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

Ono, Ayako ; Nagatake, Taku ; Suzuki, Takayuki*; Yoshida, Hiroyuki  

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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