Elements of Validation for LWRs Thermalhydraulic Studies With FLICA-OVAP
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
B3-1 Core Thermalhydraulics and Subchannel Analysis

Philippe Fillion (CEA Saclay)
Matteo Bucci (CEA Saclay)
Anne Charmeau (CEA Saclay)


FLICA-OVAP is an advanced two-phase flow thermal-hydraulics code based on a full 3D subchannel approach. It is designed to analyze flows in Light Water Reactors (LWRs) cores such as PWRs, BWRs and experimental reactors. Therefore its applicability covers all ranges of operating conditions for water-cooled reactors.

This paper presents an overview of FLICA-OVAP modeling capabilities for applications in nuclear reactors design and safety analysis. A validation matrix is proposed and its results are presented. The matrix covers a wide range of selected phenomena, which are relevant for thermalhydraulics studies. Therefore the different FLICA-OVAP physical correlations addressed in the current study include single phase and two-phase friction factors, single phase and boiling heat transfer, turbulence and critical heat flux.

Results of the FLICA-OVAP validation studies highlight the capabilities of the code to well predict two-phase flows in LightWater Reactors for both normal operation and under accidental circumstances. Future developments as well as validation activities are also summarized.

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