Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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A TEST VERIFIED MODEL DEVELOPMENT STUDY FOR A NUCLEAR WATER CHILLER USING THE SEISMIC QUALIFICATION ANALYSIS AND TEST

  • Sur, Uk-Hwan (School of Mechanical and Automotive Engineering, Halla University)
  • Received : 2011.01.18
  • Accepted : 2011.03.11
  • Published : 2011.08.31
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Abstract

This paper is a study on a nuclear water chiller. It presents a test-verified finite element model of a water chiller to be used at a Nuclear Power Plant. The test-verified model predicts natural frequencies within 5% for all major modes below 50 Hz. This model accurately represents the dynamic characteristics of the actual hardware and is qualified for its use in the final stress analysis for seismic verification.

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References

  1. Wyle Laboratories' Report No. 41380, Seismic Analysis of Water Chiller Beaver Valley Nuclear Power Station in U.S.A., (1991).
  2. ASME Boiler and Pressure Vessel Code, Section III, (1986).
  3. AISC Steel and Construction Manual, (1990).
  4. COSMOSM user's manual, Structural Research and Analysis Corporation, Santa Monica, California, (1990).
  5. Roark, Raymond J., and Warren C. Young, Formulas for Stress and Strain, 5th Ed., McGraw Hill, (1990)
  6. ASHRAE Handbook, Fundamental, (1981).
  7. Incropera, Frank P., and David P. Dewitt, Fundamentals of Heat and Mass Transfer, 2nd Ed., John Wiley and Sons, (1992).

Cited by

  1. Frequency Analysis of the Motor Control Centers in a Nuclear Power Plant Using Testing and Simulating Methods vol.479-480, pp.1662-7482, 2013, https://doi.org/10.4028/www.scientific.net/AMM.479-480.1045