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Kabasawa, Satsuki; Sakamoto, Michihito*; Takahashi, Yuta; Yamaguchi, Masaaki
no journal, ,
no abstracts in English
Okita, Shoichiro
no journal, ,
no abstracts in English
Okada, Jumpei
no journal, ,
no abstracts in English
Kodama, Yu; Lee, J.; Hironaka, Kota; Rossi, F.; Koizumi, Mitsuo; Hori, Junichi*; Terada, Kazushi*; Sano, Tadafumi*
no journal, ,
no abstracts in English
Nagaoka, Kosuke
no journal, ,
no abstracts in English
Kosaka, Wataru; Uchibori, Akihiro; Yanagisawa, Hideki*; Okano, Yasushi
no journal, ,
no abstracts in English
Sato, Kuri
no journal, ,
no abstracts in English
Kobayashi, Kenji; Ishii, Tatsuya; Tsubota, Yoichi; Shioya, Satoshi; Ishibashi, Nauya; Nakagawa, Takahiro
no journal, ,
no abstracts in English
Ishii, Tatsuya; Kobayashi, Kenji; Tsubota, Yoichi; Shioya, Satoshi; Ishibashi, Nauya; Nakagawa, Takahiro
no journal, ,
no abstracts in English
Kato, Tatsuki; Hirato, Misaki; Matsuo, Kazuki; Takahashi, Akina; Tamura, Ken; Nagaoka, Mika; Yamazaki, Takumi; Nakagawa, Takahiro
no journal, ,
no abstracts in English
Sonehara, Masateru; Okano, Yasushi; Uchibori, Akihiro; Oki, Hiroshi*
no journal, ,
In the development of sodium-cooled fast reactors, it is important to understand the combustion behavior in sodium leak accidents. In this study, the multidimensional thermal fluid analysis code AQUA-SF was applied to the numerical simulation of the large-scale combustion test (so-called the T3 test) with accounting characteristic event progressions (temporary stop of combustion, droplet splash on the floor).
Nagai, Yuya
no journal, ,
no abstracts in English
Nakagawa, Takuya; Yamamoto, Keisuke; Suguro, Toshiyasu; Sone, Tomoyuki
no journal, ,
no abstracts in English
Shimojo, Hiroto; Miura, Daiya; Okadome, Yoshihiro; Sone, Tomoyuki
no journal, ,
no abstracts in English
Matsushita, Kentaro; Ezure, Toshiki; Imai, Yasutomo*; Fujisaki, Tatsuya*; Tanaka, Masaaki
no journal, ,
In sodium-cooled fast reactors, the cover gas is entrained into the coolant due to the dimple vortices generated in the free surface in the upper plenum of the reactor vessel, and gas entrainment (GE) phenomenon may affect core behavior. It is necessary to develop evaluation methods of GE phenomenon. In this study, a GE evaluation model, PVL model (Pressure Vortex Line model) was constructed. The PVL model includes the identification of vortex center lines from the flow velocity distribution obtained by 3-D analysis, the calculation of the 3-D distribution of pressure decrease along the vortex center line and the evaluation of gas core length of vortex by comparing the pressure decrease and the hydrostatic pressure. The PVL model was applied to the analysis results of advective vortex experiments in a rectangular channel system to evaluate GE. As the result, it was confirmed that it was possible to judge the GE occurrence of advective vortices by the application of PVL model.