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核电厂冷却水系统热工水力仿真研究

Research on Thermal Hydraulic Simulation of Cooling Water System in Nuclear Power Plant
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摘要 传统的阻力计算方法已经无法完成核电厂冷却水系统的测试及流量分配,也无法对运行模式进行准确的仿真论证,为此,文章提出核电站系统热工水力模型,并采用一维流体管网系统软件进行仿真验证,结果显示,该仿真建模方法更适用于核电厂的管网系统。 The traditional resistance calculation method cannot complete the test and flow distribution of the cooling water system of the nuclear power plant,nor can it accurately simulate the operation mode.To this end,a thermal hydraulic model of the nuclear power plant system was proposed,and one-dimensional fluid pipe network system software was used for simulation verification.The results showed that the simulation modeling method was more suitable for the nuclear power plant network system.
作者 刘广山 滕飞 LIU Guangshan;TENG Fei(Hainan Nuclear Power Co.,Ltd.,Changjiang 572733,China)
出处 《电工技术》 2020年第12期144-145,共2页 Electric Engineering
关键词 核电厂 冷却水 流量分配 热工水力 nuclear power plant cooling water flow distribution thermal hydraulic power
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  • 1林萌,杨燕华,胡锐,苏云,张荣华.RELAP5作为核电站模拟器热工水力系统程序的改造[J].核动力工程,2005,26(2):125-129. 被引量:7
  • 2周兴东,马学虎,兰忠,宋天一.滴状冷凝强化含不凝气的蒸气冷凝传热机制[J].化工学报,2007,58(7):1619-1625. 被引量:20
  • 3鲁钟琪.两相流与沸腾换热[M].北京:清华大学出版社,2002:27-32.
  • 4Gavrilenko G, Semukhin M. Heat-hydraulic tests of the reactor upper unit [R]. Test report LYG-1-JAB, TP-I003/04-TR-01, 02, 03, 04, 05 (Rev. A. 09. 2006), 06, 07, 08.
  • 5Norikov G, Grigoryer D. Testing of recirculation cooling systems for CPS driving actuators(KLA30)[R]. Test report LYG-1-KLA10, 20, 30, 40, 50, 60, TP- F001/ 04-TR-01, 2004.
  • 6Stelko M. Testing and adjustment of ventilation systems KLA30[R]. Test report LYG-2-KLA. TP-F001/01- TR-02, 2004.
  • 7Meng Lin,Dong Hou,Pengfei Liu. Main Control System Verification and Validation of NPP Digital I&C System Based on Engineering Simulator[J].Nuclear Engineering and Design,2010,(07):1887-1896.
  • 8LING AO Nuclear Power Company Ltd. Test Report,PL127RRCR60LSUM45GN (TP 1 RRC 60)[R].LANPC,2002.
  • 9Kukita Y, Yonomoto T, Asaka H, et al. ROSA/AP600 Testing: Facility Modifications and Initial Test Results [J]. Journal of nuclear science and technology, 1996, 33 (3) : 259-265.
  • 10Medich C, Rigamonti M, Martinelli R, et al. SPES-2, the full-height, full-pressure, test facility simulating the AP600 plant: Main results from the experimental campaign [ R ]. American Society of Mechanical Engineers, New York, NY (United States), 1995.

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