A steady-state 3D simulation for predicting the local subcooling of the moderator in the vicinity of the calandria tubes in a CANDU-6 reactor is performed. For the current simulation, a set of grid structures with the same geometry as the CANDU-6 moderator tank, called ‘calandria vessel’, is generated and the momentum, heat and continuity equations are solved by CFX-4.3, a CFD code developed by AEA technology. The standard k-ε turbulence model associated with logarithmic wall treatment is used to model turbulence generation and dissipation within the vessel. The moderator fluid is heavy water. Buoyancy forces are modeled using the Boussinesq approximation in which density is assumed to be a linear function of temperature. The matrix of the calandria tubes in the center region of the calandria vessel is simplified by the porous media approach. The anisotropic hydraulic impedance of the calandria tubes is modeled using the frictional pressure drop correlations suggested by Idelchik and Szymanski. The heat load in this steady-state simulation is conservatively set as 103 MW of 103% full power, consisting of 96.7 MW to the core region and 6.3 MW to the reflector region. The total volumetric flow rate through eight inlet nozzles is 940 L/s and the outlet temperature is constantly 71.0 °C. The thermal boundary condition of the circumferential vessel wall is assumed a little heat flux out. As a result, the velocity field and temperature distribution of a CANDU-6 moderator in the operating condition are presented. The flow pattern identified in this simulation is the weak jet momentum-dominated flow, which is generated by the interaction between the buoyancy force by heating and the dominant momentum forces by inlet jets. The calculated maximum temperature of the moderator is 83.0 °C at the lower center region of the core, which corresponds to the minimum subcooling of 33.0 °C considering the boiling point increase due to the hydrostatic pressure change.
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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
CFD Simulation of the CANDU-6 Moderator Circulation Under Normal Operating Conditions
Bo Wook Rhee,
Bo Wook Rhee
Korea Atomic Energy Research Institute, Daejeon, Korea
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Churl Yoon,
Churl Yoon
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:
Bo Wook Rhee
Korea Atomic Energy Research Institute, Daejeon, Korea
Churl Yoon
Korea Atomic Energy Research Institute, Daejeon, Korea
Byung-Joo Min
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE10-22527, pp. 901-908; 8 pages
Published Online:
March 4, 2009
Citation
Rhee, BW, Yoon, C, & Min, B. "CFD Simulation of the CANDU-6 Moderator Circulation Under Normal Operating Conditions." 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. 901-908. ASME. https://doi.org/10.1115/ICONE10-22527
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