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

被引:12
|
作者
Wang, X. A. [1 ]
Zhang, Dalin [1 ]
Wang, Mingjun [1 ]
Song, Ping [1 ]
Wang, Shibao [1 ]
Liang, Yu [1 ]
Zhang, Yapei [1 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
Su, G. H. [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Shaanxi Key Lab Adv Nucl Energy & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
关键词
Porous medium model; Hybrid medium model; Conjugate heat transfer; Inter-wrapper flow; Sodium-cooled fast reactor; TURBULENT-FLOW; POROUS-MEDIUM; TEMPERATURE; DIFFUSION;
D O I
10.1016/j.net.2019.09.009
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:708 / 720
页数:13
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