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지진하중이 적용되는 배관 관통부의 용접에 대한 구조 건전성 해석

Analytical Structural Integrity for Welding Part at Piping Penetration under Seismic Loads

  • 투고 : 2014.02.03
  • 심사 : 2014.02.17
  • 발행 : 2014.02.28

초록

The purpose of this paper is to assess the structural integrity of piping penetrations for nuclear power plants. A piping qualification analysis describes loads due to deadweight, pressure difference acts normal to the plate, thermal transients, and earthquakes, among other events, on piping penetrations that have been modeled as an anchor. Amodel was analyzed using a commercial finite element program. Apiping penetration analysis model was constructed with an assembly of pipe, head fittings and sleeves. Normally, the design load, thus obtained, will consist of three moments and three forces, referred to a Cartesian coordinate system. When comparing the stress analysis results from each required cutting position, the general membrane stress intensities and local membrane plus bending stress intensities during a structural evaluation cannot exceed the allowable amount of stress for the design loads. Therefore, the piping penetration design satisfies the code requirements.

키워드

참고문헌

  1. Nuclear Power Engineering Committee of the IEEE Power Engineering Society, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 323, 1983.
  2. Nuclear Power Engineering Committee of the IEEE Power Engineering Society, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 323, 1987.
  3. ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities.
  4. Andrew D. Dimarogonas, Vibration for Engineers, Prentis Hall, 127-137, 1996.
  5. A. C Hang and G. O Sankey, "The Containment of Disc Burst Fragments by Cylindrical Shells", Journal of Engineering for Power. 114-309, April 1974.
  6. E. Oberg and F. D. Jones, Machinery's Handbook, 28th Edition, 224, 2009.
  7. ASME OM Code, Code for Operation and Maintenance of Nuclear Power Plants, 2007 Edition with 2009 Addenda.
  8. Korea Electric Power Industry Code, KEPIC-MN, Rules for Construction of Nuclear Power Plant Component, ASME Boiler & Pressure Vessel Code Section III, Division 1. Subsection NB/MC, 2010 Edition with 2007 through 2009 Addenda.
  9. ANSYS version 12.1

피인용 문헌

  1. Detection and Comparison of Surface Defects in Pipe Welds vol.19, pp.1, 2014, https://doi.org/10.14775/ksmpe.2020.19.01.043