Published 2006 | Version v1
Book

Assessment of CFD Modeling for PTS Thermal-Hydraulics Using Multiple Scale Experimental Facilities

  • 1. NRG, Plant Performance and Technology, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands)

Description

A serious threat to the life span of a Reactor Pressure Vessel (RPV) is the occurrence of Pressurized Thermal Shock during an Emergency Core Coolant injection in a loss-of-coolant accident (LOCA). Traditional thermal-hydraulic system codes fail to predict the complex three-dimensional thermal mixing and flow phenomena that occur during the injection. Since Computational Fluid Dynamics (CFD) is able to predict these phenomena, the present paper presents an assessment of Reynolds Averaged Navier Stokes CFD approaches. This assessment has been performed by comparing the numerical results obtained using advanced turbulence models available in the CFX 5.6 CFD code with experimental results of the full-scale Upper Plenum Test Facility (UPTF) and the 1:5 linear scale Rossendorf Coolant Mixing Model (ROCOM). The assessment shows that the observed flow behavior is quite similar for these facilities of different scale. The CFD code is very well capable of capturing the stratification and mixing phenomena occurring in the cold leg, while it has been shown that current RANS approaches are less capable of grasping the complex oscillating flow in the downcomer. (authors)

Part of:
Validation of the TRACE Code Against Post-Dryout Experiments in Tubes and Annuli

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-698-5
Imprint Title
Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
Imprint Pagination
2734 p.
Journal Page Range
p. 1636-1645

Conference

Title
2006 International congress on advances in nuclear power plants - ICAPP'06
Dates
4-8 Jun 2006
Place
Reno - Nevada (United States)

Optional Information

Notes
8 refs.