[1A07-11] Gas-liquid Two-phase Flow

[1A11] Development of a System Analysis Code for NPP

(3)Code Validation Based on Void Fraction Measurement Tests

*Junichi Kaneko¹, Naofumi Tsukamoto¹ (1. NRA)

Keywords:System analysis code for nuclear power plants, AMAGI, Thermal-hydraulic analysis, Void fraction measurement test, Code validation

Development of a system analysis code for nuclear power plants, AMAGI, is ongoing to reflect state-of-the-art technical knowledge and to apply it into safety evaluations. In this study, thermal-hydrauic analyses using AMAGI on various void fraction measurement tests were conducted in order to validate models, which affect void fraction estimation, such as an interfacial shear model and a wall heat transfer model.