• 제목/요약/키워드: Verification of equipment

검색결과 508건 처리시간 0.031초

한국형발사체 추진기관시스템 시험설비(PSTC) 통합제어시스템 (Main Control System of Propulsion System Test Complex(PSTC) for KSLV-II)

  • 김동기;이정호;조기주;심주영
    • 한국추진공학회:학술대회논문집
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    • 한국추진공학회 2017년도 제48회 춘계학술대회논문집
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    • pp.1205-1211
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    • 2017
  • 한국형발사체 각 단 추진기관시스템의 성능 검증을 위해 나로우주센터에 추진기관시스템 시험설비(PSTC, Propulsion System Test Complex)가 구축되었다. 본 논문은 PSTC 지상설비와 발사체 운용 및 제어를 위해 개발된 통합제어시스템(MCS, Main Control System)의 설계, 개발 현황, 시운전 결과에 관한 내용이다. MCS는 시험대상체와 지상시스템의 인터페이스에 활용될 예정이며, 시험책임자에 의한 시험운용 및 시퀀스 처리를 수행하게 된다. 또한 시험책임자 모의시험운용에도 활용될 예정이다.

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APPLICATION OF FUZZY SET THEORY IN SAFEGUARDS

  • Fattah, A.;Nishiwaki, Y.
    • 한국지능시스템학회:학술대회논문집
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    • 한국퍼지및지능시스템학회 1993년도 Fifth International Fuzzy Systems Association World Congress 93
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    • pp.1051-1054
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    • 1993
  • The International Atomic Energy Agency's Statute in Article III.A.5 allows it“to establish and administer safeguards designed to ensure that special fissionable and other materials, services, equipment, facilities and information made available by the Agency or at its request or under its supervision or control are not used in such a way as to further any military purpose; and to apply safeguards, at the request of the parties, to any bilateral or multilateral arrangement, or at the request of a State, to any of that State's activities in the field of atomic energy”. Safeguards are essentially a technical means of verifying the fulfilment of political obligations undertaken by States and given a legal force in international agreements relating to the peaceful uses of nuclear energy. The main political objectives are: to assure the international community that States are complying with their non-proliferation and other peaceful undertakings; and to deter (a) the diversion of afeguarded nuclear materials to the production of nuclear explosives or for military purposes and (b) the misuse of safeguarded facilities with the aim of producing unsafeguarded nuclear material. It is clear that no international safeguards system can physically prevent diversion. The IAEA safeguards system is basically a verification measure designed to provide assurance in those cases in which diversion has not occurred. Verification is accomplished by two basic means: material accountancy and containment and surveillance measures. Nuclear material accountancy is the fundamental IAEA safeguards mechanism, while containment and surveillance serve as important complementary measures. Material accountancy refers to a collection of measurements and other determinations which enable the State and the Agency to maintain a current picture of the location and movement of nuclear material into and out of material balance areas, i. e. areas where all material entering or leaving is measurab e. A containment measure is one that is designed by taking advantage of structural characteristics, such as containers, tanks or pipes, etc. To establish the physical integrity of an area or item by preventing the undetected movement of nuclear material or equipment. Such measures involve the application of tamper-indicating or surveillance devices. Surveillance refers to both human and instrumental observation aimed at indicating the movement of nuclear material. The verification process consists of three over-lapping elements: (a) Provision by the State of information such as - design information describing nuclear installations; - accounting reports listing nuclear material inventories, receipts and shipments; - documents amplifying and clarifying reports, as applicable; - notification of international transfers of nuclear material. (b) Collection by the IAEA of information through inspection activities such as - verification of design information - examination of records and repo ts - measurement of nuclear material - examination of containment and surveillance measures - follow-up activities in case of unusual findings. (c) Evaluation of the information provided by the State and of that collected by inspectors to determine the completeness, accuracy and validity of the information provided by the State and to resolve any anomalies and discrepancies. To design an effective verification system, one must identify possible ways and means by which nuclear material could be diverted from peaceful uses, including means to conceal such diversions. These theoretical ways and means, which have become known as diversion strategies, are used as one of the basic inputs for the development of safeguards procedures, equipment and instrumentation. For analysis of implementation strategy purposes, it is assumed that non-compliance cannot be excluded a priori and that consequently there is a low but non-zero probability that a diversion could be attempted in all safeguards ituations. An important element of diversion strategies is