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Takase, Kazuyuki; Yoshida, Hiroyuki; Akimoto, Hajime; Ose, Yasuo*
Nihon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.231 - 232, 2005/08
no abstracts in English
Takase, Kazuyuki; Ose, Yasuo*; Yoshida, Hiroyuki; Akimoto, Hajime; Aoki, Takayuki*
Kashika Joho Gakkai-Shi, 25(Suppl.1), p.435 - 436, 2005/07
no abstracts in English
Takase, Kazuyuki
Nihon Kikai Gakkai Ryutai Kogaku Bumon Nyuzu Reta Nagare (Internet), 6 Pages, 2005/04
no abstracts in English
Ose, Yasuo*; Takase, Kazuyuki; Yoshida, Hiroyuki
Proceedings of 1st International Forum on Heat Transfer (IFHT 2004), p.199 - 200, 2004/11
no abstracts in English
Ose, Yasuo*; Takase, Kazuyuki; Yoshida, Hiroyuki; Kano, Takuma; Kureta, Masatoshi; Akimoto, Hajime
Dai-41-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, 2 Pages, 2004/05
no abstracts in English
Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*
Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.6, p.205 - 206, 2003/00
no abstracts in English
Ose, Yasuo*; Suzuki, Takayuki*; Yoshida, Hiroyuki; Takase, Kazuyuki; Kunugi, Tomoaki*
Nihon Kikai Gakkai Yamanashi Koenkai Koen Rombunshu (020-4), p.51 - 52, 2002/00
no abstracts in English
Kurihara, Ryoichi; Ajima, Toshio*; Ueda, Shuzo; Seki, Yasushi
Journal of Nuclear Science and Technology, 38(7), p.571 - 576, 2001/07
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime
Nihon Kikai Gakkai Kansai Shibu Dai-75-ki Teiji Soukai Koenkai Koen Rombunshu, p.13_11 - 13_12, 2000/00
no abstracts in English
Watanabe, Tadashi; Hirano, Masashi; *
JAERI-M 89-101, 20 Pages, 1989/08
no abstracts in English
Ono, Ayako; Yoshida, Hiroyuki; Suzuki, Takayuki*
no journal, ,
The behavior of bubbles and the process of coalescence are simulated by a computational multi-fluid dynamics (CMFD) simulation code TPFIT, which will contribute to develop the prediction method of critical heat flux based on the liquid-layer evaporation model. In this study, the calculation results in various pressure condition will be shown and the effect of the pressure on the behavior of bubbles will be discussed.
4 simulated fuel bundle using TPFITOno, Ayako; Nagatake, Taku; Suzuki, Takayuki*; Yoshida, Hiroyuki
no journal, ,
The evaluation method for the critical heat flux based on a mechanism is needed to evaluate the safety of fuel bundles in a light water reactor. The development of the numerical simulation method to predict the two-phase flow in the fuel bundles is implemented, which is needed to predict the CHF. The bubbly flow in 44 simulated fuel bundle was calculated in order to develop the evaluation method of the two-phase flow in the fuel bundle using TPFIT. The applicability of TPFIT for the two-phase flow in the fuel bundle was confirmed.
4 fuel bundle with the spacer by the mechanistically based methodOno, Ayako; Yamashita, Susumu; Suzuki, Takayuki*; Yoshida, Hiroyuki
no journal, ,
JAEA is implementing the 3D detailed nuclear-thermal-coupled analysis code in order to analyze the transition state of the core and to reduce the likelihood of the design. In the development plan, the computational fluid dynamics code based on the VOF method, JUPITER, is applied for TH part of the 3D detailed nuclear-thermal-coupled analysis code. In this study, the JUPITER code is examined to apply for the two-phase flow simulation of 44 fuel assembly with the spacer grid. The simulation results and previous study relating to observation of the two-phase flow in the fuel bundle are compared to validate the simulation results and considered reproducibility of the effect of the spacer grid.
Ito, Ryo*; Maemura, Tsuneyuki*; Matsui, Hiroya; Ozaki, Yusuke; Mochizuki, Akihito; Goke, Mitsuo*; Okihara, Mitsunobu*; Toguri, Satohito*
no journal, ,
The report summarized the hydrological simulation about a case study for long term changing of the geological environment around a drift in Horonobe URL.
