THYC calculations in assemblies with staggered grids
Creators
- 1. Electricite de France, Direction des Etudes et Recherches, Departement Transfers Thermiques et Aerodynamique, 78 - Chatou (France)
Description
This paper is devoted to the validation of the THYC code in 3D configurations. THYC has been developed by EDF, and can be applied to PWR core thermal-hydraulic analysis. It is based on a porous medium approach and a fully three dimensional representation of the flow. Two analytical experiments dealing with in-bundle single-phase 3D flows are presented. One was performed at CEA, the other one at EDF. Both represent a bundle with a few rods, and simplified grids. The grids are arranged so as to cause baffle effects somehow similar to those induced at the border in between two assemblies whose grids are not at the same level. The CEA mock-up includes 5 x 5 rods and two staggered partial grids. The EDF mock-up includes 4 x 10 rods, and one partial grid in between two whole grids. Measured velocities using Laser Doppler Velocimetry are compared with THYC predictions. As the arrangements of the grids are not alike in the two experiments, the mechanisms governing the flow downstream of the baffle are different. The flow deviation around the partial grids is properly predicted by the THYC code, Yet, in the second configuration, the computed flow recovers uniform conditions downstream of the partial grid, on a shorter distance than in the experiment, hinting that the transverse pressure drop modeling could be improved for situations with small inclinations of the flow with respect to rod axis. (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. 217-229
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
- 30022204
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BAFFLES; FUEL ELEMENT CLUSTERS; GRIDS; HYDRAULICS; NUMERICAL ANALYSIS; PWR TYPE REACTORS; REACTOR CORES; T CODES; THERMODYNAMICS; VELOCITY
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; ELECTRODES; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FUEL ASSEMBLIES; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS