YUAN Tianhong, CAI Qi, YU Lei, HAO Jianli. Effect of Bypass Flow on Operation Characteristic of Primary Side Passive Residual Heat Removal System[J]. Atomic Energy Science and Technology, 2019, 53(11): 2169-2175. DOI: 10.7538/yzk.2019.youxian.0360
Citation: YUAN Tianhong, CAI Qi, YU Lei, HAO Jianli. Effect of Bypass Flow on Operation Characteristic of Primary Side Passive Residual Heat Removal System[J]. Atomic Energy Science and Technology, 2019, 53(11): 2169-2175. DOI: 10.7538/yzk.2019.youxian.0360

Effect of Bypass Flow on Operation Characteristic of Primary Side Passive Residual Heat Removal System

More Information
  • The passive residual heat removal (PRHR) system plays an important role in the safe operation of the reactor. However, studies have shown that the bypass flow in the primary system increases the flow rate of reactor core, which increases the flow resistance and enhances the heat transfer in the core. Therefore, operation characteristics of the system become complicated, and the effect of the bypass flow needs to be analyzed. Based on the one-dimensional N-S equation, the operational characteristic analysis model of the PRHR system considering the bypass flow was established and verified. Then the mechanism of the bypass flow was revealed, and its influence on the operating characteristics of the PRHR system was analyzed. The results show that the existence of bypass flow reduces the heat-removal capacity of the PRHR system, which affects the passive safety of the reactor. The influence of bypass flow needs to be considered in the design and safety analysis of the reactor PRHR system.
  • [1]
    IAEA. Passive safety systems and natural circulation in water cooled nuclear power plants, IAEA TECDOC-1624[R]. Vienna: IAEA, 2009.
    [2]
    IWAMURA T, MURAO Y, ARAYA F, et al. A concept and safety characteristics of JAERI passive safety reactor[J]. Progress in Nuclear Energy, 1995, 29: 397-404.
    [3]
    周慧辉,彭传新,徐建军,等. 非能动余热排出系统长期冷却特性实验研究[J]. 核动力工程,2017,38(2):43-45.ZHOU Huihui, PENG Chuanxin, XU Jianjun, et al. Experimental study on long-time cooling characteristics of passive residual heat removal system[J]. Nuclear Power Engineering, 2017, 38(2): 43-45(in Chinese).
    [4]
    王盟,陈薇,吕焱燊. 非能动余热排出换热器优化设计研究[J]. 原子能科学技术,2015,49(3):455-459.WANG Meng, CHEN Wei, LV Yanshen. Research on optimal design of passive residual heat removal heat exchanger[J]. Atomic Energy Science and Technology, 2015, 49(3): 455-459(in Chinese).
    [5]
    黄志刚,张妍,彭传新,等. 换料水箱初始水温对非能动余热排出系统运行特性影响试验研究[J]. 核动力工程,2017,38(5):14-17.HUANG Zhigang, ZHANG Yan, PENG Chuanxin, et al. Experimental study of the effect of original IRWST temperature on PRHRS operation characteristics[J]. Nuclear Power Engineering, 2017, 38(5): 14-17(in Chinese).
    [6]
    肖三平,陈树山,吴昊. 非能动余热排出换热器在主给水管道断裂事故下的冷却能力研究[J]. 原子能科学技术,2016,50(3):454-458.XIAO Sanping, CHEN Shushan, WU Hao. Cooling performance of PRHR HX in main feedwater line break accident[J]. Atomic Energy Science and Technology, 2016, 50(3): 454-458(in Chinese).
    [7]
    齐实,周涛,李兵,等. 基于灰色关联度的AP1000非能动余热排出系统参数敏感度分析[J]. 核动力工程,2017,38(6):107-112.QI Shi, ZHOU Tao, LI Bing, et al. Sensitivity analysis for passive residual heat removal system of AP1000 based on grey correlation degree[J]. Nuclear Power Engineering, 2017, 38(6): 107-112(in Chinese).
    [8]
    POPP D M. AP1000 european design control document[M]. USA: Westinghouse Electric Company, 2010.
    [9]
    LAFI A Y, REYES J N. Comparative study of station blackout counterpart tests in APEX and ROSA/AP600[J]. Nuclear Technology, 2000, 130: 177-183.
    [10]
    杨帆,张丹,谭长禄,等. 海洋条件对浮动式核电厂事故后自然循环特性影响研究[J]. 核动力工程,2015,36(3):148-151.YANG Fan, ZHANG Dan, TAN Changlu, et al. Effect of marine condition on feature of natural circulation after accident in floating nuclear power plant[J]. Nuclear Power Engineering, 2015, 36(3): 148-151(in Chinese).
    [11]
    VIJAYAN P K. Experimental observations on the general trends of the steady state and stability behavior of single-phase natural circulation loops[J]. Nuclear Engineering and Design, 2002, 215: 139-152.
    [12]
    YANG J, LIANG R, LIN Z K, et al. Transient analysis of AP1000 NPP under the similar Fukushima accident conditions[J]. Annals of Nuclear Energy, 2017, 108: 181-187.
    [13]
    王宝生,王冬青,董化平,等. 全厂断电事故下AP1000非能动余热排出系统瞬态特性数值分析[J]. 原子能科学技术,2013,47(9):1514-1521.WANG Baosheng, WANG Dongqing, DONG Huaping, et al. Numerical analysis on transient characteristics of AP1000 passive residual heat removal system under station blackout accident[J]. Atomic Energy Science and Technology, 2013, 47(9): 1514-1521(in Chinese).
    [14]
    章熙民,任泽霈,梅飞鸣. 传热学[M]. 5版. 北京:中国建筑工业出版社,2007:285-291.
    [15]
    徐钊,吴莘馨. 200 MW低温核供热堆非能动余热排出系统动态分析[J]. 核动力工程,2008,29(2):61-65.XU Zhao, WU Xinxin. Transient analysis of residual heat removal system used in 200 MW low temperature heating reactor[J]. Nuclear Power Engineering, 2008, 29(2): 61-65(in Chinese).

Catalog

    Article views (340) PDF downloads (1241) Cited by()

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return