3d simulations of single phase flows in rod bundles with ESTET-ASTRID code
Creators
- 1. Electricite de France, 78 - Chatou (France). Direction des Etudes et Recherches
Description
The study presented in this paper can be used to evaluate the performance of the ESTET-ASTRID code in the geometry of the Graziella experiment. This experiment which is performed at CEA-Grenoble, reproduces a conventional 5 x 5 rod bundle in thermal-hydraulic conditions equivalent to the normal operating conditions of a PWR core. It gives average subchannel flowrate and enthalpy measurements of great value when validating PWR core thermal-hydraulic codes. A Graziella test point corresponding to isothermal single-phase flow was simulated with ESTET-ASTRID. The influence of the mesh refinement and of the turbulence model (κ-ε, Rij-ε) is studied and we show that a second moment closure model (Rij-ε) in association with a fine mesh (about 400 nodes per subchannel) gives excellent results. The simulations performed indicate that the ESTET-ASTRID local approach and its physical models could bring complementary information, when combined with a subchannel thermal-hydraulic code such as THYC, for rod bundle flow prediction. (author)
Availability note (English)
Available from INIS in electronic formFiles
30001862.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- EDF--98-NB-00011
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 30001862
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; E CODES; ENTHALPY; FLUID FLOW; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.