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http://dx.doi.org/10.3795/KSME-B.2012.36.2.189

Visualization and 3D Numerical Analysis of the Circulation Flow of the Neutron Moderator in a Heavy-Water Nuclear Reactor  

Eom, Tae-Kwang (Dept. of Mechanical Control Engineering, Handong Global Univ.)
Lee, Jae-Young (Dept. of Mechanical Control Engineering, Handong Global Univ.)
Publication Information
Transactions of the Korean Society of Mechanical Engineers B / v.36, no.2, 2012 , pp. 189-196 More about this Journal
Abstract
The heavy moderator acts as the ultimate heat-sink in an operating CANDU reactor. HUKINS has been developed to investigate moderator flow patterns. HUKINS consists of a 38.4-mm-thick cylindrical shell with a 0.95 m inner diameter and 88 sus-tubes that produce a total heat of 10 kW. A chemical visualization method was selected to estimate the occurrence of typical moderator flow patterns. Momentum-dominated flow, mixed flow, and buoyancy-dominated flow are detected under conditions of a heat load of 7.7 kW and input mass flow rates of 4, 7, and 11 L/min. The experimental results are similar to the results of a CFD simulation that consisted of approximately 1.9 million grids and was conducted using the k-${\varepsilon}$ turbulence model. Therefore, both the present experiments and simulations using HUKINS, a 1/8-scale model, represent all three important flow patterns expected in the real CANDU6 reference reactor. Thus, it has been demonstrated that HUKINS could be useful in the study of CANDU6 moderator circulation.
Keywords
Moderator Cooling System; CANDU; Calandria; Chemical Visualization Method; CFD; Flow Patterns; k-${\varepsilon}$ Turbulence Model;
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  • Reference
1 Koroyannakis, D., Hepworth, R.D. and Hendrie, G., 1983, "An Experimental Study of Combined Natural and Forced Convection Flow in a Cylindrical Tank," TDVI-382, AECL.
2 Fortman, R.A. and Hadaller, G.I., 1990, "Moderator Temperature Distribution Experiments, Modified Inlet Port Tests: Results and Comparison," COG R&D Commercial, Nov.
3 Hadaller, G. I. and Fortman, R. A., 1990, "Moderator Temperature Distribution Experiments, Phase 1: Unobstructed and Obstructed; Adiabatic and Diabatic with Resistance Heating," COG R&D Commercial, Mach.
4 Hadaller, G. I. and Fortman, R. A., 1990, "Moderator Temperature Distribution Experiments, Phase 2: Obstructed Diabatic Tests with Electrolytic and Resistance Heating," COG R&D Commercial, June.
5 Khartabil, H.F., Inch, W.W., Szymanski, J., Novog, D., Tavasoli, V. and Mackinon, J., 2002. "Three dimensional moderator circulation experimental program for validation of CFD code MODTURC_CLAS," In 21st CNS Nuclear Simulation Symposium, Ottawa, Canada.
6 Lee, J.Y., Kim, M.W. and Kim, N.S., 2006, "Design of the 1/8 Scaled HUKINS Based on the Scaling Laws for the Experimental Investigation of Thermal-Hydraulic Effect of CANDU-6 Moderator," Trans. Of the KSME B, Vol. 30, No. 9, pp. 825-833.
7 Yoon, C., Rhee, B.W. and Min, B.J., 2002, "Validation of a CFD Analysis Model for Predicting CANDU-6 Moderator Temperature Against SPEL Experiments," Proceedings of ICONE10, April 14-18, Virginia, USA.
8 Kim, M., Yu, S.-O. and Kim, H.-J., 2006, "Analyses on Fluid Flow and Heat Transfer Inside Calandria vessel of CANDU-6 using CFD," Nuclear Engineering and Design 236, pp. 1155-1164.   DOI   ScienceOn