• 제목/요약/키워드: Verification & Validation

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Verification of Safety Critical Software

  • Son, Ki-Chang;Chun, Chong-Son;Lee, Byeong-Joo;Lee, Soon-Sung;Lee, Byung-Chai
    • Nuclear Engineering and Technology
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    • 제28권6호
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    • pp.594-601
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    • 1996
  • To assure quality of safety critical software, software should be developed in accordance with software development procedures and rigorous software verification and validation should be performed. Software verification is the formal act of reviewing, testing or checking, and documenting whether software components comply with the specified requirements for a particular stage of the development phase [1]. New software verification methodology was developed and was applied to the Shutdown System No. 1 and 2(SDS1,2) for Wolsong 2, 3 and 4 nuclear power plants by Korea Atomic Energy Research Institute(KAERI) and Atomic Energy of Canada Limited(AECL) in order to satisfy new regulation requirements of Atomic Energy Control Board(AECB). Software verification methodology applied to SDS1 for Wolsong 2, 3 and 4 project will be described in this paper. Some errors were found by this methodology during the software development for SDS1 and were corrected by software designer. Output from Wolsong 2, 3 and 4 project have demonstrated that the use of this methodology results in a high quality, cost-effective product.

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Testbench Implementation for FPGA based Nuclear Safety Class System using OVM

  • Heo, Hyung-Suk;Oh, Seungrohk;Kim, Kyuchull
    • 전기전자학회논문지
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    • 제18권4호
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    • pp.566-571
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    • 2014
  • A safety class field programmable gate array based system in nuclear power plant has been developed to improve the diversity. Testbench is necessary to satisfy the technical reference, IEC-62566, for verification and validation of register transfer level code. We use the open verification methodology(OVM) developed by standard body. We show that our testbench can use random input for test. And also we show that reusability of block level testbench for the integration level testbench, which is very efficient for large scale system like nuclear reactor protection system.

POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor

  • Tak, Nam-il;Lee, Jeong-Hun;Lee, Sung Nam;Jo, Chang Keun
    • Nuclear Engineering and Technology
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    • 제52권9호
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    • pp.1974-1982
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    • 2020
  • Numerical prediction of fission product plateout and circulating coolant activities under normal operating conditions is crucial in the design of a high temperature gas-cooled reactor (HTGR). The results are used for the maintenance and repair of the components as well as the safety analysis regarding early source terms under loss of coolant accident scenarios. In this work, a new computer code named POSCA (Plate-Out Surface and Circulating Activities) was developed based on a one-dimensional model to evaluate fission product plateout and circulating coolant activities within the primary circuit of a HTGR. The verification and validation of study for the POSCA code was done using available analytical results and two in-pile experiments (i.e., OGL-1 and VAMPYR-1). The results of the POSCA calculations show that POSCA is able to simulate plateout and circulating coolant activities in a HTGR with fast computation and reasonable accuracy.

항공무기체계 LVC 시뮬레이션을 위한 통합연동시스템 V&V (V&V of Integrated Interoperability System for LVC Simulation on Aircraft Weapon System)

  • 오지현;장영찬;김천영;지철규;홍영석
    • 한국군사과학기술학회지
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    • 제18권3호
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    • pp.326-334
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    • 2015
  • This paper describes the verification and the validation about the development of the integrated interoperability system for live, virtual, and constructive simulations on the aircraft weapon system. The proposed integrated interoperability system provides the framework and application softwares for implementing a synthetic environment emulating real-world environment among distributed simulation models, which are a mission model and an air combat model of a constructive level, an tactical simulator of a virtual level, and simulated ACMI of a live level. In this paper, we verify requested functions through an developmental test and evaluation, and validate operability and usability through conducing integrated LVC scenarios on the integrated interoperability system.

하드디스크 드라이브의 충격해석 및 실험적 검증 (Shock Simulation and Experimental Verification of HDD)

  • 김진곤;이재곤
    • 한국산학기술학회논문지
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    • 제10권10호
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    • pp.2583-2588
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    • 2009
  • 본 논문에서는 반정현파 형태의 충격을 받는 HDD에 대한 충격해석을 수행하고, 그 타당성을 실험적으로 검증하였다. 일반적으로 센서를 이용한 제품의 충격실험을 통해서는 제한적인 정보만을 얻을 수 있지만, 컴퓨터를 이용한 해석기술은 제품의 파손현상을 규명하는데 필요한 보다 광범위하고 상세한 정보를 제공할 수 있는 장점을 가진다. 하지만, 이러한 해석결과는 여러 요인들에 따라 매우 민감하기 때문에 그 타당성을 검증하는 것이 중요하다. 따라서 본 연구에서는 200G/1ms의 전자기 충격실험과 300G/2ms의 낙하충격실험을 통하여 HDD의 조립단계별로 LS-DYNA를 이용한 유한요소해석의 신뢰성을 검증하였다.

