Browse > Article
http://dx.doi.org/10.5050/KSNVE.2011.21.8.708

Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program  

Ko, Do-Young (한국수력원자력(주) 중앙연구원)
Kim, Kyu-Hyung (한국수력원자력(주) 중앙연구원)
Kim, Sung-Hwan (한국수력원자력(주) 중앙연구원)
Publication Information
Transactions of the Korean Society for Noise and Vibration Engineering / v.21, no.8, 2011 , pp. 708-713 More about this Journal
Abstract
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.
Keywords
RVI; CVAP; APR1400; Measurement Program;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 Ko, D. Y., Lee, J. G. and Kim, K. H., 2009, Vibration Measurement Plan of RVI CVAP for Shin-kori unit 4, Transactions of the Korean Nuclear Society Spring Meeting, pp. 1037-1038.
2 Park, C. Y. and Kim, J. W., 2000, Report on the Observation and Synthesis about CVAP in KNGR RVI, TM.99NJ13.P2000.243, Korea Electric Power Corp., Daejeon, pp. 19-22.
3 KEPCO Engineering and Construction Company Inc., 2008, Design Specification for Reactor Vessel Core Support and Internal Structures.
4 KEPCO Engineering and Construction Company Inc., 2008, Fluid System and Component Engineering Design Data for Plant Safety, Containment and Performance Analyses.
5 KEPCO Engineering and Construction Company Inc., 2008, System Description for Reactor Internals Assembly.
6 KEPCO Engineering and Construction Company Inc., 2008, Reactor Vessel Core Support and Internal Structures System Design Requirements.
7 KEPCO Engineering and Construction Company Inc., 2008, Design Data for The Hydraulic Loads on Reactor Internals During Normal Operation.
8 Combustion Engineering Inc., 1984, A Comprehensive Vibration Assessment Program for the Prototype System 80 Reactor Internals Palo Verde Nuclear Generating Station Unit 1.
9 U. S. Nuclear Regulatory Commission, 2007, Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Testing, Regulatory Guide 1.20 Rev. 3, Nuclear Regulatory Commission, Washington, pp. 1-25.
10 Ko, D. Y. and Lee, J. G., 2011, A Review of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 21, No. 1, pp. 47-55.   과학기술학회마을   DOI
11 Ko, D. Y. and Lee, J. G., 2010, Development of a Remote Measurement System for the Gap between RV and CSB for RVI-modularization, Nuclear Engineering and Design, Vol. 240, pp. 2907-2913.   DOI
12 Ko, D. Y., Lee, J. G., Kang, Y. C. and Kim, S. H., 2009, Development of a Measurement System of Gap between CSB and RV to Shorten a Nuclear Reactor Installation Period, Nuclear Engineering and Design, Vol. 39, pp. 495-500.
13 Ko, D. Y., Lee, J. G. and Kim, K. H., 2009, Preliminary Determination Measurement Sensors and Location for RVI CVAP of Shin-kori #4, Proceedings of the Conference on Information and Control Systems, pp. 216-217.