钠冷快堆燃料组件流道优化设计数值模拟
摘要
本文采用计算流体力学(CFD)方法针对不同流通横截面的7根棒束组成的快堆燃料组件进行数值模拟,分析绕丝直径与六角管内对边距设置对组件热工水力性能的影响。结果表明,绕丝对冷却剂具有强烈的搅混作用,在起到定位作用的同时,为热平衡提供驱动力。通过改变燃料组件流道结构,即采用外圈小直径绕丝并缩小内对边距的设置,可以对冷却剂在不同子通道中的流量进行重新分配,具有更好的热工水力性能。
This paper uses computational fluid dynamics( CFD) method to simulate the fast reactor fuel assemblies composed of 7 bundles with different flow cross sections, and analyzes the influence of the diameter of the wire-wrap and the setting of the margin in the hexagonal tube on the thermal hydraulic performance of the assemblies. The results show that the wire-wrap has a strong mixing effect on the coolant, and provides a driving force for the heat balance while positioning. By changing the fuel assembly flow path structure, that is, the setting of small diameter wire-wrap with outer ring and narrowing inner-to-edge distance is adopted., the flow rate of the coolant in different sub-channels can be redistributed, and the thermal hydraulic performance is better.
This paper uses computational fluid dynamics( CFD) method to simulate the fast reactor fuel assemblies composed of 7 bundles with different flow cross sections, and analyzes the influence of the diameter of the wire-wrap and the setting of the margin in the hexagonal tube on the thermal hydraulic performance of the assemblies. The results show that the wire-wrap has a strong mixing effect on the coolant, and provides a driving force for the heat balance while positioning. By changing the fuel assembly flow path structure, that is, the setting of small diameter wire-wrap with outer ring and narrowing inner-to-edge distance is adopted., the flow rate of the coolant in different sub-channels can be redistributed, and the thermal hydraulic performance is better.
引文
[1]K.Natesan,T.Sundararajan,ArunnNarasimhan,K,et al.Turbulent flow simulation in a wire-wrap rod bundle of an LMFBR[J].Nuclear Engineering and Design,2009,240(5).1-10
[2]T.Sreenivasulu*,BVSSS Prasad.Flow and heat transfer characteristics in a seven tube bundle wrapped with helical wires[J].International Journal of Advancements in Technology.2011,2(3):1-32
[3]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, 48(10):1790-1796.
[4]李淞,杨红义,周志伟,等.快堆组件稠密棒束数值模拟[J/OL].原子能科学技术, 2018, 4:1-5.
[5] Kurt D. Hamman; Ray A. Berry, A CFD simulation process for fast reactor fuel assemblies[J]. Nuclear Engineering and Design,2009, 240(9):1-9.
[6]Imteyaz Ahmad,Kwang-Yong Kim,Flow and convective heat transfer analysis using RANS for a wire-wrapped fuel assembly, Journal of Mechanical Science and Technology,2006,20(9):1514-1524.
[7]T.Sreenivasulu*,BVSSS Prasad.Flow and heat transfer characteristics in a seven tube-boundle wrapped with helical wires[j].International Journal of Advancements in Technology.2011,2(3):350-359.
[8]J.K Fink and Leibowitz*.Thermodynamic and transport properties of sodium liquid andvapor[R].Reactor Engineering Division, Argonne National Laboratory, 1995.
[2]T.Sreenivasulu*,BVSSS Prasad.Flow and heat transfer characteristics in a seven tube bundle wrapped with helical wires[J].International Journal of Advancements in Technology.2011,2(3):1-32
[3]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, 48(10):1790-1796.
[4]李淞,杨红义,周志伟,等.快堆组件稠密棒束数值模拟[J/OL].原子能科学技术, 2018, 4:1-5.
[5] Kurt D. Hamman; Ray A. Berry, A CFD simulation process for fast reactor fuel assemblies[J]. Nuclear Engineering and Design,2009, 240(9):1-9.
[6]Imteyaz Ahmad,Kwang-Yong Kim,Flow and convective heat transfer analysis using RANS for a wire-wrapped fuel assembly, Journal of Mechanical Science and Technology,2006,20(9):1514-1524.
[7]T.Sreenivasulu*,BVSSS Prasad.Flow and heat transfer characteristics in a seven tube-boundle wrapped with helical wires[j].International Journal of Advancements in Technology.2011,2(3):350-359.
[8]J.K Fink and Leibowitz*.Thermodynamic and transport properties of sodium liquid andvapor[R].Reactor Engineering Division, Argonne National Laboratory, 1995.