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FA300燃料棒包壳疲劳分析

Analysis of the FA300 Fuel Rod Cladding Fatigue
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摘要 包壳疲劳是燃料棒安全分析的重要设计准则之一。与传统的包壳疲劳分析方法不同,基于300 MWt核电厂典型装载方案,采用统计学方法进行包壳疲劳性能分析。包壳疲劳分析中考虑的不确定性主要有:芯块直径、包壳直径、芯块密度、包壳蠕变、包壳生长及预充压力等方面,这些不确定性采用平方和的平方根(SRSS)方法进行统计。采用SRSS方法的包壳疲劳结果表明,包壳疲劳可以满足设计准则要求,与传统计算方法相比可以释放计算裕量。 Cladding Fatigue is one of the important design criteria of the fuel rod safety analysis. Different with traditional cladding fatigue analysis methods, cladding fatigue performance analysis is made based on a typical loading program of 300 MWt nuclear power plant, using statistical methods. The uncertainties considered in fatigue cladding analysis mainly includes: diameter of the pellet, the diameter of the cladding, the density of the pellet, the creep of the cladding, growth of the cladding and precharge pressure, etc., statistics of which is made by using the method of square root of the sum of the squares (SRSS). Results of cladding fatigue by using SRSS method show that the cladding fatigue can meet the requirements of design criteria, and can re- lease the calculated margin comparing with the traditional method,
出处 《能源与节能》 2013年第8期39-41,共3页 Energy and Energy Conservation
关键词 FA300 包壳疲劳分析 SRSS方法 FA300 cladding fatigue analysis method of SRSS
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参考文献3

  • 1United States Nuclear Regulatory Commission. NUREG-0800 Standard Review Plan[S].U.S.NRC,2007.
  • 2全国核能标准化技术委员会.压水堆核电厂燃料系统设计限值规定[S]北京:中国核工业总公司,1996.
  • 3Andrea Bucalossil,Alessandro Petruzzi. Role of Best Estimate Plus Uncertainty Methods in Major Nuclear Power Plant Modifications[J].Journal of Nuclear Science and Technology,2010,(08):671-683.doi:10.3327/jnst.47.671.

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