Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

VIBRATION AND STRESS ANALYSIS OF A UGS ASSEMBLY FOR THE APR1400 RVI CVAP

  • Ko, Do-Young (Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd.) ;
  • Kim, Kyu-Hyung (Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd.)
  • Received : 2011.10.19
  • Accepted : 2012.01.26
  • Published : 2012.10.25
Download PDF
⟨ Previous Next ⟩

Abstract

The most important component of a nuclear power plant is its nuclear reactor. Studies on the integrity of reactors have become an important part regarding the safety of a nuclear power plant. The US Nuclear Regulatory Commission Regulatory Guide (NRC RG) 1.20 presents a Comprehensive Vibration Assessment Program (CVAP) to be used to verify the structural integrity of the Reactor Vessel Internals (RVI) for flow-induced vibration prior to commercial operation. However, there are few published studies related to the RVI CVAP. We classified the Advanced Power Reactor 1400 (APR1400) RVI CVAP as a non-prototype category-2 reactor as part of an independent validation of its design. The aim of this paper is to present the results of structural response analyses of the Upper Guide Structure (UGS) assembly of the APR1400 reactor. These results show that the UGS and the Inner Barrel Assembly (IBA) meet the specified integrity levels of the design acceptance criteria. The vibration and stress analysis results in this paper will be used as basic information to select measurement locations of the vibration and stress for the APR1400 RVI CVAP.

Keywords

References

  1. US Nuclear Regulatory Commission, "Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing," Regulatory Guide 1.20, Rev.0 (2007).
  2. D. Y. Ko and J. G. Lee, "A Review of Measuring Sensors for Reactor Vessel Internals Comprehensive Vibration Assessment Program in Advanced Power Reactor 1400," Transactions of Korean Society for Noise and Vibration Engineering, Vol. 21, No. 1, pp. 47-55 (2011). https://doi.org/10.5050/KSNVE.2011.21.1.047
  3. D. Y. Ko, K. H. Kim and S. H. Kim, "Selection Criteria of Measurement Locations for Advanced Power Reactor 1400 Reactor Vessel Internals Comprehensive Vibration Assessment Program," Transactions of Korean Society for Noise and Vibration Engineering, Vol. 21, No. 8, pp. 708- 713 (2011). https://doi.org/10.5050/KSNVE.2011.21.8.708
  4. D. Y. Ko, K. H. Kim and S. H. Kim, "Response Instrumentation Test Acceptance Criteria for APR1400 RVI CVAP," Transactions of Korean Society for Noise and Vibration Engineering, Vol. 21, No. 11, pp. 1036- 1042 (2011). https://doi.org/10.5050/KSNVE.2011.21.11.1036
  5. D. Y. Ko, K. H. Kim and S. H. Kim, "Structural Analysis and Response Measurement Locations of Inner Barrel Assembly Top Plate in APR1400," Transactions of Korean Society for Noise and Vibration Engineering, Vol. 22, No. 5, pp. 474-479 (2012). https://doi.org/10.5050/KSNVE.2012.22.5.474
  6. K. H. Kim, D. Y. Ko and S. H. Kim, "Vibration Stress Analysis for Reactor Vessel Internals of Advanced Power Reactor 1400 by Pulsation of Reactor Coolant Pump," Transactions of Korean Society for Noise and Vibration Engineering, Vol. 21, No. 12, pp. 1098-1103 (2011). https://doi.org/10.5050/KSNVE.2011.21.12.1098
  7. D. Y. Ko and J. G. Lee, "Development of a remote measurement system for the gap between RV and CSB for RVI-modularization," Nucl. Eng. Des, Vol. 240, pp. 2907- 2913 (2010). https://doi.org/10.1016/j.nucengdes.2010.05.048
  8. K. H. Kim, D. Y. Ko and Y. S. Kim, "Hydraulic and Structural Analysis Methodology of RVI CVAP in Shin- Kori 4," Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 18-23, 2009.
  9. K. H. Kim, D. Y. Ko and J. Y. Gu, "Deterministic Hydraulic Load Analysis on Reactor Internals of APR1400," Transaction of the Korean Nuclear Society Spring Meeting, Taebaek, Korea, May 26-27, 2011.
  10. J. Y. Gu, K. H. Kim and Y. J. Choi, "Structural Response of APR1400 CSB to Pressure Pulsation of RCP," Proceeding of Korean Society of Safety, Wonju, Korea, May 19-20, 2011
  11. K. H. Kim, Y. S. Kim and D. Y. Ko "Evaluation of Detached Eddy Simulation Applicability to Random Hydraulic Load Analysis for Reactor Vessel Internals," Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea, Oct. 21-22, 2010.
  12. J. Y. Gu, K. H. Kim and Y. S. Kim, "Development and Validation of Structural Analysis Methodology for Comprehensive Vibration Assessment for Reactor Vessel Internals," Proceeding of the Korean Society of Mechanical Engineers, Jeju, Korea, Nov. 3-5, 2010.

Cited by

  1. Screening Method for Flow-induced Vibration of Piping Systems for APR1400 Comprehensive Vibration Assessment Program vol.25, pp.9, 2015, https://doi.org/10.5050/KSNVE.2015.25.9.599