the identification of various possible diversion paths; the amount, type and location of nuclear material involved, the physical route and conversion of the material that may take place, rate of removal and concealment methods, as appropriate. With regard to the physical route and conversion of nuclear material the following main categories may be considered: - unreported removal of nuclear material from an installation or during transit - unreported introduction of nuclear material into an installation - unreported transfer of nuclear material from one material balance area to another - unreported production of nuclear material, e. g. enrichment of uranium or production of plutonium - undeclared uses of the material within the installation. With respect to the amount of nuclear material that might be diverted in a given time (the diversion rate), the continuum between the following two limiting cases is cons dered: - one significant quantity or more in a short time, often known as abrupt diversion; and - one significant quantity or more per year, for example, by accumulation of smaller amounts each time to add up to a significant quantity over a period of one year, often called protracted diversion. Concealment methods may include: - restriction of access of inspectors - falsification of records, reports and other material balance areas - replacement of nuclear material, e. g. use of dummy objects - falsification of measurements or of their evaluation - interference with IAEA installed equipment.As a result of diversion and its concealment or other actions, anomalies will occur. All reasonable diversion routes, scenarios/strategies and concealment methods have to be taken into account in designing safeguards implementation strategies so as to provide sufficient opportunities for the IAEA to observe such anomalies. The safeguards approach for each facility will make a different use of these procedures, equipment and instrumentation according to the various diversion strategies which could be applicable to that facility and according to the detection and inspection goals which are applied. Postulated pathways sets of scenarios comprise those elements of diversion strategies which might be carried out at a facility or across a State's fuel cycle with declared or undeclared activities. All such factors, however, contain a degree of fuzziness that need a human judgment to make the ultimate conclusion that all material is being used for peaceful purposes. Safeguards has been traditionally based on verification of declared material and facilities using material accountancy as a fundamental measure. The strength of material accountancy is based on the fact that it allows to detect any diversion independent of the diversion route taken. Material accountancy detects a diversion after it actually happened and thus is powerless to physically prevent it and can only deter by the risk of early detection any contemplation by State authorities to carry out a diversion. Recently the IAEA has been faced with new challenges. To deal with these, various measures are being reconsidered to strengthen the safeguards system such as enhanced assessment of the completeness of the State's initial declaration of nuclear material and installations under its jurisdiction enhanced monitoring and analysis of open information and analysis of open information that may indicate inconsistencies with the State's safeguards obligations. Precise information vital for such enhanced assessments and analyses is normally not available or, if available, difficult and expensive collection of information would be necessary. Above all, realistic appraisal of truth needs sound human judgment.

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예인윈치의 설계 및 실험적 검증 (Design and Experimental Verification on a Towing Winch)

  • 양승윤
    • 제어로봇시스템학회논문지
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    • 제5권4호
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    • pp.489-495
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    • 1999
  • This paper contains the design specification and detail design for a towing winch system. We analyze operating condition of the system and decide the design specification for the winch system, and also perform a detail design for the subsystem such as hydraulic winch system, control equipment and power supplier at the full scale development. The performance of designed towing winch is established by load tests and sea trial tests.

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계측제어 기기의 현장적용을 위한 품질보증 사례 (The Case Study of Qualification Assurance for Instrumentation and Control in Nuclear Power Plant)

  • 안병주;이승준;정창기;정우중
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2002년도 하계학술대회 논문집 D
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    • pp.2219-2221
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    • 2002
  • This paper describes QA methodologies for developed TBN control system that will be applied to nuclear power plants. The details are the development of QA Manual, QA Procedures, Equipment Qualification Procedure, Commercial Grade Items Dedication, and Software Verification & Validation Plan.

