NST  >> Vol. 5 No. 3 (July 2017)

    Analysis on Transient Working Conditions for Main Water Feeding System of Floating Nuclear Power

  • 全文下载: PDF(512KB) HTML   XML   PP.185-193   DOI: 10.12677/NST.2017.53024  
  • 下载量: 246  浏览量: 436   国家科技经费支持


彭明民,管晓纳,李浩杰,刘现星,李刘杰:武汉第二船舶设计研究所,湖北 武汉

浮动核电站给水系统瞬态工况失水量给水流量Floating Nuclear Power Main Water Feeding System Transient Conditions Water Loss Feedwater Flow Rate



Based on the floating nuclear power plant main water feeding system, the water feeding process model from the outlet of deaerator to the outlet of the steam generator is established by using a one-dimensional fluid simulation software Flowmaster. The change of water quantity of steam generator in four transient processes of water supply system is analyzed, includes: a water pump trip in rated state, and standby pump interlock start; a water pump trip in rated state, and standby pump interlock start; main feed-regulating valve is in full open due to failure under no load; main feed-regulating valve is in full open due to failure under full load. The simulation results show that: steam generator water level changes within the scope of the requirements under the feed pump switching transient conditions, which cannot trip the reactor. And according to steam generator water supply curves under the transient conditions, the conservative water flow value is obtained, which is an input to the nuclear island safety analysis, and to make sure the reactor core do not departure from nucleate boiling under these transient conditions.

彭明民, 管晓纳, 李浩杰, 刘现星, 李刘杰. 浮动核电站给水系统瞬态分析[J]. 核科学与技术, 2017, 5(3): 185-193. https://doi.org/10.12677/NST.2017.53024


[1] Zhang, S.B., Luo, B.X., Qiao, X.B., et al. (2011) Feed Water System Transient Analysis of Nuclear Power Station. Advanced Materi-als Research, 347-353, 1557-1560.
[2] 吴清, 卢毅力. 秦山二期工程瞬态事故分析[J]. 核动力工程, 2003, 24(S1): 56-60.
[3] 付锴, 马立, 李洪凤. 利用Flowmaster对水锤现场的研究[J]. 制冷与空调, 2015, 29(5): 597-600.
[4] 陈海松, 张锡中, 孙永盛, 等. 基于FLOWMASTER的工程机械热平衡仿真分析[J]. 矿山机械, 2007(6): 118-121.
[5] 杨小华, 彭雪平, 罗必雄, 等. CPR1000核电常规岛工艺设计技术研究[M]. 武汉: 中国地质大学出版社, 2007.
[6] Luo, F., Zhou, T., Cheng, W. and Su, Z. (2012) Flowmaster in the Application of Auxiliary Feedwater Sys-tem’s Transient Operation. Power & Energy Engineering Conference, 2012, 1-5.
[7] 李遵基. 热工自动控制系统[M]. 北京: 中国电力出版社, 2004.
[8] 王晓东, 黄涛. CPR1000核电站主给水系统稳态及瞬态工况分析[J]. 吉林电力, 2014, 42(2): 39-41.
[9] 贾祥, 安婕铷, 靖剑平. AP1000核电厂主给水管线断裂事故瞬态特性分析[J]. 原子能科学技术, 2016, 50(8): 1422-1427.