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[期刊论文] 作者:LV Yu-feng,ZHAO Min-fu,,
来源:Annual Report of China Institute of Atomic Energy 年份:2013
The RELAP5 code has been adopted to calculate critical flow through nozzles under steady state and transient blowdown experiment.Under steady state condition,th...
[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: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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