DESIGN OF A VIBRATION AND STRESS MEASUREMENT SYSTEM FOR AN ADVANCED POWER REACTOR 1400 REACTOR VESSEL INTERNALS COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM

被引:4
|
作者
Ko, Do-Young [1 ]
Kim, Kyu-Hyung [1 ]
机构
[1] Korea Hydro & Nucl Power Co Ltd, Cent Res Inst, Taejon 305343, South Korea
关键词
APR1400; RVI; CVAP; Vibration and Stress; Measurement System;
D O I
10.5516/NET.09.2012.049
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In accordance with the US Nuclear Regulatory Commission (US NRC), Regulatory Guide 1.20, the reactor vessel internals comprehensive vibration assessment program (RVI CVAP) has been developed for an Advanced Power Reactor 1400 (APR1400). The purpose of the RVI CVAP is to verify the structural integrity of the reactor internals to flow-induced loads prior to commercial operation. The APR1400 RVI CVAP consists of four programs (analysis, measurement, inspection, and assessment). Thoughtful preparation is essential to the measurement program, because data acquisition must be performed only once. The optimized design of a vibration and stress measurement system for the RVI CVAP is essential to verify the integrity of the APR1400 RVI. We successfully designed a vibration and stress measurement system for the APR1400 RVI CVAP based on the design materials, the hydraulic and structural analysis results, and performance tests of transducers in an extreme environment. The measurement system designed in this paper will be utilized for the APR1400 RVI CVAP as part of the first construction project in Korea.
引用
收藏
页码:249 / 256
页数:8
相关论文
共 28 条
  • [1] Measurement of vibration and stress for APR-1400 reactor internals
    Ko, Do-Young
    Kim, Kyu-Hyung
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2018, 50 (06) : 963 - 970
  • [2] VALIDATION AND BENCHMARKING OF COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM FOR PROTOTYPE REACTOR INTERNALS
    Yang, Jianfeng
    Yu, Lixin
    Choi, Byounghoan
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 2, 2012, : 205 - 209
  • [3] VIBRATION MEASUREMENT PLAN FOR FEED-WATER PIPING SYSTEM FOR THE APR1400 COMPREHENSIVE VIBRATION ASSESSMENT PROGRAM
    Ko, Doyoung
    PROCEEDINGS OF THE 23RD INTERNATIONAL CONGRESS ON SOUND AND VIBRATION: FROM ANCIENT TO MODERN ACOUSTICS, 2016,
  • [4] VIBRATION MEASUREMENT FOR MAIN STEAM PIPING SYSTEM FOR THE APR1400 COMPREHENSIVE ASSESSMENT PROGRAM
    Ko, Do-Young
    Oh, Eung-Se
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONGRESS ON SOUND AND VIBRATION: MAJOR CHALLENGES IN ACOUSTICS, NOISE AND VIBRATION RESEARCH, 2015, 2015,
  • [5] THE DESIGN FEATURES OF THE ADVANCED POWER REACTOR 1400
    Lee, Sang-Seob
    Kim, Sung-Hwan
    Suh, Kune-Yull
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (08) : 995 - 1004
  • [6] Assessment of WWER reactor pressure vessel internals and program of lifetime management
    Ruscák, M
    Zamboch, M
    Erben, O
    PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 997 - 1003
  • [7] Development of an on-line Reactor Internals Vibration Monitoring System(RIDS)
    Park, JH
    Park, JB
    Hwang, C
    Choi, ES
    CONDITION MONITORING AND DIAGNOSTIC ENGINEERING MANAGEMENT, 2001, : 801 - 807
  • [8] Requirement description for R.G. 1.20 addenda 'Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Test'
    Yao, Wei-Da
    Zhang, Ming
    Xie, Yong-Cheng
    Liang, Xing-Yun
    Zhang, Kai
    Hedongli Gongcheng/Nuclear Power Engineering, 2011, 32 (SUPPL. 1): : 1 - 3
  • [9] DEVELOPMENT OF AN ADVANCED PWR REACTOR INTERNALS SYSTEM FINITE ELEMENT MODEL FOR FLOW-INDUCED VIBRATION ANALYSES
    Palamara, Matthew J.
    Smith, Stephen D.
    Walker, Adam P.
    Basel, Richard A.
    Meyer, Gregory A.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 4, 2015,
  • [10] DEVELOPMENT OF STRUCTURAL INTEGRITY ASSESSMENT METHOD FOR FLOW-INDUCED VIBRATION OF REACTOR INTERNALS IN PWR
    Sugiura, Hirokazu
    Watanabe, Shigeyuki
    Iwasaki, Akihisa
    Morita, Hideyuki
    Sakata, Hideyuki
    Nishikawa, Yoshito
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 4, 2019,