페이지 정보2017.02.07 / 665
As one of a key phenomenon in thermal hydraulics
system, nucleate boiling has been widely studied by numerous researchers to
improve efficiency and safety of the system (i.e, nuclear power plant,
refrigerating system etc.). In general, the evaluation of the boiling
performance mainly focus on two physical parameters: boiling heat transfer
(BHT) and critical heat flux (CHF). Since both BHT and CHF contribute the
thermal system efficiency and safety, respectively many new approaches to
enhance the boiling performance compared to the conventional methodology have
been investigated. We study the boiling phenomena and its performance
enhancement using pool boiling experiments, which is the most fundamental
approach of the boiling study.
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