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200MW低温供热堆盒间流道流动传热数值分析
引用本文:解衡,高祖瑛. 200MW低温供热堆盒间流道流动传热数值分析[J]. 核技术, 2001, 24(10): 816-821
作者姓名:解衡  高祖瑛
作者单位:清华大学核能技术研究院
摘    要:采用三维CFD软件Phoenics-3.2,计算了200MW低温供热堆燃料组件盒间的流场及温场。研究了旁通流量、控制棒提升等因素的影响。在考虑这些因素之后,得出了最佳旁通入流方案。

关 键 词:CFD Phoenics 低温供热堆 燃料组件 盒间流道 流动传热 数值分析
修稿时间:2000-06-19

The numerical analysis of flow and heat transfer along the gap between the fuel assemblies of NHR-200
XIE Heng GAO Zuying. The numerical analysis of flow and heat transfer along the gap between the fuel assemblies of NHR-200[J]. Nuclear Techniques, 2001, 24(10): 816-821
Authors:XIE Heng GAO Zuying
Abstract:Three-dimensional CFD code, Phoenics-3.2, is used to calculate the flow and heat transfer along the gap between the fuel assemblies of 200MW nuclear heating reactor (NHR-200). The actions of important factors which could affect the flow and heat transfer were considered. After these investigations, the optimum scheme of bypass was gotten.
Keywords:CFD   Phoenics   Nuclear heating reactor  
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