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Study of a low Mach nuclear core model for two-phase flows with phase transition I: Stiffened gas law. (English) Zbl 1304.35529
Summary: In this paper, we are interested in modelling the flow of the coolant (water) in a nuclear reactor core. To this end, we use a monodimensional low Mach number model supplemented with the stiffened gas law. We take into account potential phase transitions by a single equation of state which describes both pure and mixture phases. In some particular cases, we give analytical steady and/or unsteady solutions which provide qualitative information about the flow. In the second part of the paper, we introduce two variants of a numerical scheme based on the method of characteristics to simulate this model. We study and verify numerically the properties of these schemes. We finally present numerical simulations of a loss of flow accident (LOFA) induced by a coolant pump trip event.

35Q35 PDEs in connection with fluid mechanics
35Q79 PDEs in connection with classical thermodynamics and heat transfer
65M25 Numerical aspects of the method of characteristics for initial value and initial-boundary value problems involving PDEs
76T10 Liquid-gas two-phase flows, bubbly flows
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