에너지공학 (Journal of Energy Engineering)

  • 제25권1호
  • /
  • Pages.153-162
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  • 2016
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  • 1598-7981(pISSN)
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  • 2713-7074(eISSN)
한국에너지학회 (The Korean Society for Energy)
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좁은 사각 유로 내 하향류 유동 조건에서 임계열유속 실험 연구

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

  • Kim, Hui Yung (School of Mechanical Engineering, Pusan National University) ;
  • Yun, Byong Jo (School of Mechanical Engineering, Pusan National University) ;
  • Bak, Jin Yeong (School of Mechanical Engineering, Pusan National University) ;
  • Park, Jong Hark (Korea Atomic Energy Research Institute(KAERI)) ;
  • Chae, Heetaek (Korea Atomic Energy Research Institute(KAERI)) ;
  • Park, Cheol (Korea Atomic Energy Research Institute(KAERI))
  • 투고 : 2015.08.10
  • 심사 : 2015.12.30
  • 발행 : 2016.03.31
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초록

요르단 수출용 연구용 원자로(JRTR, Jordan Research and Training Reactor)에 사용되는 판형핵연료(Plate-type-fuel)의 부수로를 모의하는 좁은 사각 유로에서 하향류 유동 조건의 임계열유속(CHF, Critical Heat Flux) 실험 연구가 수행되었다. 실험은 연구용 원자로 인허가 요건을 만족하는 유동 조건에서 수행되었으며 크기가 다른 두 가지 시험부를 이용하였다. 두 시험부는 각각 피션몰리(Fission moly) 우라늄 타겟의 부수로와 판형핵연료의 부수로를 모의하며 모두 원형과 같은 크기로 제작되었다. 각 시험부에 대해 임계열유속 실험이 수행되었으며 이를 통해 임계열유속에 영향을 주는 변수를 분석하였다. 그리고 실험결과를 기존의 임계열유속 모델과 비교하였으며 모델의 예측 정확도를 제시하였다. 이를 통해 좁은 사각 유로 내 하향류 유동 조건에서의 임계열유속 예측에 대한 기존 모델의 적용성을 분석하였다.

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.

키워드

참고문헌

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