지속가능생산시스템의 특성 분석 및 V&V 전략 (Characteristics Analysis of Sustainable Manufacturing System and V&V Strategy)

  • 윤수철;서석환
    • 시스템엔지니어링학술지
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    • 제10권2호
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    • pp.51-58
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    • 2014
  • Manufacturing industry is one of the core sectors providing national competitiveness and economical impact Today's manufacturing industry is required to fulfill so called Sustainable Factory paradigm from the perspectives of environmental and social development. To cope with the requirements, researches for achieving sustainability in manufacturing system are actively carried out in the world from various perspectives. In this paper, we analyzed systemic characteristics of sustainable manufacturing system, and developed verification & validation strategy based on traceability between system requirement and functionality. The developed methods were applied to a European Project called the Foundation for the Sustainable Factory of the Future (FoFdation). Specifically, we analyzed and verified the deliverables of FoFdation by deriving systems architecture in terms of Component, Function, and Items. The results indicated that the FoFdation is pretty much compliant with the concept of Ubiquitous Factory, and can be used as an International Reference Model for the Smart Factoy, a world wide hot topic under the paradigm of IOT (Internet-Of-Things), if information processing part is supplemented.

안전에 중요한 소프트웨어 개발을 위한 확인 및 검증 (Verification and Validation to develop Safety-critical Software)

  • 이종복;서상문;금종용
    • 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.

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BASINS/HSPF 모형을 이용한 수질오염총량관리 유달율 산정방법 연구 (Estimation of Delivery Ratio Based on BASINS/HSPF Model for Total Maximum Daily Load)

  • 박주현;황하선;류덕희;권오상
    • 한국물환경학회지
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    • 제28권6호
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    • pp.833-842
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    • 2012
  • In this study Window interface to Hydrological Simulation Program-FORTRAN (HSPF) developed by the United States Environmental Protection Agency (EPA) was applied to the upstream of Namgang watershed to estimate its applicability for estimating Delivery Ratio (DR) of water pollutants for Total Maximum Daily Load (TMDL). BASINS/HSPF which is selected in this study, is found to be appropriate for simulation of daily flow and water quality in target basins. DR was estimated utilizing discharge loads of unobserved sub-basin and delivery load of unobserved locations obtained not by actual evaluation but by simulation through validation and verification. Annual average DR of BOD, TN and TP were 0.97 ~ 1.50, 2.23 ~ 3.21, and 0.81 ~ 1.09 respectively. Net DR of dependent basins excluding influence of upstream basin was 1.50 ~ 1.70, 0.55 ~ 0.69, and 0.24 ~ 0.31, all of which are lower than those of independent basins area. Utilizing the model selected by this research, DR and Net DR of unobserved basins will be estimated, which will help determine priorities in management of basin areas.

모델 기반 내장형 소프트웨어의 효율적 신뢰성 시험 기법 (An Efficient Software Reliability Testing Method for the Model based Embedded Software)

  • 박장성;조성봉;박현룡;김도완;김성균
    • 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.

A Systems Engineering Approach to Multi-Physics Load Follow Simulation of the Korean APR1400 Nuclear Power Plant

  • Mahmoud, Abd El Rahman;Diab, Aya
    • 시스템엔지니어링학술지
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    • 제16권2호
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    • pp.1-15
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    • 2020
  • Nuclear power plants in South Korea are operated to cover the baseload demand. Hence they are operated at 100% rated power and do not deploy power tracking control except for startup, shutdown, or during transients. However, as the contribution of renewable energy in the energy mix increases, load follow operation may be needed to cover the imbalance between consumption and production due to the intermittent nature of electricity produced from the conversion of wind or solar energy. Load follow operation may be quite challenging since the operators need to control the axial power distribution and core reactivity while simultaneously conducting the power maneuvering. In this paper, a systems engineering approach for multi-physics load follow simulation of APR1400 is performed. RELAP5/SCDAPSIM/MOD3.4/3DKIN multi-physics package is selected to simulate the Korean Advanced Power Reactor, APR1400, under load follow operation to reflect the impact of feedback signals on the system safety parameters. Furthermore, the systems engineering approach is adopted to identify the requirements, functions, and physical architecture to provide a set of verification and validation activities that guide this project development by linking each requirement to a validation or verification test with predefined success criteria.