• 제목/요약/키워드: integrated verification facility

검색결과 16건 처리시간 0.025초

위성비행소프트웨어 통합검증환경의 설계 및 구축 (Design and Implementation of Integrated Verification Facility for Satellite Flight Software)

  • 신현규;이재승;최종욱;천이진
    • 항공우주기술
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    • 제11권1호
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    • pp.49-56
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    • 2012
  • 위성의 기본적인 상태를 모니터링하며 자세 제어 및 위성 고유의 임무를 수행하는 위성비행소프트웨어는 운용 환경 및 그 특수성으로 인하여 매우 높은 수준의 신뢰성이 요구된다. 이를 위하여 개발 과정에서 다양한 활동이 이루어지게 된다. 실제 하드웨어 또는 하드웨어를 모사하는 시뮬레이터를 통해 위성비행소프트웨어를 동작시키고 지상 명령의 전송, Telemetry의 수신을 통한 검증의 경우, 매우 다양한 지원환경이 요구된다. 위성비행소프트웨어팀에서는 이러한 검증 활동을 보다 효과적으로 수행하고 이를 통해 소프트웨어의 신뢰성을 향상하고, 다양한 위성 개발에 공통으로 사용될 수 있는 위성 비행 소프트웨어 통합 검증 시스템을 구축하고 있다. 본 논문에서는 위성비행소프트웨어의 효과적인 검증을 위한 통합 검증 시스템의 설계 및 구축 방안에 대하여 소개한다.

디지털 원자로 보호계통의 소프트웨어 확인 및 검증 (Software Verification & Validation for Digital Reactor Protection System)

  • 박기용;권기춘
    • 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.

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일체형원자로의 신개념 안전계통 실증을 위한 실험적 연구 (Experimental Study on Design Verification of New Concept for Integral Reactor Safety System)

  • 정문기;최기용;박현식;조석;박춘경;이성재;송철화
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 춘계학술대회
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    • pp.2053-2058
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    • 2004
  • The pressurized light water cooled, medium power (330 MWt) SMART (System-integrated Modular Advanced ReacTor) has been under development at KAERI for a dual purpose : seawater desalination and electricity generation. The SMART design verification phase was followed to conduct various separate effects tests and comprehensive integral effect tests. The high temperature / high pressure thermal-hydraulic test facility, VISTA(Experimental Verification by Integral Simulation of Transient and Accidents) has been constructed to simulate the SMART-P (the one fifth scaled pilot plant) by KAERI. Experimental tests have been performed to investigate the thermal-hydraulic dynamic characteristics of the primary and the secondary systems. Heat transfer characteristics and natural circulation performance of the PRHRS (Passive Residual Heat Removal System) of SMART-P were also investigated using the VISTA facility. The coolant flows steadily in the natural circulation loop which is composed of the steam generator (SG) primary side, the secondary system, and the PRHRS. The heat transfers through the PRHRS heat exchanger and ECT are sufficient enough to enable the natural circulation of the coolant.

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방사성폐기물 표층처분시설 통합 모니터링 시스템 개발 (Development of an Integrated Monitoring System for the Low and Intermediate Level Radioactive Waste Near-surface Disposal Facility)

  • 최세호;강현구;권미진;하재철
    • 방사선산업학회지
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    • 제17권4호
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    • pp.359-367
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    • 2023
  • In this study, the function and purpose of the disposal cover, which is an engineering barrier installed to isolate the disposal vault of the near-surface disposal facility for radioactive waste from natural/man-made intrusion, and the design details of the demonstration facility for performance verification were described. The Demonstration facility was designed in a partially divided form to secure the efficiency of measurement while being the same as the actual size of the surface disposal facility to be built in the Intermediate & low-level radioactive waste disposal site of the Korea Radioactive Waste Agency (KORAD). The instruments used for measurement consist of a multi-point thermometer, FDR (Frequency Domain Reflectometry) sensor, inclinometer, acoustic sensor, flow meter, and meteorological observer. It is used as input data for the monitoring system. The 3D monitoring system was composed of 5 layers using the e-government standard framework, and was developed based on 4 components: screen, control module, service module, and DBIO(DataBase Input Output) module, and connected them to system operation. The monitoring system can provide real-time information on physical changes in the demonstration facility through the collection, analysis, storage, and visualization processes.

Contribution of thermal-hydraulic validation tests to the standard design approval of SMART

  • Park, Hyun-Sik;Kwon, Tae-Soon;Moon, Sang-Ki;Cho, Seok;Euh, Dong-Jin;Yi, Sung-Jae
    • Nuclear Engineering and Technology
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    • 제49권7호
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    • pp.1537-1546
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    • 2017
  • Many thermal-hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop) has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium) safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test) facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant) performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test) facility to evaluate the safety injection performance and to validate the thermal-hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux) test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop) facility to construct a database from the $5{\times}5$ rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio) model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

철도시스템의 종합시험운행을 통한 철도안전 확보방안 (A Railway Safety Proposal with Full System Commissioning)

  • 김정주;이희성;문대섭
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2005년도 추계학술대회 논문집
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    • pp.522-527
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    • 2005
  • Rail network authority have to do the safety ensuring activities including the maintenance of railway facility, integrated performance verification between the facilities and related rolling stock and safety inspections, etc. When constructing the new lines or revising the conventional lines, full system commissioning should be done before the revenue service with railway operator. To develop the optimal full system commissioning model, the status of domestic and foreign railway facility and railway accidents are analysed and the problems of the safety management are derived. As one of countermeasures for the problems, the procedures and criteria for the full system commissioning are developed.

