T. Narabayashi
Toshiba Corporation, Nuclear Engineering Laboratory, Kawasaki, Kanagawa; and Hokkaido University, Kita 13, Nishi 8, Kita-ku, Sapporo, Japan
Shinichi Morooka
Toshiba Corporation, Nuclear Engineering Laboratory, Yokohama, Kanagawa, Japan
T. Kagawa
Tokyo Institute of Technology, Nuclear Engineering Laboratory, Toshiba Corporation, Japan
T. Ishizuka
Nuclear Engineering Laboratory, Toshiba Corporation, Japan
A. Hoshide
Nuclear Engineering Laboratory, Toshiba Corporation, Japan
T. Ishiyama
Nuclear Engineering Laboratory, Toshiba Corporation, Japan
To improve the accuracy of BWR fuel design and safety evaluation, it is necessary to obtain a better understanding of high pressure two-phase flow phenomena. For this purpose, the authors developed a new two-phase measurement apparatus using X-ray beam scanning and X-ray CT (Computed Tomography) scanner methods, and measured the high pressure steam-water two-phase phenomena in a horizontal tube and a simulated BWR fuel rod bundle.
X-ray beam scanning and X-ray CT scanning showed the effectiveness of measuring the transient two-phase phenomena, as well as the local void distribution in the complicated flow channel.
These new two-phase flow measurement methods can also be used to visualize two-phase flow phenomena under high pressure conditions.