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核动力装置非能动系统可靠性及参数敏感性分析 被引量:6

Reliability and Parameter Sensitivity Analysis of Passive System in Nuclear Power Plants
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摘要 在非能动安全功能可靠性方法(RMPS)框架下,对某型核动力装置非能动余热排出系统原理性试验系统的热工水力可靠性(TH-R)进行评估,并对影响系统可靠性的不确定性参数进行敏感性分析。相关结论有助于从可靠性角度增强对该非能动余热排出系统热工水力过程不确定性的认识,可用于指导系统的设计优化及运行管理。 Under the framework of RMPS (Reliability Methods for Passive Safety Functions), thermal-hydraulic reliability (TH-R) of an experimental facility is evaluated, and sensitivity analysis is applied for uncertainty parameters which has effects on the TH-R of the passive systems. Related conclusions contribute to understand the uncertainty of the thermal hydraulic processes of the passive residual system from the view of reliability. Results of reliability and sensitivity analysis can be used to guide the system optimal design and operation management.
作者 蒋立志 蔡琦 张永发 Jiang Lizhi Cai Qi Zhang Yongfa(Depaament of Nuclear Science and Engineering, Naval University of Engineering, Wuhan, 430033, Chin)
出处 《核动力工程》 EI CAS CSCD 北大核心 2017年第5期91-95,共5页 Nuclear Power Engineering
关键词 非能动系统 非能动安全功能可靠性方法(RMPS) 可靠性分析 参数敏感性分析 Passive system, RMPS, Reliability analysis, Parameter sensitivity analysis
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  • 1白楠,臧希年.用AC-600非能动余热排出系统实验评估RELAP5程序[J].核科学与工程,2004,24(2):125-128. 被引量:7
  • 2肖泽军,卓文彬,陈炳德,贾斗南,周连帮.中国先进压水堆非能动余热排出系统稳态特性研究[J].核动力工程,2005,26(5):436-442. 被引量:7
  • 3肖泽军,卓文彬,陈炳德,贾斗南.中国先进压水堆非能动余热排出系统瞬态特性研究[J].核动力工程,2005,26(6):548-553. 被引量:6
  • 4INTERNATIONAL ATOMIC ENERGY AGENCY. Natural circulation data and methods for advanced water cooled nuclear power plant designs[R]. IAEA-TECDOC-1281, Vienna: IAEA, 2002.
  • 5Hicken E F , Jaegers H. Passive decay heat removal from the core region[C]. Vienna: IAEA, 2002: 227- 233.
  • 6徐济均,贾斗南.沸腾传热和气液两相流[M].北京:原子能出版社,2001.
  • 7The RELAP5 Code Development Team. RELAPS/mod3 Code Manual[M]. USA: Idaho Engineering Laboratory, 1995.
  • 8IAEA. Natural circulation data and methods for advanced water cooled nuclear power plant designs, IAEA-TECDOC-1281 [ R]. Vienna: IAEA, 2000.
  • 9IAEA. Natural circulation in water cooled nuclear power plants, IAEA-TECDOC-1474 [R]. Vienna: IAEA, 2005.
  • 10郝亚雷.舰船核动力装置非能动余热排出系统的仿真研究[D].武汉:海军工程大学,2006.

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