http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
Hypervapotron 냉각 채널 적용을 위한 텅스텐 모노블락 형태의디버터 플라즈마 대면체의 열기계적 설계 및 평가
오훈교(Hoongyo Oh),김무환(Moo Hwan Kim),조항진(HangJin Jo) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
Divertor is the main part expected to load about 10 ㎿/m^2 high heat flux in fusion reactor system. Plasma facing components include cooling channel extracting heat, armour protecting the cooling channel and interlayer connecting them. Armour in divertor vertical target has been designed as a monobolock type rather than a flat tile type because of plasma behavior, but detail channel configuration has not been decided. In this study, based on hypervapotron cooling capability for high critical heat flux with low pressure drop, new type plasma facing components with hypervapotron cooling channel are designed. Thermomechanical analysis is conducted with this new designs, and then the designs are evaluated by the Monoblock Elastic Analysis Procedure (MEAP) Rule.
과냉각 유동비등 조건에서 평가된 사각 히트싱크의 유동 불안정 시작점
임지환(Ji Hwan Lim),오훈교(Hoongyo Oh),박민규(Minkyu Park),이수원(Su Won Lee),황돈관(Donkoan Hwang),김무환(Moo Hwan Kim),조항진(HangJin Jo) 대한기계학회 2021 대한기계학회 춘추학술대회 Vol.2021 No.11
Onset of flow instability (OFI), a phenomenon that rapidly fluctuates the system due to the generation of many vapors inside the heat sink, is a major threat to the operation of the cooling system. However, studies evaluating OFI under one-side high heat load conditions are very scarce. Therefore, in this study, the OFI of a rectangular heat sink was investigated through a sub-cooled flow boiling experiment. In addition, the effects of pressure, flow, and sub-cooling on OFI heat flux were analyzed. Finally, the accuracy of OFI correlations developed under the existing sub-cooled flow boiling condition was evaluated. Unfortunately, the existing correlations showed a high error rate because they were developed based on mini or micro-channel. This shows the need to develop a new correlation suitable for one-side high heat load conditions.
과냉유동비등 상황에서의 직사각형 채널의 비등시작점에 대한 실험적 연구
임지환(Ji Hwan Lim),이수원(Su Won Lee),오훈교(Hoongyo Oh),박민규(Minkyu Park),황돈관(Donkoan Hwang),김무환(Moo Hwan Kim),조항진(HangJin Jo) 대한기계학회 2021 대한기계학회 춘추학술대회 Vol.2021 No.11
The cooling system of a fusion power plant is safe to operate in single-phase to avoid flow instability due to vapour or reaching a potential critical heat flux. However, there are very few cases of experimental evaluation of onset of nucleate boiling (ONB) under one-side high heat load conditions inside the tokamak. Therefore, ONB of a rectangular channel was evaluated under one-side heating condition. As a result of analyzing the effect of system parameters on ONB heat flux, it was confirmed that ONB heat flux had a proportional relationship with flow and sub-cooling, and an inverse relationship with pressure. In addition, as a result of evaluating various types of ONB correlations, it was difficult to find correlations that predict ONB with high accuracy under one-side high heat load conditions. This proves that it is essential to develop a new ONB correlation for application to the tokamak cooling system.