DOI QR코드

DOI QR Code

Development of a new CVAP structural analysis methodology of APR1400 reactor internals using scaled model tests

  • Jongsung Moon (KEPCO E&C (Korea Electric Power Corporation Engineering & Construction)) ;
  • Inseong Jin (KEPCO E&C (Korea Electric Power Corporation Engineering & Construction)) ;
  • Doyoung Ko (KHNP(Korea Hydro & Nuclear Power Co, Ltd.)) ;
  • Kyuhyung Kim (KHNP(Korea Hydro & Nuclear Power Co, Ltd.))
  • 투고 : 2023.02.15
  • 심사 : 2023.10.03
  • 발행 : 2024.01.25

초록

The U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.20 provides guidance on the comprehensive vibration assessment program (CVAP) to be performed on reactor internals during preoperational and startup tests. The purpose of the program is to identify loads that could cause vibration in the reactor internals and to ensure that these vibrations do not affect their structural integrity. The structural vibrational analysis program involves creating finite element analysis models of the reactor internals and calculating their structural responses when subjected to vibration loads. The appropriateness of the structural analysis methodology must be demonstrated through benchmarks or any other reasonable means. Although existing structural analysis methodologies have been proven to be appropriate and are widely used, this paper presents the development of an improved new structural analysis methodology for APR1400 reactor internals using scaled model tests.

키워드

과제정보

This research was supported by KHNP (Korea Hydro & Nuclear Power Co., Ltd.) and received assistance from KEPCO E&C (Korea Electric Power Corporation Engineering & Construction), Doosan Enerbility, Woojin, and KIMM (Korea Institute of Machinery & Materials) in the design of experiments, testing, and analysis.

참고문헌

  1. U.S. NRC, Regulatory Guide 1.20, Rev. 4, Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Startup Testing, February 2017.
  2. NUAP-0727-NP, Rev. 3, Comprehensive Vibration Assessment Program for USAPWR Reactor Internals, Mitsubishi Heavy Industries, LTD., November 2012.
  3. APP-CVAP-GES-002 (WCAP-17534-NP, Rev.0), Vibration Analysis Plan for the AP1000 Comprehensive Vibration Assessment Program, Westinghouse, April 2012.
  4. ANP-10306NP, Rev. 1, Comprehensive Vibration Assessment Program for U.S. EPR the Reactor Internals - Technical Report, AREVA NP Inc., January, 2013.
  5. APR1400-Z-M-NR-14009-NP, Rev. 1, Comprehensive Vibration Assessment Program for Reactor Vessel Internals, KEPCO & KHNP, February 2017.
  6. K.H. Kim, D.Y. Ko, S.H. Kim, Vibration and 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, December, 2011.
  7. K.H. Kim, D.Y. Ko, S.H. Kim, Validation of Vibration and Stress Analysis Method for APR1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program, Transaction of the Korean Society for Noise and Vibration Engineering, March 2013.
  8. ANSYS Release 18.0, ANSYS, Inc. (www.ansys.com).
  9. ASME V&V 10, Guide for Verification and Validation in Computational Solid Mechanics, 2006.
  10. M. Pastor, M. Binda, T. Harcarik, Modal Assurance Criterion, Procedia Engineering, November 2012.
  11. R.J. Fritz, The Effect of Liquids on the Dynamic Motions of Immersed Solids, ASME J. Eng. Indust. (February 1972).
  12. ASME Boiler and Pressure Vessel Code, Section III, Appendix N, Dynamic Analysis Methods, 2019.
  13. J. Batham, Pressure Distribution on Circular Cylinders at Critical Reynolds Numbers, J. Fluid Mech. (February 1973).
  14. E. Szechenyi, Supercritical Reynolds Number Simulation for Two-Dimensional Flow over Circular Cylinders, J. Fluid Mech. (August 1975).
  15. ASME Boilder and Pressure Vessel Code, Section II - Part D, Properties, Edition, 2019.