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Kato, Masatsugu*; Funakoshi, Kanji*; Liu, X.*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji
Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 7 Pages, 2018/11
Yamauchi, Toshiya*; Ogawa, Ryusei*; Kato, Masatsugu*; Liu, X.*; Matsumoto, Tatsuya*; Morita, Koji*; Kamiyama, Kenji; Suzuki, Toru
no journal, ,
no abstracts in English
Ogawa, Ryusei*; Yamauchi, Toshiya*; Kato, Masatsugu*; Liu, X.*; Matsumoto, Tatsuya*; Morita, Koji*; Kamiyama, Kenji; Suzuki, Toru
no journal, ,
no abstracts in English
Kato, Masatsugu*; Ogawa, Ryusei*; Funakoshi, Kanji*; Liu, X.*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji
no journal, ,
no abstracts in English
Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji
no journal, ,
In order to eliminate the energetic potential in the case of postulated core-disruptive accidents (CDAs) of sodium-cooled fast reactors, introduction of a fuel subassembly with an inner-duct structure (FAIDUS) has been proposed. In the present study, to demonstrate a function for early fuel discharge, analytical study using three-dimensional particle-based simulations were performed against a series of multi-component, multi-phase thermal hydraulics phenomena, which are formation of molten pool of fuel and steel mixture caused by disruption of fuel pins, and, heat-transfer from the pool to duct wall.
Sakaguchi, Kazuya*; Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji
no journal, ,
no abstracts in English
Sakaguchi, Kazuya*; Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji
no journal, ,
no abstracts in English