DOI QR코드

DOI QR Code

Structural Analysis and Measuring Locations of Upper Guide Structure Assembly in APR1400

APR1400 상부안내구조물집합체 구조해석 및 측정위치 선정

  • Ko, Do-Young (Korea Hydro and Nuclear Power Co., Ltd., Central Research Institute(KHNP-CRI)) ;
  • Kim, Kyu-Hyung (Korea Hydro and Nuclear Power Co., Ltd., Central Research Institute(KHNP-CRI)) ;
  • Kim, Sung-Hwan (Korea Hydro and Nuclear Power Co., Ltd., Central Research Institute(KHNP-CRI))
  • Received : 2012.09.20
  • Accepted : 2012.10.24
  • Published : 2013.01.20

Abstract

A reactor vessel internals comprehensive vibration assessment program(RVI CVAP) of an advanced power reactor 1400(APR1400) is being performed as a non-prototype category-2 type of reactor based on the US nuclear regulatory commission regulatory guide(NRC RG) 1.20. The aim of this paper is to present the results of structural response analysis and measuring locations of a upper guide structure(UGS) assembly of the APR1400 reactor. The analysis results of the UGS assembly show that the specified integrity levels meet the design acceptance criteria. Also, the measuring locations are determined by the analysis results of the UGS assembly and selection criteria of previous study. These analysis results and measuring locations will be used as a guide to design a measurement system for the APR1400 RVI CVAP.

Keywords

References

  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. Korea Electric Power Corp., 2000, Report on the Observation and Synthesis about CVAP in KNGR RVI.
  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, Reactor Vessel Core Support and Internal Structures System Design Requirements.
  5. KEPCO Engineering and Construction Company Inc., 2008, Design Data for The Hydraulic Loads on Reactor Internals During Normal Operation.
  6. 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. https://doi.org/10.5050/KSNVE.2011.21.1.047
  7. 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. https://doi.org/10.5050/KSNVE.2011.21.8.708
  8. 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. https://doi.org/10.5050/KSNVE.2011.21.11.1036
  9. Ko, D. Y., Kim, K. H. and Kim, S. H., 2012, Structural Analysis and Response Measurement Locations of Inner Barrel Assembly Top Plate in APR1400, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 22, No. 5, pp. 474-479. https://doi.org/10.5050/KSNVE.2012.22.5.474
  10. 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. https://doi.org/10.5050/KSNVE.2011.21.12.1098
  11. 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.
  12. ASME, 2010, Boiler & Pressure Vessel Code Section III, Division 1 - Appendices, Rules for Construction of Nuclear Facility Components.
  13. 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.
  14. KEPCO, 1995, A Comprehensive Vibration Assessment Program for Yonggwang Nuclear Generating Station Unit 4, 10487-ME-TE-240-03.