원자로냉각재펌프 맥동에 대한 APR1400 원자로내부구조물의 진동 및 응력 해석

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

  • 김규형 (한국수력원자력(주) 한수원중앙연구원) ;
  • 고도영 (한국수력원자력(주) 한수원중앙연구원) ;
  • 김성환 (한국수력원자력(주) 한수원중앙연구원)
  • 발행 : 2011.10.27

초록

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 limited vibration measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals due to 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. The peak stress of the reactor vessel internals is much lower than the acceptance limit.

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