CHF experiment and CFD analysis in a 2 x 3 rod bundle with mixing vane
Creators
- 1. Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)
Description
In this study, the CHF enhancement using various mixing vanes is evaluated and the flow characteristics are investigated through the CHF experiments and CFD analysis. CHF tests were performed using 2 x 2 and 2 x 3 rod bundles and with R-134a as the working fluid. The test section geometry was identical to that of commercial PWR fuel assembly not including the heated length (1.125 m) and number of fuel rods. From the CHF tests, it was found that the CHF enhancement using mixing vanes under higher mass flux (1400 kg/m2 s) and lower pressure (15 bar) conditions is larger than the CHF enhancements under other conditions. Among the mixing vanes used in this study, the swirl vane showed the best performance under relatively low pressure (15 bar) and mass flux (300-1000 kg/m2 s) conditions and the hybrid vane performed best near the PWR operating conditions. The detailed flow characteristics were also investigated by CFD analysis using the same conditions as the CHF tests. To calculate the subcooled boiling flow, the wall partitioning model was applied to the wall boundary and various two-phase parameters were also considered. The reliability of the CFD analysis in the boiling analysis was confirmed by comparing the average void fractions of the analysis and the experiments: the results agreed well. From the CFD analysis, the void fraction flattening as a result of the lateral velocity induced by the mixing vane was observed. By the lateral motion of the liquid, the void fraction in the near wall was decreased and that of the core region was increased resulting in the void fraction flattening. The decrease of the void fraction in the near wall region promoted liquid supply to the wall and consequently the CHF increased. For the quantification of the void flatness, an index was developed and the applicability of the index in the CHF assessment was confirmed.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2009.01.011Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2009.01.011;
- PII
- S0029-5493(09)00076-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 239
- Journal Issue
- 5
- Journal Page Range
- p. 899-912
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41010266
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL ELEMENT CLUSTERS; FUEL RODS; LIQUIDS; MIXING; PERFORMANCE; PWR TYPE REACTORS; RELIABILITY; SUBCOOLED BOILING; VELOCITY; VOID FRACTION; VOIDS; WALLS; WORKING FLUIDS
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ASSEMBLIES; FUEL ELEMENTS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.