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Vibration and Stress Analysis for Reactor Vessel Internals of Advanced Power Reactor 1400 by Pulsation of Reactor Coolant Pump

원자로냉각재펌프 맥동에 대한 APR1400 원자로내부구조물의 진동 및 응력 해석

  • 김규형 (한국수력원자력(주) 중앙연구원) ;
  • 고도영 (한국수력원자력(주) 중앙연구원) ;
  • 김성환 (한국수력원자력(주) 중앙연구원)
  • Received : 2011.08.31
  • Accepted : 2011.10.21
  • Published : 2011.12.20

Abstract

The structural integrity of APR1400 reactor vessel internals has been being assessed referring the US Nuclear Regulatory Commission regulatory guide 1.20, comprehensive vibration assessment program. The program is composed of a vibration and stress analysis, a vibration and stress measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals by the pulsation of reactor coolant pump. 3-dimensional models to calculate the hydraulic loads and structural responses were built and the pressure distributions and the structural responses were predicted using ANSYS. This paper presents that APR1400 reactor vessel internals have enough structural integrity against the pulsation of reactor coolant pump as the peak stress of the reactor vessel internals is much lower than the acceptance limit.

Keywords

References

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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