Transactions of the Korean Society for Noise and Vibration Engineering (한국소음진동공학회논문집)

The Korean Society for Noise and Vibration Engineering (한국소음진동공학회)
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Validation of Vibration and Stress Analysis Method for APR1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program

APR1400 원자로내부구조물 종합진동평가프로그램 진동 및 응력해석 방법 검증

  • Kim, Kyu Hyung (Korea Hydro & Nuclear Power Co., LTD., Central Research Institute) ;
  • Ko, Do Young (Korea Hydro & Nuclear Power Co., LTD., Central Research Institute) ;
  • Kim, Sung Hwan (Korea Hydro & Nuclear Power Co., LTD., Central Research Institute)
  • Received : 2012.10.17
  • Accepted : 2013.03.26
  • Published : 2013.04.20
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Abstract

The vibration and stress analysis program of comprehensive vibration assessment program(CVAP) is to theoretically verify the structural integrity of reactor vessel internals(RVI) and to provide the basis for selecting the locations monitored in measurement and inspection programs. This paper covers the applicability of the vibration and stress analysis method of APR1400 RVI CVAP. The analysis method was developed to use 3-dimensional detail hydraulic and structural models with ANSYS and CFX. To assess the method, the hydraulic loads and structural reponses of OPR1000 were predicted and compared with the measured data in the OPR1000 RVI CVAP. The results predicted with this method were close to the measured values considerably. Therefore, the analysis method was developed properly.

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References

  1. U.S. NRC, Regulatory Guide 1.20, 2007, Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing.
  2. Combustion Engineering, Inc., 1984, A Comprehensive Vibration Assessment Program for the Prototype System 80 Reactor Internals(Palo Verde Nuclear Generating Station Unit 1), CEN-202(V)-P.
  3. KEPCO, 1995, A Comprehensive Vibration Assessment Program for Yonggwang Nuclear Generating Station Unit 4, 10487-ME-TE-240-03.
  4. 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
  5. Kim, K. H., Ko, D. Y. and Kim, S. H., 2011, 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, Vol. 21, No. 12, pp. 1098-1103. https://doi.org/10.5050/KSNVE.2011.21.12.1098
  6. 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.
  7. Lim, S. G., Kim, T. J. and Kim, H. G., 2012, CFD Simulation of Acoustic-induced Vibration in Main Steam Line of APR1400, Transactions of the Korean Nuclear Society Spring Meeting, pp. 17-18.
  8. ASME B&PV Section III Division 1 Appendix N, 2010.