Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Zhang, H.*; Umehara, Yutaro*; Yoshida, Hiroyuki; Mori, Shoji*
International Journal of Heat and Mass Transfer, 218, p.124750_1 - 124750_11, 2024/01
Times Cited Count:8 Percentile:75.43(Thermodynamics)Zhang, H.*; Umehara, Yutaro*; Yoshida, Hiroyuki; Mori, Shoji*
International Journal of Heat and Mass Transfer, 211, p.124253_1 - 124253_13, 2023/09
Times Cited Count:10 Percentile:79.03(Thermodynamics)Abe, Yutaka*; Nishi, Yoshihisa*; Iwaki, Chikako*; Umehara, Yutaro*; Horiguchi, Naoki; Sonoda, Hiroki*
no journal, ,
Human resource development is an important issue in the nuclear field, and it is extremely important to transfer the know-how of veteran researchers who have accumulated over many years in the research field to the younger generation. In the field of reactor safety research in particular, the research environment has been changing in recent years, as it has become more difficult to conduct research using large experimental equipment, and many young researchers are finding the difficulty. This session will provide a forum in the form of a "round-table discussion" to discuss what veteran researchers want to tell young researchers and what young researchers want to ask veteran researchers. Through the panel discussion, communication between veteran researchers and young researchers about the future in the field will be promoted.
Zhang, H.*; Umehara, Yutaro*; Mori, Shoji*; Horiguchi, Naoki; Yoshida, Hiroyuki
no journal, ,
Due to the operating conditions of BWRs (285C and 7 MPa), the direct visualization and detailed liquid film measurement of steam-water annular flow in BWRs have been highly challenging. This study addresses this limitation by developing a novel HFC134a-ethanol annular flow system at lower temperature and pressure (40
C and 0.7 MPa), simulating the steam-water annular flow under BWR conditions. The experiments of HFC134a-ethanol upward annular flow were conducted in a 5 mm inner diameter tube using the constant electric current method, and we obtained the flow characteristics including base, average, and maximum film thickness and the height of disturbance wave.
Mori, Shoji*; Zhang, H.*; Umehara, Yutaro*; Horiguchi, Naoki; Yoshida, Hiroyuki
no journal, ,
To ensure nuclear safety, understanding of liquid film behavior of annular flow like flow near fuel rods in BWRs is important. It is hard to experimentally obtain thin liquid behavior in BWRs because of technical limits under the high pressure and temperature, 7MPa and 285C, and to understand the behavior sufficiently. Therefore, in this study, liquid film behavior under the actual condition was reproduced using ethanol-HFC134a system at 0.7MPa and 40
C such as a university laboratory, which has almost same physical properties with the actual water-vapor system. In addition, the liquid film behavior was measured using the constant electric current method, and the measurable range and accuracy of the method were examined.