反应堆失流事故下堆芯自然循环冷却能力的模拟实验研究
Simulation Experimental Investigation on Capacity of Natural Circulation Cooling in Nuclear Reactor Core Under Loss-of-Flow Accident
-
摘要: 为分析不同热工参数对强迫循环向自然循环过渡过程及稳定自然循环阶段传热及流动特性的影响，在内径为6 mm的竖直实验段内开展实验，研究不同入口过冷度、热流密度及初始流量对强迫循环向自然循环过渡过程以及稳定自然循环过程的影响。实验结果表明：入口过冷度及热流密度对自然循环向强迫循环过渡过程及稳定自然循环过程的换热能力有明显影响，而初始流量对该过渡过程及稳定自然循环的换热能力的影响并不显著。Abstract: In order to analyze the influence of different thermal parameters on the characteristics of heat transfer and flowing during the transition from forced circulation to natural circulation and during the stable natural circulation, the experimental study was carried out in a vertical test section with 6 mm inner diameter. The experiment was carried out under different thermal-hydraulic conditions, including different inlet subcoolings, heat fluxes and initial mass fluxes. The experimental results show that the inlet subcooling and heat flux have great effect on the characteristics of flowing and the heat transfer during the transition from forced circulation to natural circulation, and also during the stable natural circulation period. However, the effect of the initial mass flux is not significant.
-
Keywords:
- flow boiling ,
- loss-of-flow accident ,
- natural circulation ,
- experimental simulation
-
-
[1] 姚青生,王章立,韩伟实,等. 自然循环向强迫循环过渡时的反应性变化[J]. 核动力工程,2008,29(3):18-23.YAO Qingsheng, WANG Zhangli, HAN Weishi, et al. Transitional reactivity variation from natural to forced circulation[J]. Nuclear Power Engineering, 2008, 29(3): 18-23(in Chinese). [2] 田兆斐，赵强，彭敏俊，等. 自然循环与强迫循环转换过渡过程研究[J]. 哈尔滨工程大学学报,2009,31(10):1389-1404.TIAN Zhaofei, ZHAO Qiang, PENG Minjun, et al. Study on transient characteristics of transition between natural circulation and forced circulation[J]. Journal of Harbin Engineering University, 2009, 31(10): 1389-1404(in Chinese). [3] 张龙飞,张大发,徐金良. 自然循环转强迫循环时反应堆功率瞬态特性研究[J]. 武汉理工大学学报:交通科学与工程版，2008,32(1):115-117.ZHANG Longfei, ZHANG Dafa, XU Jinliang. Study of reactor power’s transient performances for transition from natural to forced circulation[J]. Journal of Wuhan University of Technology: Transportation Science & Engineering, 2008, 32(1): 115-117(in Chinese). [4] CHENG S Y, PENG M J, TIAN Z F, et al. Study on control of natural circulation and forced circulation in nuclear power plant[C]∥Asia-Pacific Power and Energy Engineering Conference. Chengdu: [s.n.], 2010. [5] HIRANO M, SUDO Y. Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3[J]. Nuclear Science and Technology, 1986, 23(4): 352-368.
计量
- 文章访问数: 284
- HTML全文浏览量: 0
- PDF下载量: 1098
下载:
