张小英; 陈焕栋; 白宁; 朱元兵; 任志豪; 黄凯

doi:10.13538/j.1001-8042/nst.25.050601

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Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-01-20

- Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model 封面论文增强出版
- Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model
- 核技术（英文版） 2014年 25卷第5期 (2014)
- 作者机构：
  
  School of Electric Power, South China University of Technology,Guangdong,China,510640;China Nuclear Power Technology Research Institute,Shenzhen,China,518026
- 作者简介：
- 基金信息：
  
  National Natural Science Foundation of China
- DOI：10.13538/j.1001-8042/nst.25.050601 中图分类号：
- 纸质出版日期：2014-10-20，
  
  网络出版日期：2014-09-20，
  
  收稿日期：2013-12-03，
  
  修回日期：，
  
  录用日期：2014-03-03
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张小英, 陈焕栋, 白宁, 等. Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model[J]. 核技术（英文版）, 2014, 25(5):050601

Xiao-Ying ZHANG, Huan-Dong CHEN, Ning BAI, et al. Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model[J]. Nuclear Science and Techniques, 2014, 25(5):050601
张小英, 陈焕栋, 白宁, 等. Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model[J]. 核技术（英文版）, 2014, 25(5):050601 DOI： 10.13538/j.1001-8042/nst.25.050601.

Xiao-Ying ZHANG, Huan-Dong CHEN, Ning BAI, et al. Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model[J]. Nuclear Science and Techniques, 2014, 25(5):050601 DOI： 10.13538/j.1001-8042/nst.25.050601.

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Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model 封面论文 增强出版

Steady thermal hydraulic characteristics of nuclear steam generators based on the drift flux code model 封面论文增强出版