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Journal Articles

Large-scale numerical simulation on two-phase flow behavior in a tight-lattice nuclear fuel bundle

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

Oral presentation

Study on behavior of bubbles and process of coalescence by using CMFD simulation code TPFIT, 1; Effect of pressure on the behavior of bubbles and process of coalescence

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.

Oral presentation

Numerical simulation of two-phase flow in 4$$times$$4 simulated fuel bundle using TPFIT

Ono, 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 4$$times$$4 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.

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