIST) for an accurate two-step PWR analysis. The calculation modules of each code were already verified against various benchmark problems, whereas this paper focuses on the V&V of linked code system. Three PWR type reactor cores, OPR-1000, three-loop Westinghouse reactor core, and APR-1400, are selected as V&V target plants. This code system, for verification, is compared against the conventional code systems used for the calculations in nuclear design reports (NDRs) and validated against measured plant data. Compared parameters are as follows: critical boron concentration (CBC), axial shape index (ASI), assembly-wise power distribution, burnup distribution and peaking factors. STREAM/RAST-K 2.0 shows the RMS error of critical boron concentration within 20 ppm, and the RMS error of assembly power within 1.34% for all the cycles of all reactors.

• 한국산업융합학회 논문집
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• 제22권6호
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• pp.689-702
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• 2019

This paper deals with the verification of the functions about mining robot, which is the system for developing deep seabed resources by applying V&V(verification and validation). In order to overcome water pressure of 500 bar and to travel on soft ground, and to operate in deep sea environment with bad conditions, it is necessary to develop a robot that can satisfy various deepsea conditions. A mining robot has been developed based on simulation based design and Multidisciplinary design optimization. In order to verify the developed robot, lab test and real sea test should be performed for various marine environment conditions. There are too many requirements to consider, such as space, time, cost, personnel, and environment to do performance test. So it is costly and time consuming for developing robot. In order to solve this problems, V&V technique was applied to mining robot. The stages of mining robot design, fabrication and commission were verified.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3494-3515
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• 2022

This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo-vodyanoi energetichesky reactor) analysis. A VVER analytic solver has been implemented in an in-house nodal diffusion code, RAST-K. The new RAST-K version, RAST-V, uses the triangle-based polynomial expansion nodal method. The RAST-K code provides stand-alone and two-step computation modes for steady-state and transient calculations. An in-house lattice code (STREAM) with updated features for VVER analysis is also utilized in the two-step method for cross-section generation. To assess the calculation capability of the formulated analysis module, various verification and validation studies have been performed with Rostov-II, and X2 multicycles, Novovoronezh-4, and the Atomic Energy Research benchmarks. In comparing the multicycle operation, rod worth, and integrated temperature coefficients, RAST-V is found to agree with measurements with high accuracy which RMS differences of each cycle are within ±47 ppm in multicycle operations, and ±81 pcm of the rod worth of the X2 reactor. Transient calculations were also performed considering two different rod ejection scenarios. The accuracy of RAST-V was observed to be comparable to that of conventional nodal diffusion codes (DYN3D, BIPR8, and PARCS).