대한기계학회논문집B (Transactions of the Korean Society of Mechanical Engineers B)

  • 제33권6호
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  • Pages.418-426
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  • 2009
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  • 1226-4881(pISSN)
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  • 2288-5324(eISSN)
대한기계학회 (The Korean Society of Mechanical Engineers)
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펌프 회전차의 관성모멘트 제공에 의한 KALIMER-600 원자로 풀 과도 성능 분석

Transient Performance Analysis of the Reactor Pool in KALIMER-600 with an Inertia Moment of a Pump Flywheel

  • 발행 : 2009.06.01
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초록

The effect of an inertia moment of a pump flywheel on the thermal-hydraulic behaviors of the KALIMER-600(Korea Advanced LIquid MEtal Reactor) reactor pool during an early-phase of a loss of normal heat sink accident was investigated. The thermal-hydraulic analyses for a steady and a transient state were made by using the COMMIX-1AR/P code. In the present analysis a quarter of the reactor geometry was modeled in a cylindrical coordinate system, which includes a quarter of a reactor core and a UIS, a half of a DHX and a pump and a full IHX. In order to evaluate the effects of an inertia moment of the pump flywheel, a coastdown flow whose flow halving time amounts to 3.69 seconds was supplied to a natural circulation flow in the reactor vessel. Thermal-hydraulic behaviors in the reactor vessel were compared to those without the flywheel equipment. The numerical results showed a good agreement with the design values in a steady state. It was found that the inertia moment contributes to an increase in the circulation flow rate during the first 40 seconds, however to a decrease of it there after. It was also found that the flow stagnant region induced by a core exit overcooling decelerated the flow rate. The appearance of the first-peak temperature was delayed by the flow coastdown during the initial stages after a reactor trip.

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참고문헌

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피인용 문헌

  1. vol.13, pp.1, 2010, https://doi.org/10.5293/KFMA.2010.13.1.052
  2. Analysis of Transient Performance of KALIMER-600 Reactor Pool by Changing the Elevation of Intermediate Heat Exchanger vol.34, pp.11, 2010, https://doi.org/10.3795/KSME-B.2010.34.11.991