• Title/Summary/Keyword: equipment qualification

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Development of Liquid Metal Passive Cooling Flow Simulation System (액체금속 피동냉각유동모사 실증설비의 개발)

  • Ryu, Kyung-Ha;Kim, Jae-Hyoung;Lee, Tae-Hyun;Lee, Sang-Hyuk;Bahn, Byoung-Min
    • Transactions of the KSME C: Technology and Education
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    • v.3 no.4
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    • pp.257-264
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    • 2015
  • To maintain sustainability of nuclear energy as an important energy source, both safety problem and Spent Nuclear Fuels(SNFs) problem should be solved. In case of Gen-IV reactors such as fast reactor, SNFs can be used as fuels by using fast neutrons. It can be a suitable treatment method of high-level waste in near future. Liquid metals such as Sodium or Lead-Bismuth Eutectic (LBE) can be possibly used as a coolant to use fast neutrons. In this paper, it was described that natural circulation parameter studies, design analyses, material selections and a completion of facilities. To develop a natural circulation facility, thermal hydraulic analyses were performed. Installation technique of liquid metal natural circulation were secured.

Electromagnetic Interference Test Result Analysis of Integral Reactor Digital I&C System (일체형 원자로 디지털 계측제어계통 전자파 장애 시험결과 분석)

  • Lee, Joon-Koo;Sohn, Kwang-Young;Park, Hee-Seok;Park, Heui-Yun;Koo, In-Soo
    • Proceedings of the Korea Electromagnetic Engineering Society Conference
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    • 2003.11a
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    • pp.213-218
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    • 2003
  • Because of the development of digital technology, modern digital instrumentation & control systems are being innovativly developed in industrial plants. Whereas, many analog systems are still being used in nuclear plants, because of the demerits of digital equipment. As known, the demerits of digital equipment are the uncertainty and weaknesses in ambient environments such as smoke & electromagnetic interference In an Integral Reactor, a digital I&C system will be composed of microprocessor, memory and network card. Designers will apply new technique for digital equipment. Thus, it is important for digital I&C systems to operate according to designed functions & performance in the ambient environments during a life cycle. Digital I&C systems should have tolerance in such environments and environment qualification should be concluded To acquire electromagnetic interference qualification of digital equipment, this paper suggests an EMI test requirement. Designers should consider the electromagnetic compatibility and test digital equipment according to each test procedure. This paper involves an EMI test requirement and the results analysis of EUT(Equipment Under Test). Test result analysis will be used as electromagnetic compatibility design guides for Integral Reactor I&C systems.

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Anaysis of Equipment Qualification Tests for IMCS(Integrated Monitoring & Control System) in Thermal Power Plants (화력발전소 통합감시제어시스템의 기기검증시험 사례 분석)

  • Shin, Man-Su;Lee, Joo-Hyun;Park, Du-Yong;Byun, Seung-Hyun;Choi, In-Kyu;Lee, Se-Gyeong
    • Proceedings of the KIEE Conference
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    • 2011.07a
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    • pp.1820-1821
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    • 2011
  • The equipment qualification test was accomplished before application to power generating stations because troubles in applying to real system could be prevented trough the test. That is, if a system was judged to be suitable in the equipment qualification test, the system was expected to be operated stable to the designed life.

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Development of An Optimum Model Using Safety-Related Equipment Qualification for the Air Conditioner in the Nuclear Power Plant (원자력 발전소에 사용되는 항온항습기의 안전관련 기기검증을 통한 최적 모델 개발)

  • Sur, Uk-Hwan;Lee, Yeong-Seop
    • Journal of the Korean Society of Safety
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    • v.21 no.1 s.73
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    • pp.1-5
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    • 2006
  • The damage of important equipments for the nuclear power plant by the earthquake brings the loss of human lives and economic losses. Therefore safety-related equipment of nuclear power plant must be proved that function must be designed and structural integrity so that it can be maintained also from accident condition of various kinds. In this study, the computer room air conditioner to be delivered at the nuclear power plant applied to this qualification, try to develop an optimum model. This model ended up with good results which were under suitably allowable conditions about structurally safe earthquake.

A Study on the Development of Qualification for Semiconductor Machine Maintenance (반도체장비유지보수 자격개발에 관한 연구)

  • Kang, Seok-Ju
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.13 no.6
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    • pp.2472-2478
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    • 2012
  • This research is aiming to develop Semiconductor equipment maintenance certification course to train qualified maintenance experts more effectively requested in related semiconductor industry. In the course of research, we adopted diverse research technique such as interview, on-spot investigation, documentary references to analyze current status of related training facilities, and forecast the population of test applicants. We analyzed similar certification course(Craftsman SMT, Industrial Engineer SMT, Craftsman Mechatronics, Industrial Enginee Mechatronics, et) as reference to set up job objectives and curriculum of semiconductor equipment maintenance certification. We conducted survey on expectations on newly created certificate, presented evaluation standard and objective of test, and preliminary writing test and demonstration test. Based on the result of various research, we were able to present training program for semiconductor equipment maintenance certification and set the assessment standard of qualification exam.

Seismic Qualification of the Air Conditioning Equipment for Nuclear Power Plant (원자력 발전소용 공조기에 대한 내진검증)

  • 이준근;김진영;정필중;정정훈
    • Journal of KSNVE
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    • v.9 no.3
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    • pp.535-543
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    • 1999
  • The seismic qualification of the structures has been great concern in our engineering society with an effort to reduce the severe damages from an earthquake. However, on the contrary to the importance of the seismic qualification, the whole procedures are used to rely on the advanced countries who require various expenses for the qualification, which leads to the heavy loss of the foreign currency. In this study, the nuclear air conditioning system produced by LG Cable are adopted for the seismic qualification based on the guideline of NUREG, IEEE and ASME code. In order to confirm the validity of the present study, the results from the Ellis & Watts are compared with the present results and, also, the seismic qualification procedures and results mentioned herein are approved by KOPEC, which is a naitonal surveillance institute for the construction of nuclear power plant. From these results, the author confirmed the validity of the present seismic qualification procedures and results, which might be usefully applied to the other kind of seismic qualification of equipments.

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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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    • v.43 no.4
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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.

Equipment Qualification of Control Rod Control System for Nuclear Power Plants (원전용 제어봉 제어시스템의 기기검증)

  • Lee, J.M.;Kim, C.K.;Cheon, J.M.;Park, M.K.;Kweon, S.M.;Nam, J.H.
    • Proceedings of the KIEE Conference
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    • 2005.07d
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    • pp.2603-2605
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    • 2005
  • This paper describes an experience on the equipment qualification of CRCS(control rod control system) that has been developed for nuclear power plants. A very high level criteria should be satisfied for the equipment to be used for nuclear power plants. We have developed a CRCS that is aimed to be applied to commercial plants. This system adopts a duplex system structure that is based on the state-of-the-art digital technology so that it has higher reliability than the existing systems. The CRCS has been tested at a licensed testing organization and finally qualified. In this paper, the procedures and some trial-and-errors we have been through in the qualification process are explained. It is expected that our experience will be a helpful tips to the industry that are developing various systems for safety-critical plants.

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Analysis of revised regulatory guidance on electromagnetic interference qualification for nuclear safety

  • In Beom Ahn;Jaeyul Choo ;Jae Yoon Park ;Hyunchul Ku ;Kyeong-Sik Min
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.870-875
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    • 2023
  • In this paper, we analyzed the revised guidance on electromagnetic (EM) interference qualification of Regulatory Guide 1.180 (Revision 2), which is published by the U.S. Nuclear Regulatory Commission for electromagnetic compatibility qualification for nuclear safety, by comparing it with that of the previous version. We confirmed that the test methods and the acceptance criteria of both CE101 and CE102 tests for conductive emission and RE102 test for radiating emission are changed in the recently revised Regulatory Guide 1.180 (Revision 2). Furthermore, we found that the revised Regulatory Guide 1.180 provides flexibility in the use of alternative methods for EM interference (EMI) qualification, in that a mix of the various base-standards is technically allowed. In addition, the primary revision of the updated Regulatory. Guide 1.180 is that MIL-STD-461G is to be adopted as the latest base-standard, instead of MIL-STD-461E. To evaluate the influence on EMI qualification for nuclear safety due to the endorsement of MIL-STD-461G, we thoroughly analyzed the modifications in the acceptance criteria and test methods for EMI qualification, and then validated the analyzed effect on the EMI qualification, which is caused by the revision of MIL-STD-461, by performing electromagnetic simulation for equipment under RE102 test.

Generation of Floor Response Spectra Considering Coupling Effect of Primary and Secondary System (부구조시스템의 연계 효과를 고려한 구조물의 층응답 스펙트럼 생성)

  • Cho, Sung Gook;Gupta, Abhinav
    • Journal of the Earthquake Engineering Society of Korea
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    • v.24 no.4
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    • pp.179-187
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    • 2020
  • Seismic qualification of equipment including piping is performed by using floor response spectra (FRS) or in-structure response spectra (ISRS) as the earthquake input at the base of the equipment. The amplitude of the FRS may be noticeably reduced when obtained from coupling analysis because of interaction between the primary structure and the equipment. This paper introduces a method using a modal synthesis approach to generate the FRS in a coupled primary-secondary system that can avoid numerical instabilities or inaccuracies. The FRS were generated by considering the dynamic interaction that can occur at the interface between the supporting structure and the equipment. This study performed a numerical example analysis using a typical nuclear structure to investigate the coupling effect when generating the FRS. The study results show that the coupling analysis dominantly reduces the FRS and yields rational results. The modal synthesis approach is very practical to implement because it requires information on only a small number of dynamic characteristics of the primary and the secondary systems such as frequencies, modal participation factors, and mode shape ordinates at the locations where the FRS needs to be generated.