• Title/Summary/Keyword: 운전 기준지진

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Seismic Test of the Control Rod Drive Mechanism for JRTR (JRTR 제어봉구동장치의 내진시험)

  • Choi, Myoung-Hwan;Kim, Gyeong-Ho;Sun, Jong-Oh;Cho, Yeong-Garp
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.26 no.5
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    • pp.552-558
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    • 2016
  • A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod within a reactor core to control the reactivity of the core. The CRDM for Jordan Research and Training Reactor with 5MW power has been designed and fabricated based on the HANARO’s experience through KAERI and DAEWOO consortium. This paper describes the seismic test results to demonstrate the operability, the drop performance and the structural integrity of CRDM during or after seismic excitations. The seismic tests are carried out under 5 OBE and 1 SSE loads at three Test Rigs simulating the reactor structure and the pool top. From the tests, the CRDM is smoothly driven without a malfunction of stepping motor under OBE load. The pure drop time under OBE and SSE loads is measured as 1.169s and 1.855s to meet the design requirement. Also, it is found that the CRDM maintains the structural integrity without a change of the function and natural frequency before and after seismic loads.

Site Monitoring System of Earthquake, Fault and Slope for Nuclear Power Plant Sites (원자력발전소의 부지감시시스템의 운영과 활용)

  • Park, Donghee;Cho, Sung-il;Lee, Yong Hee;Choi, Weon Hack;Lee, Dong Hun;Kim, Hak-sung
    • Economic and Environmental Geology
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    • v.51 no.2
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    • pp.185-201
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    • 2018
  • Nuclear power plants(NPP) are constructed and operated to ensure safety against natural disasters and man-made disasters in all processes including site selection, site survey, design, construction, and operation. This paper will introduce a series of efforts conducted in Korea Hydro and Nuclear Power Co. Ltd., to assure the safety of nuclear power plant against earthquakes and other natural hazards. In particular, the present status of the earthquake, fault, and slope safety monitoring system for nuclear power plants is introduced. A earthquake observatory network for the NPP sites has been built up for nuclear safety and providing adequate seismic design standards for NPP sites by monitoring seismicity in and around NPPs since 1999. The Eupcheon Fault Monitoring System, composed of a strainmeter, seismometer, creepmeter, Global Positioning System, and groundwater meter, was installed to assess the safety of the Wolsung Nuclear Power Plant against earthquakes by monitoring the short- and long-term behavioral characteristics of the Eupcheon fault. Through the analysis of measured data, it was verified that the Eupcheon fault is a relatively stable fault that is not affected by earthquakes occurring around the southeastern part of the Korean peninsula. In addition, it was confirmed that the fault monitoring system could be very useful for seismic safety analysis and earthquake prediction study on the fault. K-SLOPE System for systematic slope monitoring was successfully developed for monitoring of the slope at nuclear power plants. Several kinds of monitoring devices including an inclinometer, tiltmeter, tension-wire, and precipitation gauge were installed on the NPP slope. A macro deformation analysis using terrestrial LiDAR (Light Detection And Ranging) was performed for overall slope deformation evaluation.

Structural Evaluation of Spent Fuel Dry Storage Cask (사용후연료 건식 저장용기의 구조평가)

  • 서기석;이재한;강경훈;박성원;정성환
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.627-631
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    • 2003
  • In a various regulations and standards related to the spent fuel storage, the storage casks should be designed to sustain the structural integrity under the accident conditions of predicted operation and design criteria. These conditions for the structural evaluation requires the drop, tip-over, wind like tornado and typhoon, flood and earthquake. This paper describes the load cases and conceptual evaluation method for the structural evaluation. Preliminary safety analysis of the concrete storage system were peformed.

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실시간 예ㆍ검지 시스템에 의한 철도방재 기술현황

  • 정승용;박영곤;김수삼
    • Journal of the Korean Society for Railway
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    • v.6 no.1
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    • pp.6-13
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    • 2003
  • 최근 세계적인 기상이변으로 인한 재해가 갈수록 증가되고 있으며, 지구 온난화 등 이상기온에 따른 국지성 호우의 발생이 증가함에 따라 이러한 기상이변에 대한 철도재해를 미연에 방지할 수 있는 체계화된 방재시스템 구축이 절실히 요구되고 있다. 철도재해 발생시 경고체계와 우회로 부재에 따른 막대한 경제적 손실이 예상되고 있으므로 강우, 지진 등에 의한 재해 위험에 대해 실질적인 감시관리시스템과 운전규제기준의 재정립이 필요한 실정이다. 특히 국내에서 자주 발생하는 대표적인 재해원인으로는 태풍을 들 수 있는데 작년 8월 우리나라를 관통한 태풍 루사(RUSA)의 경우 일 최다 강우량 870.5mm, 1시간 최다강우량100.5mm를 기록하며, 총 48개소의 철도피해지역과 이로 인한 복구비용은 약 1,472억원 정도로 추정되었고, 경부선 등 전국 8개노선 48개소의 열차운행이 일시 중단된 바 있다. (중략)

A Stress Analysis of Wall-Thinned Feedwater Ring in Nuclear Power Plant (원전 증기발생기 감육 급수링 응력해석)

  • Min Ki Cho;Ki Hyun Cho
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.17 no.1
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    • pp.56-63
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    • 2021
  • The feedwater ring is an assembly in steam generator internal piping, which distributes feedwater into the secondary side of the steam generator. It consists of an assembly of carbon steel piping, pipe fittings and J-nozzles which are inserted into the top of the feedwater ring and welded to the diameter of the ring. The feedwater ring at the attachment region of the J-nozzle may be susceptible to flow accelerated corrosion (FAC) due to flow turbulence which increases local fluid velocities. If a J-nozzle becomes a loose part, it can cause damage to tubing near the tube sheet. In this paper, the structural stress analysis for a wall thinned feedwater ring and integrity evaluations under assumed loading conditions are carried out in compliance with ASME B&PV SecIII, NB-3200.

Improvement in Design Load and Seismic Performance Objective for Industrial and Environmental Facilities (산업환경시설의 설계하중과 내진성능목표 개선안)

  • Kim, Ickhyun;Hong, Kee-Jeung;Kim, Jung Han;Lee, Jin Ho;Cho, Sunggook;Lee, Jin-Hyeong
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.42 no.6
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    • pp.763-773
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    • 2022
  • Industrial and environmental facilities, which are national growth engine, must sustain their structural safety and maintain their process to continue production activities under various load conditions including natural hazards. In this study, by improving existing design codes which aim to secure the structural safety only, new structural and seismic design codes are proposed to secure both the structural safety and the operability of facilities. In the proposed structural design code, a variety of loads to reflect the characteristics of industrial and environmental facilities are considered and load combinations for the ultimate strength design and the allowable stress design of structures are suggested. Considering the importance of a unit industrial facility and that of a unit process, the seismic design class, design earthquake, and seismic performance level of a unit component are determined to achieve the dual seismic performance objectives for securing both the structural safety and the operability. Also, the proposed design code are applied to an example of an environmental facility in order to examine its applicability.