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[期刊论文] 作者：CHEN Yu-zhou,BI Ke-ming,YANG Bing,ZHAO Min-fu,,
来源：Annual Report of China Institute of Atomic Energy 年份：2014
As the core components of the reactor,the performance of fuel element is one of the main influence factors for nuclear safety and economy.Using annular fuel ele...
[期刊论文] 作者：LIU Hong-wei,BI Ke-ming,ZHANG Wei,LIANG Shu-hong,WANG Fan,LIU Dong-hai,,
来源：Annual Report of China Institute of Atomic Energy 年份：2015
The critical safety in the fuel reprocessing is always one of the most focused issues.The dissolver for nuclear fuel is one of the key devices,which has multiph...
[期刊论文] 作者：QI Xiao-guang,CHENG Dao-xi,ZHAI Wei-ming,ZHOU Ping,BI Ke-ming,WANG Wei,,
来源：Annual Report of China Institute of Atomic Energy 年份：2014
On December 6th,2014,jet impingement tests have been completed successfully for two types of in-containment cables for the AP1000Sanmen project in China Institu...
Progress of Two-phase Flow and Heat Transfer Behavior Research in Natural Circulation and Core Reflo
[期刊论文] 作者：CHEN Yu-zhou,DUAN Ming-hui,LV Yu-feng,LI Wei-qing,BI Ke-ming,WANG Wei,,
来源：Annual Report of China Institute of Atomic Energy 年份：2014
1 Research purpose and significance The two-phase flow and heat transfer behavior research in the natural circulation and core reflooding is the first subprojec...
[期刊论文] 作者：CHEN Yu-zhou,ZHAO Min-fu,BI Ke-ming,ZHANG Dong-xu,LV Yu-feng,WANG Wei,YANG Bing,LI Wei-qing,,
来源：Annual Report of China Institute of Atomic Energy 年份：2015
In order to investigate the effect of nozzle diameter and break orientation on two-phase critical flow and obtain the transient experiment data under different...
Progress of Two-phase Flow and Heat Transfer Behavior Research in Natural Circulation and Core Reflo
[期刊论文] 作者：CHEN Yu-zhou,DUAN Ming-hui,LV Yu-feng,LI Wei-qing,ZHAO Min-fu,ZHANG Dong-xu,BI Ke-ming,WANG Wei,YANG,
来源：Annual Report of China Institute of Atomic Energy 年份：2015
The two-phase flow and heat transf e r behavior research in the natural circulation and core reflooding is the first subproject of the key technology research o...
[期刊论文] 作者：CHEN Yu-zhou,ZHAO Min-fu,LI Wei-qing,LV Yu-Feng,ZHANG Dong-xu,BI Ke-ming,WANG Wei,DUAN Ming-hui,YANG,
来源：Annual Report of China Institute of Atomic Energy 年份：2014
Under a hypothetical lost of coolant accident of nuclear reactor,it may cause critical flow due to the pressure down sharply and the coolant vapors at the break...
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