Comparisons of numerical simulations with ASTRID code against experimental results in rod bundle geometry for boiling flows
- 1. Electricite de France, 78 - Chatou (France). Direction des Etudes et Recherches
Description
After different validation simulations of flows through cylindrical and annular channels, a subcooled boiling flow through a rod bundle has been simulated with ASTRID Steam-Water of software. The experiment simulated is called Poseidon. It is a vertical rectangular channel with three heating rods inside. The thermohydraulic conditions of the simulated flow were close to the DNB conditions. The simulation results were analysed and compared against the available measurements of liquid and wall temperatures. ASTRID Steam-Water produced satisfactory results. The wall and the liquid temperatures were well predicted in the different parts of the flow. The void fraction reached 40 % in the vicinity of the heating rods. The distribution of the different calculated variables showed that a three-dimensional simulation gives essential information for the analysis of the physical phenomena involved in this kind of flow. The good results obtained in Poseidon geometry will encourage future rod bundle flow simulations and analyses with ASTRID Steam-Water code. (author)
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- EDF--98-NB-00012
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 30001863
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; FLUID FLOW; FUEL ELEMENT CLUSTERS; PWR TYPE REACTORS; SUBCOOLED BOILING; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BOILING; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 15 refs.