Host: The Japan Society of Mechanical Engineers
Name : [in Japanese]
Date : June 16, 2016 - June 17, 2016
Ex-vessel cooling is an important subject in the field of nuclear safety so that many researchers focus on CHF (critical heat flux) enhancement study of pressure vessel reactor. In this study, pool boiling experiment is carried out to test CHF value. Meanwhile, a new structure design, honeycomb plate, is introduced for enhancement study of CHF. During experiment, different kind of plates are utilized. It is found that CHF can be enhanced after using honeycomb structure. Also, porous plate can further increase CHF compared with solid plate.
