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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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