Journal of the Korean Society of Manufacturing Process Engineers (한국기계가공학회지)

The Korean Society of Manufacturing Process Engineers (한국기계가공학회)
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A Study on the Structural Integrity of an Auxiliary Feed Water Pump in a Nuclear Power Plant

원자력 발전소 보조급수펌프의 구조 건전성에 관한 연구

  • Kim, Chae-Sil (Department of Mechanical Engineering, Changwon National University) ;
  • Cho, Bang-Hyun (Advanced automotive battery validation team, LG Chem. Ltd.)
  • Received : 2014.06.19
  • Accepted : 2014.06.26
  • Published : 2014.06.30
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Abstract

The auxiliary-feed-water pump (AFWP) used to supply water during a station black out situation at nuclear power plants should meet the seismic qualification regulations stipulated in IEEE Std 323 and 344, so as to withstand earthquakes or dangerous situations. Here, we establish a model for the estimation of the structural integrity of this type of pump. If the natural frequency that results from a modal analysis is less than 33 Hz, we adopt a dynamic analysis, instead of a static analysis. A dynamic analysis was carried out taking into consideration seismic conditions such as the floor response spectra (FRS), an operation-base earthquake (OBE), and a safe-shutdown earthquake (SSE). Finally, an analytical estimation of the structural integrity of an AFWP is made through a comparison of calculated values and allowable values. If the result is less than the allowable stress, the pump is deemed to have good structural integrity. In addition, future studies will involve a stability check for rotor accidents that may occur during the operation of the pump.

Keywords

References

  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 Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, Class 1, 2 and 3, 2007 Edition with 2009 Addenda.
  4. ASME OM Code, Code for Operation and Maintenance of Nuclear Power Plants, 2007 Edition with 2009 Addenda.
  5. Andrew D. Dimarogonas, Vibration for Engineers, Prentis Hall, pp. 127-137, 1996.
  6. Jung H. H., Cho B. H., Kim C. S. and Choi H. O., A Study on the Analytical Estimation of Structural Health for A Main Control Board in Nuclear Power Plant, Proceedings of the KSPE Conference, pp. 1091-1092, 2012.
  7. Jo H. M., A Study on the Design of Tilting Pad Journal Bearing Considering the Rotor Stability, Master's Thesis, Mechanical Engineering, Changwon National Univ., 2010.
  8. Churl Yoon, Jin hee Park, Mee jeong Hwang and Sang Hoon Han, Heat-up Calculation for the Auxiliary Feed Water Pump Room at Ulchin Units 3 and 4 for Loss of HVAC Accidents, Transactions of the Korean society of mechanical engineers. B. B., Vol. 36, No. 5 , pp. 553-562, 2012. https://doi.org/10.3795/KSME-B.2012.36.5.553
  9. Byeon Hoon Seok. and Lee Joon Keun, Seismic Qualification of the Main Control Board for Nuclear Power Plant, Transactions of the Korean Society for Noise and Vibration Engineering, Vol. 12, issue 11, pp. 856-863, 2002. https://doi.org/10.5050/KSNVN.2002.12.11.856
  10. Cho B. H., A Study on the Safety for Motor Driven Ausiliary Feedwater Pump in a Nuclear Power Plant, Master's Thesis, Mechanical Engineering, Changwon National Univ., 2013.