The numerical analysis of flow and heat transfer along the gap   between the fuel assemblies of NHR-200

XIE Heng  GAO Zuying

doi:null

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The numerical analysis of flow and heat transfer along the gap between the fuel assemblies of NHR-200

更新时间：2021-03-12

- The numerical analysis of flow and heat transfer along the gap between the fuel assemblies of NHR-200
- NUCLEAR TECHNIQUES Issue 10, (2001)
- 作者机构：
  
  1. 清华大学核能技术研究院
  2. 清华大学核能技术研究院,北京,100084
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL413.2
- Published：01 October 2001
- 稿件说明：
移动端阅览
[1]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(10):816-821.

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, (10): 816-821.
[1]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(10):816-821. DOI：

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, (10): 816-821. DOI：

摘要

采用三维CFD软件Phoenics - 3.2

计算了 2 0 0MW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。

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.

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