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http://dx.doi.org/10.1016/j.net.2019.09.009

Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor  

Wang, X.A. (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Zhang, Dalin (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Wang, Mingjun (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Song, Ping (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Wang, Shibao (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Liang, Yu (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Zhang, Yapei (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Tian, Wenxi (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Qiu, Suizheng (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Su, G.H. (School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
Publication Information
Nuclear Engineering and Technology / v.52, no.4, 2020 , pp. 708-720 More about this Journal
Abstract
Core-wide temperature distribution in sodium-cooled fast reactor plays a key role in its decay heat removal process, however the prediction for temperature distribution is quite complex due to the conjugate heat transfer between the assembly flow and the inter-wrapper flow. Hybrid medium model has been proposed for conjugate heat transfer modeling in the core. The core is modeled with a Realistic modeled inter-wrapper flow and hybrid medium modeled assembly flow. To validate present model, simulations for a three-assembly model were performed with Realistic modeling, traditional porous medium model and hybrid medium model, respectively. The influences of Uniform/Non-Uniform power distribution among assemblies and the Peclet number within the assembly flow have been considered. Compared to traditional porous medium model, present model shows a better agreement with in Realistic modeling prediction of the temperature distribution and the radial heat transfer between the inter-wrapper flow and the assembly flow.
Keywords
Porous medium model; Hybrid medium model; Conjugate heat transfer; Inter-wrapper flow; Sodium-cooled fast reactor;
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