[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management - The Current Research Status and Technical Development Framework of Multi-Reactor Probabilistic Consequence Assessment
- 作者Ding, Hongchun; Tong, Jiejuan; Zhang, Liguo; Wang, Lu; Wang, Ruiying
- 文件大小300.19KB
- 发表时间2017
- DOI10.1115/ICONE25-66365
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Experimental study of critical heat flux enhancement with hypervapotron structure under natural circulation conditionsHou, Fangxin; Chang, Huajian; Zhao, Yufeng; Zhang, Ming; Gao, Tianfang; Chen, Peipei · Nuclear Engineering and Design · 2017
[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 6: Thermal-Hydraulics - Measurement of the Vapor Blanket Thickness by Image Processing MethodHou, Fangxin; Chang, Huajian; Zhao, Yufeng; Zhang, Ming; Chen, Peipei; Gao, Tianfang · 2017
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