期刊文献+

AP1000小破口事故下非能动氮气安注箱的瞬态特性研究 被引量:5

Study on Transient Characteristics of AP1000 Passive Nitrogen-Typed Accumulator During SBLOCA
在线阅读 下载PDF
导出
摘要 根据AP1000非能动氮气安全注入水箱的结构和工作原理建立了热工水力模型并开发了计算分析程序TACAP。利用TACAP计算得到了AP1000非能动氮气安全注入水箱在两种小破口失水事故(包括25.4cm等效直径冷管破口和5.08cm等效直径冷管破口)下的瞬态特性,得到了箱内水位及注入流量等关键参数的瞬态变化。计算结果表明:安注箱在小破口失水事故后能提供高效的安全注入,对一回路快速地进行冷却和降压,有效地缓解事故后果。TACAP计算结果与西屋公司NOTRUMP程序计算结果基本一致,表明了TACAP程序的适用性和正确性。 Based on the basic principle and structure of passive nitrogen-typed accumulators,the thermal-hydraulic model was built up and the transient analysis code for accumulator of AP1000(TACAP) was developed.In addition,the performance of the accumulators was analyzed during different cold leg small break loss of coolant accidents,including 25.4 cm equivalent diameter cold leg break and 5.08 cm equivalent diameter cold leg break.This study also brought about some key transient characteristics during these accidents,such as water level of tank and injection flow rate.The calculation result shows that the injection flow of accumulator can effectively lower temperature and reduce pressure of primary circuit.The calculation result of TACAP also shows good agreements with the calculation result performed by Westinghouse(USA) with NOTRUMP code,which demonstrates the applicability and the validity of TACAP.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第5期755-760,共6页 Atomic Energy Science and Technology
关键词 AP1000 安注箱 瞬态特性 AP1000 accumulator transient characteristics
  • 相关文献

参考文献11

  • 1林诚格,郁祖盛,欧阳予.能动安全先进核电厂APlOOO[M].北京:原子能出版社,2008:155-157.
  • 2REDFIELD J A. Pressurizer performance during loss of load tests at shipping port: Analysis and test[J].NuclApli, 1986, 81(4): 173- 186.
  • 3BARON R C. Digital simulation of nuclear pressuri- zer[J]. Nucl Soc Eng, 1973, 52(3):283-291.
  • 4KURIDAN R M, BEYNON T D. A linearized non steady state model for the pressurizer of the safe integral reactor concept[J].Progress in Nu clear Energy, 1998, 33(4): 421-438.
  • 5尤洪君,崔震华,程轶平.核动力稳压器多区非平衡模型[J].核动力工程,2001,22(2):133-137. 被引量:8
  • 6JOSE N, REYES J. AP600 and AP1000 passive saety system design and testing in APEX[R]. Vienna: IAEA, 2005.
  • 7张大林,秋穗正,苟军利,贾斗南.新型氮气稳压器系统稳态和瞬态特性研究[J].核动力工程,2006,27(z1):38-42. 被引量:5
  • 8McADAMS W H. Heat transfer[M]. America.. Harper Row, 1983: 369-380.
  • 9YOUSEF W W, TARASUK J D, McKEEN W J. Experimental study of natural heat transfer [J]. Journal of Heat Transfer, 1982, 104(4):493-500.
  • 10齐欣,杨金宝,许晋寿.传热学基础手册[M].北京:科学出版社,1992:430-431.

二级参考文献11

  • 1聂春福.压水堆蒸汽式稳压器.核动力工程,1987,8(3):24-34.
  • 2[1]Redfield J A. Pressurizer Performance During Loss of Load Test at Shippingport: Analysis and Test[J]. Nuclear Application, 1986, 4:173
  • 3[2]Baron R. C. Digital Simulation of a Nuclear Pressurizer [J]. Nuclear Science and Engineering, 1982, 73:447
  • 4[3]Seung Min Baek, Hee Cheon. No. A Nonequilibrium Three-Region Model for Transient Analysis of pressurized Water Reactor Pressurizer[J]. Nuclear Technology, 1986, 74:260
  • 5[4]Wilson, J F. The Velocity of Rising Steam in a Bubble Two-Phase Mixture[J]. Trans Am Nucl Soc. 1962, 5:151.
  • 6[5]Amir N. NAHAVANDI, Suresh MAKKENCHERY. An Improved Pressurizer Model with Bubble Rise and Condensate Drop Dynamics[J]. Nuclear Engineering and Design, 1970, 135:147
  • 7[3]Kuridan R M,Beynon T D.A Linearized Non Steady State Model for the Pressurizer of the Safe Integral Reactor Concept[J].Progress in Nuclear Energy,1998,33(4):421 ~ 438.
  • 8[5]McAdams W H.Heat Transfer[M].Harper & Row,New York,1983,369~380.
  • 9[6]Yousef W W,Tarasuk J D,McKeen W J.Experimental Study of Natural Heat Transfer[J].Journal of Heat Transfer,1982,104(4):493 ~ 500.
  • 10刘聚奎,唐传宝.俄罗斯一体化压水堆 ABV-6M 综述[J].核动力工程,1997,18(3):279-283. 被引量:12

共引文献10

同被引文献21

引证文献5

二级引证文献5

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部