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Multi-body dynamics model for spent nuclear fuel transportation system under normal transport test conditions

  • Seongji Han;Gil-Eon Jeong;Hyeonbeen Lee;Woo-Seok Choi;Jin-Gyun Kim
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.4125-4133
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    • 2023
  • The transportation of spent nuclear fuel is an important process that involves road and sea transport from an interim storage facility to storage and final disposal sites. As spent nuclear fuel poses a significant risk, carefully evaluating its vibration and shock characteristics under normal transport conditions is essential. In this regard, full-scale multi-modal transport tests (MMTT) have been conducted domestically and internationally. In this paper, we discuss the process of developing a multi-body dynamics (MBD) model to analytically simulate conditions that cannot be considered in tests. The MBD model is based on the KORAD-21 transportation system was validated using the Korean MMTT results from 2020 to 2021. This paper summarizes the details of the development and verification of the MBD model for the KORAD-21 transportation system under normal transport test conditions. This approach can be applicable to various transportation scenarios and systems, and the results of this study will help to ensure that nuclear fuel transportation is conducted safely and effectively.

교육 시설물의 선제적 노후화 관리를 위한 유지관리 서비스 수준의 인지요인 도출 (Critical Factors Influencing on the Level of Service for Proactive Maintenance in Educational Facilities)

  • 신승우;이준성;손정욱
    • 한국건설관리학회논문집
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    • 제16권3호
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    • pp.24-35
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    • 2015
  • 향후 교육시설의 노후화 관리는 단편적인 개 수공사가 아닌 안전하고 쾌적한 교육환경을 목적으로 하는 시설물의 기능을 고려한 통합적인 서비스 관점에서 이루어져야 한다. 이를 위해 현행 유지관리에서 주류를 이루고 있는 편향된 성능기반 관점의 한계성을 인지하고 시설물이 제공해야 하는 유지관리 서비스의 기능과 속성을 반영한 유지관리 체계를 구축하여야 한다. 따라서 본 연구는 교육시설물에서 제공하는 시설물 서비스 기능의 적절한 평가를 위해 서비스 수준 인지에 영향을 미치는 유지관리 항목들을 도출하고, 이를 적절한 범주로 설정하여 향후 지속적이고 효율적인 유지관리 체계를 구축하기 위한 기초자료로 활용하고자 한다. 이를 위하여 주요 유지관리 범주별 영향요인을 측정하기 위한 설명변수가 제시되었고, 그 타당성을 확인하기 위하여 전문가들을 대상으로 수행된 설문에 대해서 적절한 통계적 검증을 수행하였다.

복합형 환승센터에서의 상황대응을 위한 통합정보시스템 구축에 관한 연구 (A Study on the Implementation of the Integrated Information System for Emergency Handling in Multi-modal Transfer Stations)

  • 김현태;한정훈;장봉섭;김황배
    • 대한공간정보학회지
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    • 제16권3호
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    • pp.87-94
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    • 2008
  • 이 연구에서는 복합형 환승센터의 돌발상황 대응을 위한 모니터링 대상의 선정과 돌발상황 모니터링, 검지, 확인, 전파, 처리, 종료까지의 진행 절차에서 관리되는 정보를 도출하고 데이터베이스로 통합관리 하도록 하여 상황진행 단계에 따라 상황처리 의사결정에 필요한 사전정보를 제공하도록 제시하였다. 시설물, 이용자, 교통류로 구성된 환승센터는 모니터링 정보의 한계성을 가지고 있다. 따라서 상황검지 및 상황대응 전략수립 방안에서는 상황대응 전문가의 경험 지식과 과거의 사례를 활용할 수 있는 전문가 시스템의 사례기반 추론을 활용하는 방안으로 접근하였다. 또한 돌발상황 발생 시 공간적 혼잡도 및 피해 최소화를 위해 환승센터에서 운영하고 있는 설비의 통제 방안을 제시하였으며, 대외기관의 서비스 지원 극대화를 위해 실시간으로 상황정보의 공유 서비스 체계가 유지되도록 하였다.

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시스템공학 접근법을 이용한 지능형 건물 자동화 시스템의 개념설계 (Conceptual Design of Intelligent Building Automation System Using Computer-Aided Systems Engineering Approach)

  • 유일상;박영원
    • 한국군사과학기술학회지
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    • 제3권2호
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    • pp.166-178
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    • 2000
  • As the 21st century signifies an information-oriented society, the computer integration takes place in all walks of human presence. Needs for computer and network-integrated automation present new challenges in military as well as commercial facility systems engineering. Since the first intelligent building appeared in USA in 1984, it gradually became an essential capability for the building industry requirement these days. Intelligent Building System(IBS) is evolving to be very complex because there are many subsystems such as telecommunication(TC), office automation(OA), building automation(BA), security, construction environments, etc. During the planing phase of IBS development, therefore, a disciplined systems engineering must be performed to analyze stake- holder's requirements to build an optimized system while minimizing trial-and-error expenses and risks. This paper presents a conceptual design of BAS applying systems engineering methods. The contribution of this study includes the development of IBS subsystem specification for building automation subsystem, which is a part of IBS, using the methodology of requirement analysis, functional analysis, synthesis, and verification. A computer-aided systems engineering s/w, RDD-100, was used to improve the system design efficiency and to promote the product design knowledge management for reuse in later design programs.

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