NDLI: Preliminary Applications of the New NEPTUNE Two-Phase CFD Solver to Pressurized Thermal Shock Investigations

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Boucker, Marc Lavie´ville, Je´roˆme Martin, Alain Be´chaud, Ce´line Bestion, Dominique Coste, Pierre
Copyright Year	2004
Abstract	The objective of this communication is to present some preliminary applications to pressurized thermal shock (PTS) investigations of the CFD two-phase flow solver of the new NEPTUNE thermal-hydraulics platform, being jointly developed by EDF (Electricite´ De France) and CEA (Commissariat a` l’Energie Atomique) and also supported by IRSN (Institut de Radioprotection et Suˆrete´ Nucle´aire) and FRAMATOME-ANP. In the framework of plant life extension, the Reactor Pressure Vessel (RPV) integrity is a major concern, and an important part of RPV integrity assessment is related to PTS analysis. In the case where the cold legs are partially filled with steam, it becomes a two-phase problem and new important effects occur, such as condensation due to the Emergency Core Cooling (ECC) injections of sub-cooled water. Thus, an advanced prediction of RPV thermal loading during these transients requires sophisticated two-phase, local scale, 3D codes. In that purpose, a program has been set up to extend the capabilities of the NEPTUNE two-phase CFD solver. The major challenge is to develop new physical models to take into account the complex two-phase phenomena: free surface, jet of cold water through steam, entrainment of droplets by steam, entrainment of bubbles by water, and, above all direct contact condensation. Turbulent mixing in the liquid layer plays a central role by controlling at the same time the thermal mixing in the water and the condensation rate at the interface between liquid and vapor. A sustained effort in this area has started both at CEA and EDF. New models are developed and validated with the help of available experimental data sets, which are unfortunately very few. Beyond analytical single-effect cases, it is important to compute instrumented cases close to the life-size one, including major physical effects. This is the case of the COSI experimental facility, representing a cold leg with ECC injection, where temperature profiles have been measured. Numerical results on a steady-state COSI test are presented and analyzed, showing encouraging results. However, research work is still required to achieve a better modeling of the heat transfer and turbulence at the steam-water interface.
Sponsorship	Nuclear Engineering Division
Starting Page	745
Ending Page	751
Page Count	7
File Format	PDF
ISBN	0791846881
DOI	10.1115/ICONE12-49128
e-ISBN	0791837351
Volume Number	12th International Conference on Nuclear Engineering, Volume 2
Conference Proceedings	12th International Conference on Nuclear Engineering
Language	English
Publisher Date	2004-04-25
Publisher Place	Arlington, Virginia, USA
Access Restriction	Subscribed
Subject Keyword	Water Turbulence Cooling Reactor vessels Computational fluid dynamics Vapors Emergencies Temperature profiles Condensation Modeling Steady state Transients (dynamics) Bubbles Two-phase flow Thermal shock Steam Drops Life extension Thermal hydraulics Heat transfer
Content Type	Text
Resource Type	Article

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