非能动IVR-ERVC试验装置的流动特性初步研究
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摘要
本文采用RELAP5/MOD3对全高度非能动的压力容器外部冷却(External Reactor Vessel Cooling,ERVC)一维传热与流动特性试验装置REPEC-II,进行了装置流道流动特性的预测计算,并结合REPEC-II的部分工况的试验结果,初步分析了ERVC流道的自然循环能力与循环流动特性。计算结果与实测数据之间一致性较好;可视化观测与计算、实测结果之间互相印证,揭示了部分流道流动及不稳定性机理特征;运用模拟与预测计算还可进一步研究装置的流道流动特性,并用于后续试验与应用的规划与优化。
Background:Through External Reactor Vessel Cooling(ERVC) to achieve the aim of In-Vessel Retention(IVR) is an important severe accident mitigation measure.After the Fukushima nuclear power plant severe accident,IVR-ERVC gains more and more attention.A full-scale IVR-ERVC engineering verification facility REPEC-II was constructed by Shanghai Jiao Tong University.Purpose:To study in-vessel retention by external reactor vessel cooling in large-scale advanced pressurized water reactor under severe accident conditions and meet the demand of verifying the validity of severe accident mitigation.Methods:The flow characteristics of the passages in some parts of the experiment conditions were calculated by RELAP5/MOD3.The natural circulation flow capabilities and features and the typical flashing eruption phenomenon in the experiment on the REPEC-II were preliminarily analyzed.Results and Conclusion:Comparative analysis showed that the calculated results were consistent well with the measured data and visual observation,and basically reflected the reliability of the calculations.Preliminary indication of the flow characteristics of the facility can be further analyzed in-depth,and applied to plan of follow-up experiments.
Background:Through External Reactor Vessel Cooling(ERVC) to achieve the aim of In-Vessel Retention(IVR) is an important severe accident mitigation measure.After the Fukushima nuclear power plant severe accident,IVR-ERVC gains more and more attention.A full-scale IVR-ERVC engineering verification facility REPEC-II was constructed by Shanghai Jiao Tong University.Purpose:To study in-vessel retention by external reactor vessel cooling in large-scale advanced pressurized water reactor under severe accident conditions and meet the demand of verifying the validity of severe accident mitigation.Methods:The flow characteristics of the passages in some parts of the experiment conditions were calculated by RELAP5/MOD3.The natural circulation flow capabilities and features and the typical flashing eruption phenomenon in the experiment on the REPEC-II were preliminarily analyzed.Results and Conclusion:Comparative analysis showed that the calculated results were consistent well with the measured data and visual observation,and basically reflected the reliability of the calculations.Preliminary indication of the flow characteristics of the facility can be further analyzed in-depth,and applied to plan of follow-up experiments.
引文
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2 Zhao G Z,Cao X R,Shi X W.Study theoretically on two-phase circulation flow characteristics under ERVC condition in advance PWR[J].Progress in Nuclear Energy,2013,67:104-113
3 Theofanous T G,Syri S.The coolability limits of a reactor pressure vessel lower head[J].Nuclear Engineering and Design,1997,169(1-3):59-76
4 Park R J,Ha K S,Kim S B,et al.Two-phase natural circulation flow of air and water in a reactor cavity model under a sever vessel accident[J].Nuclear Engineering and Design,2006,236(23):2424-2430
5 Wang J R,Chang H J,Zheng W X,et al.In-vessel retention of molten core debris for CAP1400[C].Presented at the 18th International Conference on Nuclear Engineering,Xi'an,China,2010
6 李飞,李永春,程旭.针对REPEC加热实验的RELAP5程序模拟与分析[J].原子能科学技术,2012,46(7):815 -820LI Fei,LI Yongchun,CHENG Xu.Simulation and analysis on REPEC heating experimental mechanism[J].Atomic Energy Science and Technology,2012,46(7):815-820
7 Inada F,Furuya M,Yasuo A.Thermo-hydraulic instability of boing natutal circulation loop induced by flashing[J].Nuclear Engineering and Design,1999,200(2000):187-199