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[국내논문] 원자력 발전소 보조급수펌프의 구조 건전성에 관한 연구
A Study on the Structural Integrity of an Auxiliary Feed Water Pump in a Nuclear Power Plant 원문보기

한국기계가공학회지 = Journal of the Korean Society of Manufacturing Process Engineers, v.13 no.3, 2014년, pp.42 - 48  

김재실 (창원대학교) ,  조방현 ((주)LG화학 자동차전지 평가팀)

Abstract ▼ AI-Helper 아이콘AI-Helper

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 esti...

주제어

#Auxiliary Feed Water Pump (AFWP)   #Nuclear Power Plant   #Structural Integrity   #Analytical Estimation  

AI 본문요약
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제안 방법

  • A response spectrum analysis using ANSYS was performed. It may be that resonance is possible in the spectral data (seismic waves) because the mode analysis results represent that a first mode exists within 33Hz.
  • A rotor analysis for the rotating part was performed to verify that an AFWP meet the dynamic design requirements. To verify the stability of the rotor system, advanced rotating machinery dynamics (ARMD) modeling and analysis were used.
  • A dynamic analysis was performed taking into consideration seismic conditions such as OBE, and SSE. Finally, an analytical estimation of the structural integrity of an AFWP is performed by making a comparison of the calculated value and the allowable value. Therefore, it was confirmed that an AFWP has sufficienct structural integrity for earthquake loads.
  • Therefore, a comprehensive study is needed on the safety of the pump shaft and the seismic safety verification of a AFWP. In this paper, a three-dimensional finite element model was constructed using ANSYS in order to verify the structural integrity of an AFWP of a nuclear power plant for earthquake load conditions. If a first natural frequency as a result of the mode analysis is greater than 33Hz, static analysis will be performed.
  • 2. The rotor analysis was implemented to investigate the natural frequencies and mode shapes of the AFWP. The fundamental mode of an AFWP was found to be above 33Hz, which is not in the seismic range.
  • A three dimensional model was constructed of an AFWP using a commercial finite element analysis program, ANSYS. Work was done to simplify as much as possible the parts needed for the analysis of the modeling, which consists of pumps, motors, and base. Figure 5 represents the completed finite element model of a AFWP.

대상 데이터

  • Otherwise, the material property of the SA-36 was applied. A Shell63 element and multi-point constraint 184 (MPC184) elements were used for modeling. The shell63 element has six degrees of freedom at each 4 nodes: translations in the nodal x, y, and z directions and rotations about the nodal x, y, and z-axes.
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참고문헌 (10)

  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. 

    원문보기 상세보기 crossref

  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. 

    원문보기 상세보기 crossref

  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. 

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