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Operating Vibration Measurements of Test Fuel Assembly in Reactor Thermo-hydraulic Test Condition

  • Kang-Hee Lee
  • Chang-Hwan Shin
  • Heung-Seok Kang
  • Dong-Seok Oh
  • Nam-Kyu Park
Conference paper
Part of the Conference Proceedings of the Society for Experimental Mechanics Series book series (CPSEMS)

Abstract

The design verification of a newly-developed nuclear fuel assembly requires a long-term endurance test under thermo-hydraulic test condition simulating power reactor core. For this verification test, vibration of the test fuel assembly inside the simulated test core should be measured under high system temperature (over 200 °C), high system pressure (over 2.5 MPa) and fast moving coolant flow (over 5 m/s). To measure the vibration, we use specially fabricated accelerometers, various sealing techniques and conduit channel design for signal cable protection. The effects of the flow rate, coolant temperature, pre-sized support clearance on the test fuel vibration response and orbit motion were discussed. The measured data is used for fuel compatibility evaluation and a basis for endurance verification, as well as the validation tool for theoretical response prediction model.

Keywords

Response Spectrum Fuel Assembly High System Pressure Verification Test Test Fuel 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Reference

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Copyright information

© Springer Science + Business Media, LLC 2011

Authors and Affiliations

  • Kang-Hee Lee
    • 1
  • Chang-Hwan Shin
    • 1
  • Heung-Seok Kang
    • 1
  • Dong-Seok Oh
    • 1
  • Nam-Kyu Park
    • 2
  1. 1.Innovative Nuclear Fuel DivisionKorea Atomic Energy Research InstituteDaejeonKorea
  2. 2.KEPCO Nuclear FuelNuclear Fuel Design GroupDaejeonKorea

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