3D simulations of single phase flows in rod bundles with ESTET-ASTRID code
Creators
- 1. Electricite de France - Direction des Etudes et Recherches, 78 - Chatou (France)
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 (k-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 we 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)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- ISBN
- 4-9900222-1-1
- Imprint Title
- Fourth international seminar on subchannel analysis
- Imprint Pagination
- 354 p.
- Journal Page Range
- p. 27-42
Conference
- Title
- 4. international seminar on subchannel analysis
- Acronym
- ISSCA-4
- Dates
- 25-26 Sep 1997
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30022190
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; CORRELATIONS; E CODES; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; HYDRAULICS; NUMERICAL SOLUTION; PWR TYPE REACTORS; SIMULATION; THERMODYNAMICS; TURBULENCE; VELOCITY
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS