• Title/Summary/Keyword: 종합진동평가

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Screening Method for Flow-induced Vibration of Piping Systems for APR1400 Comprehensive Vibration Assessment Program (APR1400 종합진동평가를 위한 배관시스템의 유동유발진동 간이평가)

  • Ko, Do-Young;Kim, Dong-Hak
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.25 no.9
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    • pp.599-605
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    • 2015
  • The revised U.S. Nuclear Regulatory Commission(NRC), Regulatory Guide(RG) 1.20, rev.3 requires the evaluation of the potential adverse effects from pressure fluctuations and vibrations on piping and components for the reactor coolant, steam, feedwater, and condensate systems. Detailed vibration analyses for the systems attached to the steam generator are very difficult, because these piping systems are very complicated. This paper suggests a screening method for the flow-induced vibration of acoustic resonances and pump-induced vibration of the piping systems attached to the steam generator in order to conduct the APR1400 comprehensive vibration assessment program. This paper seeks to address the areas such as potential vibration sources, and methods to prevent the occurrence of acoustic resonances and pump-induced vibration of piping systems attached to the steam generator, for conducting the APR1400 comprehensive vibration assessment program. The screening method in this paper will be used to estimate the flow-induced vibration of the piping systems attached to the steam generator for the APR1400.

Development integrated Evaluation System for Measuring Sound and vibration of Dry Pumps (진공펌프의 소음 진동 측정을 위한 종합 성능 평가 장치 개발)

  • Ryu Je-Dam;Cheung Wan-Sup;Lim Jong-Yeon;Hong Dong-Pyo
    • Proceedings of the Acoustical Society of Korea Conference
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    • spring
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    • pp.221-224
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    • 2004
  • 드라이 펌프(Dry Pump)는 청결을 요구하는 반도체 생산 공정에 많이 사용하고 있다. 오늘날 반도체 수요의 증가와 함께 드라이 펌프의 수요도 늘어나고 있다. 그에 각 반도체 회사들은 진공 펌프의 선정이 매우 중요한 문제 중 하나로 대두대고 있다. 진공 펌프를 위한 종합 성능 평가 장치의 개발은 이들 회사에서 요구하는 펌프의 성능을 종합적으로 평가함으로써 펌프 선정의 중요한 근거 자료로 사용 할 수 있을 것이다. 본 연구에서 구축한 종합성능 평가 장치는 진공 펌프의 최대 도달 진공도(Ultimate Pressure), 배기속도(Pumping Speed), 전력 소비(Power Consumption), 진동(Vibration) 그리고 음향 파워(Sound Power)등과 같은 종합적인 성능을 한번에 평가 할 수 있다.

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Response Instrumentation Test Acceptance Criteria for APR1400 RVI CVAP (APR1400 원자로내부구조물 종합진동평가 응답측정시험 허용기준)

  • Ko, Do-Young;Kim, Kyu-Hyung;Kim, Sung-Hwan
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.21 no.11
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    • pp.1036-1042
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    • 2011
  • APR1400 RVI CVAP using the non-prototype category II is being conducted to verify integrity of the RVI design and to secure the CVAP technology. The measurement programs are to confirm vibration analysis results for reactor internals during pre-operational and initial startup testing and to determine the safety margin. One of the important basis for the measurement programs is test acceptance criteria. Therefore, this paper is on establishment of response instrumentation test acceptance criteria for APR1400 RVI CVAP. The established acceptance criteria show that the stress criteria of APR1400 RVI are more conservative values than those of the valid prototype plant(Palo Verde unit 1) and, the displacement criteria of the inner barrel assembly and the upper guide structure were established to 0.03 in and 0.01 in, respectively.

Establishment of Response Instrumentation Test Acceptance Criteria for APR1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program (APR1400 원자로내부구조물 종합진동평가 응답측정시험 허용기준 수립)

  • Ko, Do-Young;Kim, Kyu-Hyung;Kim, Sung-Hwan
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2011.10a
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    • pp.212-218
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    • 2011
  • APR1400 RVI CVAP using the non-prototype category is being conducted to verify integrity of the RVI design and to secure the CVAP technology. The measurement programs are to confirm vibration analysis results for reactor internals during preoperational and initial startup testing and to detemine the safety margin. One of the important basis for the measurement programs is test acceptance criteria. Therefore, this paper is on establishment of response instrumentation test acceptance criteria for APR1400 RVI CVAP. The established acceptance criteria show that the stress criteria of APR1400 RVI are more conservative values than those of the valid prototype plant(Palo Verde unit 1) and, the displacement criteria of the IBA and the UGS were established to 0.03 in and 0.01 in, respectively.

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Written Plan of CVAP Design Control Document for APR1400 U.S. Design Certification (APR1400 미국 설계인증을 위한 종합진동평가 심사서류 작성 방안)

  • Ko, Do Young;Kim, Dong Hak;Park, Young Sheop
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2014.10a
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    • pp.102-105
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    • 2014
  • In accordance with U.S. Nuclear Regulatory Commission regulatory guide(NRC RG) 1.20(Rev.3), we are writing a comprehensive vibration assessment program(CVAP) design control document(DCD) and a technical report for U.S. NRC design certification(DC) of an Advanced Power Reactor 1400(APR1400) nuclear power plant(NPP). CVAP of an APR1400 NPP for U.S. NRC DC is classified as a non-prototype category 1 type. Therefore, CVAP DCD of reactor vessel internals(RVI) and steam generator internals(SGI) consist of analysis and full inspection program. However, piping system of primary and secondary system will be described as measurement program.

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Selection of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400 (APR1400 원자로 내부구조물 종합진동평가 측정센서 선정)

  • Ko, Do-Young;Lee, Jae-Gon
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2010.10a
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    • pp.433-438
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    • 2010
  • Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. Nuclear Regulatory Commission Regulatory Guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement, and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors. We analyzed RVI design data of Palo Verde nuclear generating station(U.S.) and Yonggwang nuclear generating station(Korea) and investigated measuring sensors used in both of them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected the most suitable sensors for RVI CVAP in Advanced Power Reactor 1400(APR1400).

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Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program (APR1400 원자로내부구조물 종합진동평가 측정위치 선정 기준)

  • Ko, Do-Young;Kim, Kyu-Hyung;Kim, Sung-Hwan
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.21 no.8
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    • pp.708-713
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    • 2011
  • U.S. nuclear regulatory commission(NRC) regulatory guide(RG) 1.20 requires a comprehensive vibration assessment program(CVAP) for use in verifying the structural integrity of reactor vessel internals(RVI) for flow-induced vibrations prior to commercial operation. The CVAP program consist of vibration and fatigue analysis, a vibration measurement program, an inspection program, and a correlation of their results. One of the main purposes of the analysis program is to select measurement locations, however measurement locations can not be determined by only analysis results, therefore we developed selection criteria of measurement locations for advanced power reactor 1400(APR1400) RVI CVAP, It will be used to select measurement locations and instrument types for APR1400 RVI CVAP.