Assessment of CFD Modeling for PTS Thermal-Hydraulics Using Multiple Scale Experimental Facilities
Creators
- 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)
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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39042868
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPLEXES; COMPUTERIZED SIMULATION; COOLANTS; LOSS OF COOLANT; MIXING; NAVIER-STOKES EQUATIONS; PRESSURE VESSELS; REYNOLDS NUMBER; THERMAL HYDRAULICS; THERMAL SHOCK
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DIFFERENTIAL EQUATIONS; DIMENSIONLESS NUMBERS; EQUATIONS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR ACCIDENTS; SIMULATION
Optional Information
- Notes
- 8 refs.