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.