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Yoshida, Atsuro*; Higashi, Yuma*; Narabayashi, Tadashi*; Khoo Chong Weng, W.*; Arae, Kunihiko*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 8 Pages, 2011/10
One of the design basis accidents in sodium-cooled fast reactor is sodium-water reaction at steam generator (SG). In case of a defect occurred on a heat transfer tube, the high-pressure water/vapor will spout into the low-pressure sodium surrounding outside the tube. As sodium is ordinarily quite reactive with water, this will initiate sodium-water reactions accompanied by high chemical heat generation. The liquid droplet in the reaction steam outflow would impinge on neighboring tubes to cause erosion, while the chemical reaction will cause corrosion, eventually may lead to secondary tube failure. Focusing on the erosion part, this study is to evaluate the liquid droplet impingement erosion (LDIE) rate on neighboring tubes caused by SG heat transfer tube rupture. In this paper, as a basic study, the pressure and temperature distribution of high -pressure two-phase free jet into the air is measured.
Yoshida, Atsuro*; Khoo Chong Weng, W.*; Narabayashi, Tadashi*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
no abstracts in English
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.