AP1000 ADS-4空气-水夹带试验研究
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摘要
为研究核电厂中ADS-4卸压夹带过程,以AP1000核电厂为原型设计建造了ADS-4喷放卸压试验回路ADETEL。用高速摄像仪拍摄夹带起始和夹带率的试验过程,将试验数据与现有试验数据和模型进行对比。结果表明:ADETEL试验数据和其他试验数据及理论模型之间存在较大差异;RELAP5和ATLATS的夹带率模型不能准确估算AP1000核电厂中的ADS-4夹带量;当热管段内液位较低时,夹带量会随热管段内液位降低而迅速减小;夹带起始在小支管-主管直径比(d/D)工况下更容易发生;在相同的热管段相对液位下,AP1000中ADS-4支管内液体的夹带率较AP600的低。
The ADS-4depressurization and entrainment test loop(ADETEL)scaled with AP1000 as the prototype was constructed to investigate the entrainment process at the ADS-4tee branch line.The experimental phenomenon of the onset of entrainment and the entrainment rate were recorded by a high speed camera.The data were obtained and compared with the existing data and correlations.The results show that large discrepancy between ADETEL experimental data and available data exists.RELAP5 and ATLATS correlations can not estimate the entrainment quality in AP1000 accurately.The entrainment rate declines rapidly with the decrease of liquid level in hot leg when the liquid level is low.The onset of entrainment is more likely to happen in smaller d/D(diameter ratio of branch to hot leg)conditions.The ADS-4entrainment rate in AP1000 is lower than that in AP600 at the same dimensionless hot leg liquid level.
The ADS-4depressurization and entrainment test loop(ADETEL)scaled with AP1000 as the prototype was constructed to investigate the entrainment process at the ADS-4tee branch line.The experimental phenomenon of the onset of entrainment and the entrainment rate were recorded by a high speed camera.The data were obtained and compared with the existing data and correlations.The results show that large discrepancy between ADETEL experimental data and available data exists.RELAP5 and ATLATS correlations can not estimate the entrainment quality in AP1000 accurately.The entrainment rate declines rapidly with the decrease of liquid level in hot leg when the liquid level is low.The onset of entrainment is more likely to happen in smaller d/D(diameter ratio of branch to hot leg)conditions.The ADS-4entrainment rate in AP1000 is lower than that in AP600 at the same dimensionless hot leg liquid level.
引文
[1]WANG W W,SU G H,QIU S Z.Thermal hydraulic phenomena related to small break LOCAs in AP1000[J].Progress in Nuclear Energy,2011,53(4):407-419.
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[4]SCHROCK V E,REVANKAR S T,MANNHEIMER R,et al.Small break critical discharge:The roles of vapor and liquid entrainment in a stratified two-phase region upstream of the break,NUREG/CR-4761,LBL-2204[R].US:Nuclear Regulatory Commission,1986.
[5]MACIASZEK T,MICAELLI J C.CATHARE phase separation modeling for small breaks in horizontal pipes with stratified flow[J].Nucl Eng Des,1990,124:247-256.
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[8]REYES J N,GROOME J T,LAFI A Y.Final report of NRC AP600research conducted at Oregon State University,NUREG/CR-6641[R].US:Nuclear Regulatory Commission,1999.
[9]SUN D C,TIAN W X,QIU S Z.Scaling analysis of AP1000ADS-4entrainment and depressurization[J].Progress in Nuclear Energy,2014,74:71-78.
[10]The RELAP5 Code Development Team.RELAP5/MOD3code manual[M].US:Nuclear Regulatory Commission,1995.
[11]WELTER K B,WU Q,YOU Y.Experimental investigation and theoretical modeling of liquid entrainment in a horizontal tee with a vertical-up branch[J].Int J Multiphase Flow,2004,30:341-360.
[2]林诚格.非能动安全先进压水堆核电技术[M].北京:原子能出版社,2008.
[3]SMOGLIE C,REIMANN J,MULLER U.Two-phase flow through small breaks in a horizontal pipe with stratified flow[J].Nucl Eng Des,1987,99:117-130.
[4]SCHROCK V E,REVANKAR S T,MANNHEIMER R,et al.Small break critical discharge:The roles of vapor and liquid entrainment in a stratified two-phase region upstream of the break,NUREG/CR-4761,LBL-2204[R].US:Nuclear Regulatory Commission,1986.
[5]MACIASZEK T,MICAELLI J C.CATHARE phase separation modeling for small breaks in horizontal pipes with stratified flow[J].Nucl Eng Des,1990,124:247-256.
[6]WELTER K B.Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe[D].US:Oregon State University,2003.
[7]孟兆明,刘丽芳,王来顺.T型管夹带起始实验研究[C]∥第13届反应堆热工流体学术年会.上海:[出版者不详],2013.
[8]REYES J N,GROOME J T,LAFI A Y.Final report of NRC AP600research conducted at Oregon State University,NUREG/CR-6641[R].US:Nuclear Regulatory Commission,1999.
[9]SUN D C,TIAN W X,QIU S Z.Scaling analysis of AP1000ADS-4entrainment and depressurization[J].Progress in Nuclear Energy,2014,74:71-78.
[10]The RELAP5 Code Development Team.RELAP5/MOD3code manual[M].US:Nuclear Regulatory Commission,1995.
[11]WELTER K B,WU Q,YOU Y.Experimental investigation and theoretical modeling of liquid entrainment in a horizontal tee with a vertical-up branch[J].Int J Multiphase Flow,2004,30:341-360.