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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.
William, K.*; Higashi, Yuma*; Narabayashi, Tadashi*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
In a steam generator (SG) of sodium-cooled fast reactors, sodium and water are separated only by the wall of the heat-transfer tube. In case of tube failure such as a defect penetrating through the heat-transfer tube, it will cause high-pressure water/steam to spout into the low-pressure sodium filling outside the tube, to initiate sodium-water reaction accompanied by high heat generation. The result is a steam outflow of the reaction that might erodes/corrodes the tube wall. While the reaction steam outflow remains unterminated, it would impinge on neighboring tubes to cause their erosion/corrosion, and eventual failure. Such phenomenon of overheating tube rupture presents a serious problem to the safety of steam generator. This study is to evaluate the wastage rate of SG heat-transfer tube caused by liquid droplet impingement erosion (LDIE).
Yoshida, Atsuro*; Higashi, Yuma*; William, K.*; Arae, Kunihiko*; Narabayashi, Tadashi*; Tsuji, Masashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
It may occur heat transfer tube failure event in steam generator of sodium-cooled fast reactor. Sodium reacts vigorously with water in the case of water leakage into sodium, the neighboring tubes are damaged by sodium-water reaction jet, tube wastage could arise from the effect of erosion and corrosion. The wastage phenomena remains to be fully elucidated by its complexity. In this study, the authors carried out the measurement experiment of temperature and pressure distribution in two-phase free jet and analyzed the wastage quantitatively from the standpoint of erosion effect.
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.