Author:
Xu Wei,Deng Yonghao,Liu Xiaojing,Cheng Xu,Wu Dan
Subject
Nuclear Energy and Engineering
Reference35 articles.
1. Sudo, Y., Miyata, K., Ikawa, H., et al., 1986. Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3. J. Nucl. Technol. 23 (1), 73–82
2. Improvements of interfacial friction and heat transfer models for rectangular narrow channel reflood simulation based on RELAP5;Zeng;Kerntechnik,2018
3. Flow and heat transfer in pressurized water reactor reflood;Zeng;Multiphase Sci. Technol.,2010
4. Cadek, F., Dominicis, D., Leyse, R. PWR FLECHT: (FULL LENGTH EMERGENCY COOLING HEAT TRANSFER). Final Report. Westinghouse Electric Corp., Pittsburgh, Pa. Nuclear Energy Systems Div. Idaho Nuclear Corp., Idaho Falls, 1971
5. System pressure effect on system and core cooling behavior during reflood phase of PWR LOCA;Akimoto;J. Nucl. Sci. Technol.,1987
Cited by
2 articles.
订阅此论文施引文献
订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献