Browse > Article
http://dx.doi.org/10.5050/KSNVE.2012.22.5.474

Structural Analysis and Response Measurement Locations of Inner Barrel Assembly Top Plate in APR1400  

Ko, Do-Young (한수원중앙연구원)
Kim, Kyu-Hyung (한수원중앙연구원)
Kim, Sung-Hwan (한수원중앙연구원)
Publication Information
Transactions of the Korean Society for Noise and Vibration Engineering / v.22, no.5, 2012 , pp. 474-479 More about this Journal
Abstract
A comprehensive vibration assessment program for the advanced power reactor 1400(APR1400) reactor vessel internals is established in accordance with the united states nuclear regulatory commission regulatory guide 1.20 revision 3. This paper is related to instruments and measurement locations based on the vibration and stress response analysis results of the inner barrel assembly top plate in APR1400. The analysis results of the inner barrel assembly top plate in the reactor show that the deterministic stress and deformation due to the reactor coolant pump induced pressure pulsations are larger than the random stress and deformation induced by the flow turbulence. The selection of the instruments and measurement locations at inner barrel assembly top plate in the reactor is essential requirements and very important study process for the vibration and stress measurement program in comprehensive vibration assessment program for APR1400 reactor vessel internals.
Keywords
RVI; CVAP; APR1400; IBA; Measurement;
Citations & Related Records
Times Cited By KSCI : 4  (Citation Analysis)
연도 인용수 순위
1 US Nuclear Regulatory Commission, 2007, Regulatory Guide 1.20, Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Testing, Rev. 3.
2 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, 239(2009), pp. 495-500.   DOI
3 Korea Electric Power Corp., 2000, Report on the Observation and Synthesis about CVAP in KNGR RVI.
4 KEPCO Engineering and Construction Company Inc., 2008, Design Specification for Reactor Vessel Core Support and Internal Structures.
5 KEPCO Engineering and Construction Company Inc., 2008, Fluid System and Component Engineering Design Data for Plant Safety, Containment and Performance Analyses.
6 KEPCO Engineering and Construction Company Inc., 2008, System Description for Reactor Internals Assembly.
7 KEPCO Engineering and Construction Company Inc., 2008, Reactor Vessel Core Support and Internal Structures System Design Requirements.
8 KEPCO Engineering and Construction Company Inc., 2008, Design Data for The Hydraulic Loads on Reactor Internals During Normal Operation.
9 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.   DOI
10 Ko, D. Y., Kim, K. H. and Kim, S. H., 2011, Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 21, No. 8, pp. 708-713.   DOI
11 Ko, D. Y., Kim, K. H. and Kim, S. H., 2011, Response Instrumentation Test Acceptance Criteria for APR1400 RVI CVAP, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 21, No. 11, pp. 1306-1042.
12 Kim, K. H., Ko, D. Y. and Kim, S. H., 2011, Vibration Stress Analysis for Reactor Vessel Internals of Advanced Power Reactor 1400 by Pulsation of Reactor Coolant Pump, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 21, No. 12, pp. 1098-1103.   DOI
13 Kim, K. H., Ko, D. Y. and Kim, T. S., 2011, Hydraulic and Structural Analysis for APR1400 Reactor Vessel Internals against Hydraulic Load Induced by Turbulence, International Journal of Safety, Vol. 10, No. 2, pp. 1-5.
14 Kim, K. H., Ko, D. Y. and Kim, Y. S., 2009, Hydraulic and Structural Analysis Methodology of RVI CVAP in Shin-Kori 4, Transaction of the Korean Nuclear Society Spring Meeting, pp. 1113-1114.
15 Gu, J. Y., Kim, K. H. and Kim, Y. S., 2010, Development and Validation of Structural Analysis Methodology for Comprehensive Vibration Assessment for Reactor Vessel Internals, Proceeding of the Korean Society of Mechanical Engineers, pp. 950-955.
16 Kim, K. H., Ko, D. Y. and Gu, J. Y., 2011, Deterministic Hydraulic Load Analysis on Reactor Internals of APR1400, Transaction of the Korean Nuclear Society Spring Meeting, pp. 26-27.
17 ASME, 2010, Boiler & Pressure Vessel Code Section III, Division 1 - Appendices, Rules for Construction of Nuclear Facility Components.
18 KEPCO, 1995, A Comprehensive Vibration Assessment Program for Yonggwang Nuclear Generating Station Unit 4, 10487-ME-TE-240-03.