| 临界热流密度实验研究进展 |
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| 引用本文： | 肖泽军,陈炳德,李忠朋,贾斗南. 临界热流密度实验研究进展[J]. 核动力工程, 2003, 24(1): 24-27 |
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| 作者姓名： | 肖泽军 陈炳德 李忠朋 贾斗南 |
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| 作者单位： | 西安交通大学,西安,710049;中国核动力研究设计院,成都,610041 |
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| 摘 要： | 临界热流密度是重要的限制性热工参数，它的大小直接影响反应堆的安全性和经济性。本文介绍了我国核电站临界热流密度实验研究进展，比较了国外核电站临界热流密度研究发展状况，文章认为，我国临界热流密度实验研究的发展方向是进行全长棒束非均匀加热临界热流密度的实验研究。
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| 关 键 词： | 临界热流密度 核电站 研究进展 发展方向 |
| 文章编号： | 0258-0926(2003)01-024-04 |
| 修稿时间： | 2002-07-07 |
Research Progress of Experiment on Critical Heat Flux |
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| XIAO Ze-jun ,CHEN Bing-de,LI Zhong-peng,JIA Dou-nan. Research Progress of Experiment on Critical Heat Flux[J]. Nuclear Power Engineering, 2003, 24(1): 24-27 |
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| Authors: | XIAO Ze-jun CHEN Bing-de LI Zhong-peng JIA Dou-nan |
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| Affiliation: | XIAO Ze-jun 1,CHEN Bing-de2,LI Zhong-peng2,JIA Dou-nan1 |
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| Abstract: | Critical heat flux(CHF) is an important restricted thermal parameter, which size directly affects safety and economy of reactors. This paper presents experimental research progress on CHF for nuclear power plants in China, and compares with the experimental research progress on CHF in other countries, and points out the development direction of CHF experimental research in China which is to carry out full-length non-uniform heated rod bundle CHF experimental research. |
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| Keywords: | Critical heat flux Nuclear power plant Research progress Development direction |
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