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제어시스템의 기기검증 시험 종류와 시험방법 (Test Methode & kind of Equipment Verification for Control System)

  • 박두용;임익헌;임건표
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2011년도 제42회 하계학술대회
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    • pp.1786-1787
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    • 2011
  • 화력발전소에 사용되는 제어시스템을 개발함에 있어 하드웨어 분야는 시스템의 안정성과 신뢰성 확보를 위해 반드시 기기검증시험을 통과한 후 적용하여야 한다. 이러한 시험은 제어모듈의 모든 종류의 개별 시험과 실제 사용하고자 하는 구성으로 캐비닛에 모두 장착한 상태에서 시험하여야 한다. 이번 시험은 제어시스템을 설계하고 제작한 후 설계 제원대로 성능을 가지고 있는지에 대한 검증을 목적으로 하였으며, 유럽규격의 CE 마크 획득에 필요한 기준으로 시험을 수행한 기준을 설명한다.

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A TEST VERIFIED MODEL DEVELOPMENT STUDY FOR A NUCLEAR WATER CHILLER USING THE SEISMIC QUALIFICATION ANALYSIS AND TEST

  • Sur, Uk-Hwan
    • Nuclear Engineering and Technology
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    • 제43권4호
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    • pp.355-360
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    • 2011
  • This paper is a study on a nuclear water chiller. It presents a test-verified finite element model of a water chiller to be used at a Nuclear Power Plant. The test-verified model predicts natural frequencies within 5% for all major modes below 50 Hz. This model accurately represents the dynamic characteristics of the actual hardware and is qualified for its use in the final stress analysis for seismic verification.

원자력기기 내진해석응답스펙트럼 생성프로그램 개발 (Development of Response Spectrum Generation Program for Seismic Analysis of the Nuclear Equipment)

  • 변훈석;김유철;이준근
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2004년도 추계학술대회논문집
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    • pp.755-762
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    • 2004
  • In our country, when the replacement for individual components of equipment in nuclear power plants is required, establishment of individual criteria i.e. Required Response Spectra(RRS) of seismic test/analysis for the component is very difficult because of the absence of Test Response Spectra(TRS) for the individual component to be replaced, from the existing qualification documents. In this case, it is required to perform the structural analysis for the nuclear equipment including the components to be replaced. After the structural analysis, Analysis Response Spectra(ARS) at the point of the component shall be generated and used for seismic test of the component. However, as of today, no standard program authorized for the response spectra generation by using the structural analysis exists in korea. Because of above reason, the STAR-Egs computer program was developed by using the method which calculates directly the expected response spectrum(frequency vs. acceleration type) of the selected points in the nuclear equipment with input spectrum(Required Response Spectra, RRS), based on the dynamic characteristics of the Finite Element(FE) model that is equivalent to the nuclear equipment. The STAR-Egs controls ANSYS/I-DEAS commercial software and automatically extract modal parameters of the FE model. The STAR-Egs calculates response spectrum using the established algorithm based on the extracted modal parameters, too. Reliance on the calculation result of the STAR-Egs was verified through comparison output with the result of MATLAB commercial software based on the identical algorithm. Moreover, actual seismic testing was performed as per IEEE344-1987 for the purpose of program verification by comparison of the FE analysis results.

