二次侧非能动余热排出系统启动特性试验研究
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摘要
二次侧非能动余热排出(ASP)系统是国内二代加型百万千瓦级压水堆核电厂应对全厂断电事故的重要改进项。为获取ASP系统的启动特性,基于比例模化方法设计建造了ASP系统试验装置。试验结果获取了不同因素对ASP系统启动特性的影响。结果表明:蒸汽发生器二次侧水装量与ASP系统隔离阀动作时间对ASP系统的启动特性影响较小;ASP系统的流量随蒸汽管线与回水管线阻力系数的增大而降低;蒸汽释放阀(VDA)的往复开启引起自然循环流量的波动,当VDA关闭后自然循环可恢复至稳定状态;换热管内初装水的水量影响ASP系统初始流量峰值;所有试验工况中均建立了稳定的自然循环。
Advanced secondary passive residual heat removal(ASP) system is one of the most important improving measures to cope with station blackout accident in the domestic second generation+ 1 000 MWe PWR nuclear power plant. In order to obtain the starting performance of ASP system, the ASP system test facility was constructed based on scaling criteria. The effects of different influencing factors on starting performance of ASP system were obtained. The results show that the secondary-side water inventory of steam generator and operating time of ASP system isolation valve have little influence on starting performance of ASP system. The flow rate of ASP system decreases with the increase of drag coefficient of steam pipeline and backwater pipeline. The flow rate of ASP system is unstable with reciprocating opening of vapor discharge to atmosphere valve(VDA), and it is recovered to stable state when VDA is closed. The peak value of flow rate of ASP system is mainly affected by the initial water volume of heat exchanger tube. The stable natural circulation is established during all the experiments.
Advanced secondary passive residual heat removal(ASP) system is one of the most important improving measures to cope with station blackout accident in the domestic second generation+ 1 000 MWe PWR nuclear power plant. In order to obtain the starting performance of ASP system, the ASP system test facility was constructed based on scaling criteria. The effects of different influencing factors on starting performance of ASP system were obtained. The results show that the secondary-side water inventory of steam generator and operating time of ASP system isolation valve have little influence on starting performance of ASP system. The flow rate of ASP system decreases with the increase of drag coefficient of steam pipeline and backwater pipeline. The flow rate of ASP system is unstable with reciprocating opening of vapor discharge to atmosphere valve(VDA), and it is recovered to stable state when VDA is closed. The peak value of flow rate of ASP system is mainly affected by the initial water volume of heat exchanger tube. The stable natural circulation is established during all the experiments.
引文
[1] 卢向晖,张吉胜,罗汉炎,等. 百万千瓦级压水堆核电厂二次侧非能动余热排出系统启动响应研究[J]. 原子能科学技术,2014,48(增刊):457-462. LU Xianghui, ZHANG Jisheng, LUO Hanyan, et al. Study on startup response of secondary passive residual heat removal system in 1 000 MWe PWR nuclear power plant[J]. Atomic Energy Science and Technology, 2014, 48(Suppl.): 457-462(in Chinese).
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[5] REYES J N, HOCHREITER L. Scaling analysis for the OSU AP600 test facility (APEX)[J]. Nuclear Engineering and Design, 1998, 186: 53-109.
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[7] LI Yuquan, CHANG Huajian, YE Zishen, et al. Analysis of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient[J]. Progress in Nuclear Energy, 2016, 88: 375-397.
[8] KIM Y S, CHOI K Y, PARK H S, et al. Commissioning of the ATLAS thermal-hydraulic integral test facility[J]. Annals of Nuclear Energy, 2008, 35: 1 791-1 799.
[9] LU Donghua, XIAO Zejun, CHEN Bingde. Investigation on scaling law for reactor natural circulation under motion conditions[J]. Annals of Nuclear Energy, 2010, 37(5): 691-700.
[10] LU Donghua, XIAO Zejun, CHEN Bingde. A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions[J]. Nuclear Engineering and Design, 2010, 240(11): 3 851-3 861.
[2] 宫厚军,郗昭,昝元峰,等. 基于RELAP5的二次侧非能动余热排出系统敏感性研究[J]. 核动力工程,2016,37(6):11-14. GONG Houjun, XI Zhao, ZAN Yuanfeng, et al. A sensitivity study on secondary side passive residual heat removal system based on RELAP5[J]. Nuclear Power Engineering, 2016, 37(6): 11-14(in Chinese).
[3] 肖泽军,陈炳德,卓文彬. AC600二次侧非能动余热排出系统应急给水箱注水启动自然循环过渡特性研究[J]. 核动力工程,1999,20(1):49-52. XIAO Zejun, CHEN Bingde, ZHUO Wenbin. Investigation on emergency feedwater tank injection water start-up natural circulation transition of AC600 secondary-side passive residual heat removal system[J]. Nuclear Power Engineering, 1999, 20(1): 49-52(in Chinese).
[4] SUN D C, LI Y, XI Z, et al. Experimental evaluation of safety performance of emergency passive heat removal system in HPR1000[J]. Nuclear Engineering and Design, 2017, 318: 54-60.
[5] REYES J N, HOCHREITER L. Scaling analysis for the OSU AP600 test facility (APEX)[J]. Nuclear Engineering and Design, 1998, 186: 53-109.
[6] 陈炼,常华健,李玉全,等. ACME整体性能试验设施工作压力选取方案分析[J]. 原子能科学技术,2011,45(10):1 215-1 220. CHEN Lian, CHANG Huajian, LI Yuquan, et al. Analysis on working pressure selection of ACME integral test facility[J]. Atomic Energy Science and Technology, 2011, 45(10): 1 215-1 220(in Chinese).
[7] LI Yuquan, CHANG Huajian, YE Zishen, et al. Analysis of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient[J]. Progress in Nuclear Energy, 2016, 88: 375-397.
[8] KIM Y S, CHOI K Y, PARK H S, et al. Commissioning of the ATLAS thermal-hydraulic integral test facility[J]. Annals of Nuclear Energy, 2008, 35: 1 791-1 799.
[9] LU Donghua, XIAO Zejun, CHEN Bingde. Investigation on scaling law for reactor natural circulation under motion conditions[J]. Annals of Nuclear Energy, 2010, 37(5): 691-700.
[10] LU Donghua, XIAO Zejun, CHEN Bingde. A new method to derive one set of scaling criteria for reactor natural circulation at single and two-phase conditions[J]. Nuclear Engineering and Design, 2010, 240(11): 3 851-3 861.