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Yoshida, Atsuro*; Khoo Chong Weng, W.*; Narabayashi, Tadashi*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
Basic research has been carried out to clarify the wastage phenomena due to tube failure of steam generator in sodium-cooled fast reactor. The authors report the pressure distribution in two-phase free jet under high temperature and high pressure conditions measured by traverse survey.
Khoo Chong Weng, W.*; Higashi, Yuma*; Narabayashi, Tadashi*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
In a steam generator of sodium-cooled fast reactor, in case of small reacting jet development, a deterioration of neighboring tube is caused mainly by erosion-corrosion. This study is carried out to evaluate the thinning rate of SG heat transfer tube material caused by liquid droplet impingement erosion using high speed rotating disc test rig.
Noguchi, Yuhei*; Kudo, Hideyuki*; Ota, Junki*; Sugiyama, Kenichiro*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
As the final goal to understand the sodium-water reaction phenomena of steam generator in sodium-cooled fast reactor, we observed directly the colliding behavior of inactive gas jet in sodium from inside a single glass cylinder. And we calculated the void fraction from the frame due to the high speed video camera, and compared with the value measured by void sensor.