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반도체장비용 오링의 종합 신뢰성 평가기술에 관한 연구 (A Study on the Reliability Evaluation System for O-ring of Semiconductor Equipments)

  • 김동수;김광영;최병오;박화영
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2001년도 춘계학술대회 논문집
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    • pp.613-617
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    • 2001
  • The test items like as endurance, air leakage and oil endurance test is requested for reliability evaluation about O-ring which is a kind of core machinery accessories of semi-conduct manufacturing equipment. For verification of these, we design and manufactured a test system for endurance, air leakage and oil endurance of O-ring for semi-conduct manufacturing equipment, and also performed the test for two kinds of O-ring, as it were Viton and Kalretz. The characteristics of this test equipment consist in realization of the test conditions of semi-conduct manufacturing equipment and satisfying the test method. The test conditions are cut gas, vacuum grade, temperature and revolution numbers in the endurance test system, vacuum grade and temperature in the air leakage test system, temperature and time in the oil endurance test system. The separating test results for wearing which is an oil endurance test item, the wearing index of domestic produced Viton O-ring is higher than foreign product by 2%, wearing rate of Kalretz O-ring better than Viton O-ring by 17%, and particles existed in various place. The test result of air leakage which is measured through the RGA sensor used Helium, the vacuum grade was $10^-3$Torr. And the test result of oil endurance, the volume change rate was 7~15%. Hereafter, we intend to analysis the reliability test evaluation and to utilize for domestic manufacturing companies by establishing data base and developing reliability softwares.

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LNG-FPSO 선박 장비들의 보전활동 지원시스템 개발에 관한 연구 (A Study on the Development of Maintenance System for Equipment of LNG-FPSO Ship)

  • 이순섭;강동훈;이종현;이승준
    • 해양환경안전학회지
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    • 제22권2호
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    • pp.233-239
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    • 2016
  • 본 연구에서는 LNG-FPSO 선박에 탑재되어 있는 장비들의 운영효율을 최대화하기 위한 상태기반유지보수(CBM) 활동을 지원하는 보전시스템을 개발하였다. 개발된 보전시스템에서는 상태기반유지보수를 수행할 주요 장비들을 식별하여 이를 PWBS(Product Work Breakdown Structure)로 정의하였고 식별된 장비들로부터 실시간 수집되는 센서데이터를 이용하여 장비들의 고장분석과 최적 유지 보수 방안을 결정하기 위한 경제성평가 등을 수행하며, 이들을 수행하기 위해 필요한 입출력 데이터를 저장, 관리하는 고장사례 및 유지보수데이터베이스를 구축하였다. 개발시스템의 성능검증을 현재 개발 중인 LNG-FPSO 선박의 Inlet 시스템의 Compressor와 화물창의 Pump Tower 등과 같은 주요 장비들을 대상으로 실시하였고 이를 바탕으로 상태기반유지보수의 가능성을 확인하였다.

고속철도 횡단 강거더 설치공사에서의 BIM 기반 가상건설 장비운영 시뮬레이션의 적용 (BIM-Based Virtual Construction Simulation for Steel Girder Installation Crossing the High-Speed Railway)

  • 박준원;이상호;김성훈;원정훈;윤영철
    • 한국안전학회지
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    • 제33권2호
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    • pp.76-85
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    • 2018
  • The interest in the Building Information Modeling (BIM) technology has risen remarkably due to the effects on construction work period reduction, cost reduction, work safety improvement, and other factors. In civil engineering field, BIM applications mainly focus on data modeling and virtual construction. In this study, we present the BIM-based virtual construction and analyze the effects of BIM for the railway facilities so that the conventional approach to the equipment operation plan can be improved in order to prevent safety accidents which can result from unclear information during the operation plan. The BIM-based virtual construction technology is applied to establish the construction plan for the site with constraints, the installation of steel girder needs to be completed, avoiding interference with the existing high-speed railway operation within a given limited time. A virtual construction model consisting of topography, structures, equipments, and avatar was built and more detailed model, including safety guard rails, was then created. Specifications of the construction equipment were input as a database, and the virtual construction model was manipulated in the equipment operation planning. Through the BIM-based virtual construction, including the verification of alternative construction method, 311 million won was saved and the construction period was shortened by 87 days compared to the original plan. In addition, it was shown that the interest and participation of the construction workers can be increased by providing the 3D virtual scene for real construction work and various safety hazards occurring during equipment operation can be effectively removed in advance by the interactive worker education.