A validation of a 3D CFD model for predicting local subcooling of the moderator in the vicinity of calandria tubes in a CANDU-6 reactor is performed. The small scale moderator experiments performed at Sheridan Park Experimental Laboratory (SPEL) in Ontario, Canada [1] is used for the validation. Also a comparison is made between previous CFD analyses based on 2DMOTH and PHOENICS, and the current analysis for the same SPEL experiment. For the current model, a set of grid structures for the same geometry as the experimental test section is generated and the momentum, heat and continuity equations are solved by CFX-4.3, a CFD code developed by AEA technology. The matrix of calandria tubes is simplified by the porous media approach. The standard k-ε turbulence model associated with logarithmic wall treatment and SIMPLEC algorithm on the body fitted grid are used. Buoyancy effects are accounted for by the Boussinesq approximation. For the test conditions simulated in this study, the flow pattern identified is the buoyancy-dominated flow, which is generated by the interaction between the dominant buoyancy force by heating and inertial momentum forces by the inlet jets. As a result, the current CFD moderator analysis model predicts the moderator temperature reasonably, and the maximum error against the experimental data is kept at less than 2.0°C over the whole domain. The simulated velocity field matches with the visualization of SPEL experiments quite well.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Validation of a CFD Analysis Model for Predicting CANDU-6 Moderator Temperature Against SPEL Experiments
Churl Yoon,
Churl Yoon
Korea Atomic Energy Research Institute, Daejeon, Korea
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Bo Wook Rhee,
Bo Wook Rhee
Korea Atomic Energy Research Institute, Daejeon, Korea
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Byung-Joo Min
Byung-Joo Min
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Churl Yoon
Korea Atomic Energy Research Institute, Daejeon, Korea
Bo Wook Rhee
Korea Atomic Energy Research Institute, Daejeon, Korea
Byung-Joo Min
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE10-22114, pp. 131-138; 8 pages
Published Online:
March 4, 2009
Citation
Yoon, C, Rhee, BW, & Min, B. "Validation of a CFD Analysis Model for Predicting CANDU-6 Moderator Temperature Against SPEL Experiments." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 131-138. ASME. https://doi.org/10.1115/ICONE10-22114
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