Experimental Investigation of the CHF for the Narrow Rectangular Channel in the Downward Flow

좁은 사각 유로 내 하향류 유동 조건에서 임계열유속 실험 연구

  • Received : 2015.08.10
  • Accepted : 2015.12.30
  • Published : 2016.03.31


Experimental investigation was carried out on the CHF(Critical Heat Flux) under downward flow condition in narrow rectangular channels simulating subchannel of plate-type-fuel for JRTR(Jordan Research and Training Reactor). The experiments covers the license requirement of the research reactor. Two test sections used in this study simulate full scale subchannels for fission moly uranium target and plate-type-fuel, respectively. From the experimental results, the parameters affecting on the CHF are investigated. By using experimental data, the existing CHF prediction models were evaluated. Finally, the applicability of correlations were analysed to predict CHF in the narrow rectangular channel under the downward flow condition.


research reactor;critical heat flux;downward flow;narrow rectangular channel


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Supported by : 한국연구재단, 한국원자력안전재단