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Development of Coolant Flow Simulation System for Nuclear Fuel Test Rigs

핵연료조사리그 냉각수 유동 모의장치 개발

  • Hong, Jintae (Dept. of Research Reactor Applications, Korea Atomic Energy Research Institute) ;
  • Joung, Chang-Young (Dept. of Research Reactor Applications, Korea Atomic Energy Research Institute) ;
  • Heo, Sung-Ho (Dept. of Research Reactor Applications, Korea Atomic Energy Research Institute) ;
  • Kim, Ka-Hye (Dept. of Research Reactor Applications, Korea Atomic Energy Research Institute)
  • 홍진태 (한국원자력연구원 하나로이용연구본부) ;
  • 정창용 (한국원자력연구원 하나로이용연구본부) ;
  • 허성호 (한국원자력연구원 하나로이용연구본부) ;
  • 김가혜 (한국원자력연구원 하나로이용연구본부)
  • Received : 2014.09.05
  • Accepted : 2014.10.16
  • Published : 2015.01.01

Abstract

To remove heat generated during a burn-up test of nuclear fuels, the heat generation rate of nuclear fuels should be calculated accurately, and a coolant should be circulated in the test loop at an adequate flow rate. HANARO is an open pool-type reactor with an independent test loop for the burn-up test of nuclear fuels. A test rig is installed in the test loop, and a coolant is circulated through the test loop to maintain the temperature of the nuclear fuel rods within a desired temperature during an irradiation test. The components and sensors in the test rig can be broken or malfunction owing to the flow-induced vibration. In this study, a coolant flow simulation system was developed to verify and confirm the soundness of components and sensors assembled in the test rig with a high flow rate of the coolant.

핵연료 연소시험 도중 핵연료봉에서 발생하는 열을 효과적으로 제거하기 위해서는 핵연료의 발열량을 정확하게 계산하고 충분한 유속을 갖는 냉각수를 순환시켜야 한다. 하나로는 개방형 수조 형태로서 핵연료 연소시험을 위한 별도의 냉각수 순환 루프를 갖추고 있는데, 여기에 핵연료 조사리그를 장착하고 냉각수를 순환시킴으로써 조사중인 핵연료봉의 온도를 일정온도 이하로 유지시킨다. 특히 순환되는 냉각수의 유속이 매우 높은 상태에서 조사리그 내에 부착된 부품이나 센서들이 유체유발 진동에 의해 파손되거나 기능을 상실하는 경우 매우 큰 기회비용을 야기한다. 본 연구에서는 조사리그 부품의 건전성 사전 검토 및 고속 유동에서의 센서 동작 특성에 대한 사전검토를 위해 냉각수 모의 순환장치를 개발하였다.

Keywords

References

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Cited by

  1. Measurement of coolant flow in a nuclear fuel test rig vol.16, pp.9, 2015, https://doi.org/10.1007/s12541-015-0259-y
  2. Study on the measurement accuracy of coolant flowrate in a nuclear fuel test rig vol.17, pp.10, 2016, https://doi.org/10.1007/s12541-016-0165-y