|
|
Applied Physics 2021
低雷诺数条件下钠冷快堆的数值模拟
|
Abstract:
钠冷快堆的自然循环过程是在低雷诺数条件下进行的，所以研究在低雷诺数条件下钠冷快堆的流动特性是非常有必要的。利用计算流体力学软件对钠冷快堆带绕丝棒束进行了数值模拟，结果表明，Rehme关系式与模拟的结果是吻合较好的。燃料组件的入口距离是小于一个螺距的距离，且出口效应对摩擦阻力系数影响不大。
The natural cycle of sodium-cooled fast reactors is carried out under low Reynolds number conditions, so it is necessary to study the flow characteristics of sodium-cooled fast reactors under low Reynolds number conditions. The numerical simulation of the wire-wrapped rod bundle of the sodium-cooled fast reactor is carried out by using computational fluid dynamics software. The results show that the Rehme relationship is in good agreement with the simulation results. The inlet distance of the fuel assembly is less than a pitch, and the outlet effect has little effect on the friction resistance coefficient.
| [1] | Cheng, S.K. and Todreas, N.E. (1986) Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters. Nuclear Engineering and Design, 92, 227-251. https://doi.org/10.1016/0029-5493(86)90249-9 |
| [2] | Rehme, K. (1973) Pressure Drop Cor-relations for Fuel Element Spacers. Nuclear Technology, 17, 15-23.
https://doi.org/10.13182/NT73-A31250 |
| [3] | Engel, F.C., Markley, R.A. and Bishop, A.A. (2017) Laminar, Tran-sition, and Turbulent Parallel Flow Pressure Drop across Wire-Wrap-Spaced Rod Bundles. Nuclear Science and Engi-neering, 69, 290-296.
https://doi.org/10.13182/NSE79-A20618 |
| [4] | Hamman, K.D. and Berry, R.A. (2010) A CFD Simulation Process for Fast Reactor Fuel Assemblies. Nuclear Engineering & Design, 240, 2304-2312. https://doi.org/10.1016/j.nucengdes.2009.11.007 |
| [5] | Gajapathy, R., Velusamy, K., Selvaraj, P., et al. (2007) CFD Investigation of Helical Wire-Wrapped 7-Pin Fuel Bundle and the Challenges in Modeling Full Scale 217 Pin Bundle. Nuclear Engineering and Design, 237, 2332-2342.
https://doi.org/10.1016/j.nucengdes.2007.05.003 |
| [6] | 刘洋, 喻宏, 周志伟. 钠冷快堆燃料组件热工水力特性数值模拟与分析[J]. 原子能科学技术, 2014(10): 1790-1796. |
| [7] | 李淞, 杨红义, 周志伟, 等. 快堆组件稠密棒束数值模拟[J]. 原子能科学技术, 2018, 52(4): 41-45. |
| [8] | Nina, Y., Dalin, Z., Jing, C., et al. (2018) The Development and Validation of the inteRwrapper Flow Model in Sodium-Cooled Fast Reactors. Progress in Nuclear Energy, 108, 54-65. https://doi.org/10.1016/j.pnucene.2018.05.007 |
| [9] | 刘亮. 从“十三五”规划看电力转型发展[J]. 大众用电, 2019, 34(4): 3-4. |
| [10] | 赵成昆. 中国核电建设进入全新时代[J]. 中国电力企业管理, 2019(4): 37-39. |
| [11] | 曹殿鹏, 邹树梁, 唐德文, 肖魏魏, 于洁. 三种核燃料循环方案的综合效益比较[J]. 核科学与工程, 2019, 39(5): 809-820. |
