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단면 열속부하된 Hypervapotron 냉각채널의 과냉비등상황 임계열유속 실험적 연구
임지환(Ji Hwan Lim),박민규(Min Gyu Park),오훈교(Hun Gyo Oh),황돈관(Don Koan Hwang),김무환(Moo Hwan Kim),조항진(Hang Jin Jo) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
In Korea, KSTAR’s tokamak long-time operation technique has reached 70 seconds in 2016, and steady-state plasma control technique is estimated to reach world-class level. However, the lack of cooling capacity to maintain the thermal steady state of the tokamak is becoming a severe engineering problem in preparation for K-DEMO. To simulate the fusion thermal condition, a test loop was constructed to withstand high temperature (150℃) and high pressure (20 bar). Through this loop, CHF experiments were carried out for the Hypervapotron channel and the results were compared with Baxi Hypervapotron CHF correlation. But, a high error average of 173.46% was found, and the Ja number index was changed to 0.45 in consideration of the 10 bar pressure to enable a reasonable prediction of 6.85% lower error. If CHF modeling and verification test is performed later, it will be possible to predict CHF over a wider range.