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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.
Kato, Keisuke*; Narabayashi, Tadashi*; Yoshida, Atsuro*; Arae, Kunihiko*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
There is a need for quantitative evaluation of wastage phenomena in steam generator for FBR. We focused attention on liquid droplet impingement erosion (LDIE) in wastage phenomena and performed basic study with piping group mock up specimen for quantitative evaluation of LDIE. First, we did visualization test of high pressure and high speed jet into the water. Test section mock up the crack of heat exchanger tube and neighboring heat exchanger tubes. We did the test under the following test conditions. Upstream pressure is 0.3 MPa, vapor temperature is 300 K, crack width is 0.1 mm, and crack length is 40 mm. (crack diameter is 0.2 mm) Second, we did pressure and temperature measurement test in the same test conditions as before. We evaluated jet behavior at test section by those two tests. In addition, we did two phase flow analysis of the jet with TRAC code.
Arae, Kunihiko*; Yoshida, Atsuro*; William, K.*; Narabayashi, Tadashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
In a Sodium-cooled Fast Reactor (SFR), liquid sodium is used as heat transfer fluid to carry the energy from the reactor core to the steam generator (SG). In case of a SG tube failure, a defect occurring on a heat transfer tube will cause the high-pressure and high-velocity water steam to spout onto the low-pressure liquid sodium filling in the space around the tube, to initiate sodium-water reaction. The steam outflow (water, sodium and sodium hydroxide) of the reaction would impinge on neighboring tube to cause erosion/corrosion, which might lead to a secondary failure. In this study, relations between several parameters and erosion rate of Mod.9Cr-1Mo in anticipated sodium-water reaction conditions were evaluated.
Arae, Kunihiko*; Narabayashi, Tadashi*; Kato, Keisuke*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
Adjacent tube wastage may occur due to sodium-water reaction in steam generator of sodium-cooled fast reactor. In this report, the authors evaluated the effect of material hardness, droplet impinging velocity and occurrence time on erosion rate, and estimated the thinning rate for Mod.9Cr-1Mo steel due to erosion which is an influencing factor on wastage.
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.
Kato, Keisuke*; Arae, Kunihiko*; Narabayashi, Tadashi*; Tsuji, Masashi*; Chiba, Go*; Ohshima, Hiroyuki; Kurihara, Akikazu; Uchibori, Akihiro
no journal, ,
The authors have carried out the visualization test of two-phase jet behavior using piping array mock-up test rig to clarify the wastage phenomena in steam generator in sodium-cooled fast reactor.
Arae, Kunihiko*; William, K.*; Narabayashi, Tadashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
Sodium-water reaction in steam generator of sodium-cooled fast reactor may cause erosion on adjacent tubes. The authors made a study of the effects of Vickers hardness on tube and the initiation time on erosion.
Kato, Keisuke*; Arae, Kunihiko*; Narabayashi, Tadashi*; Ohshima, Hiroyuki; Kurihara, Akikazu
no journal, ,
The authors measured the behavior of water/steam two-phase jet in water under high-temperature and high-pressure conditions to evaluate quantitatively the effect of liquid droplet impingement erosion (LDIE) on target-wastage in case of sodium-water reaction in steam generator of sodium-cooled fast reactor.