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International Heat Transfer Conference 8

ISSN: 2377-424X (online)
ISSN: 2377-4371 (flashdrive)

Transient Analysis of Nuclear U-tube Steam Generator

Zeljko Bogdan
Faculty of Mechanical Engineering and Naval Architecture, University of Zagreb, Croatia

Naim Hamdia Afgan
Instituto Superior Técnico, Lisbon, Portugal

要約

Steam generator transient behavior in ATWS is one of the milestones in the safety assessment of nuclear power plants. This paper is devoted to the analysis of steam generator behavior in the power plant transient scenario leading to 18 percent power increase. Transient, threedimensional code NUGEN was used in the analysis. It is based on algebraic slip two-phase flow model which takes into account drift velocity as a result of steam-water velocity difference. With respective constitutive equations for wall friction and heat transfer coefficients mass, momentum and energy equations have been solved. Obtained results for specific scenario are analysed with respect to integral parameters of the steam generator as well as spacial distribution of the parameters within the secondary side of the steam generator. In particular water level in downcorner, steam mass flow rate, primary fluid inlet and out let temperature and circulation ratio have been analysed. Change in spacial distribution of two-phase flow on the secondary side of the steam generator has shown that further improvement in the two-phase model is required in order to obtain fully reliable data for the safety assessment of a nuclear power plant.

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