期刊文献+

TVS-2M燃料棒制造参数对堆内性能影响的不确定性研究

Uncertainty Analysis of Manufacturer Parameters Impact on TVS-2M Fuel Rod Performance in Reactor
原文传递
导出
摘要 田湾核电站3、4号机组计划从首炉堆芯开始使用TVS-2M燃料。为了对前8个燃料循环中燃料棒稳态性能进行验证,根据保守性燃料制造参数进行选择,利用START-3程序开展了5个设计准则上的燃料棒性能校验工作。但是,上述传统方法的保守性并未得到验证,而且也无法开展燃料制造参数的敏感性研究。为此,将DAKOTA与START-3程序耦合,利用统计类的GRS方法,对田湾核电站3、4号机组中的TVS-2M燃料棒稳态性能的不确定性开展计算分析。结果表明:传统方法在燃料温度与包壳应力方面过于保守,而在包壳的轴向和径向应变方面则保守性不足;在燃料制造参数的敏感性方面,包壳内径和芯块外径的敏感度价值普遍较高;此外,燃料密度对燃料温度和燃料棒内压有较大影响。 TVS-2M fuel will be deployed in the TIANWAN NPP Unit 3&4 from the first batch In traditional method, the predicted conservative fuel manufacturer parameters will be used to analyze the fuel rod performance under steady state condition for the first 8 fuel cycles, which includes 5 fuel rod design criteria. But this conservative evaluation method can neither reflect the realities of the real world, nor analyze the sensitivities of the manufacturer parameters. Therefore, by coupling DAKOTA and START-3 codes, GRS method is used to calculate the fuel performance and to analyze the uncertainty. After compared with the traditional method, the results reveal that the traditional method not only overestimate the fuel temperature and cladding stress, but also underestimate the axial and radial strain, and the sensitivities of cladding inner diameter and pellet outer diameter are significant for fuel rod criteria.
出处 《核动力工程》 EI CAS CSCD 北大核心 2017年第4期134-138,共5页 Nuclear Power Engineering
关键词 GRS法 不确定性 制造参数 稳态性能 燃料棒 TVS-2M GRS method, Uncertainty, Manufacturer parameter, Steady state performance,Fuel rod, TVS-2M
  • 相关文献

参考文献3

二级参考文献37

  • 1Jernkvist L, Massih A. Models for Fuel Rod Behaviour at High Bumup, SKI Report 2005, 2004. 41-48. 被引量:1
  • 2Mardon P, Charquet D, Senevat J, et al. Update On The Development of Advanced Zirconium Alloys for PWR Fuel Rod Claddings. Portland, ANS, 1991.405-412. 被引量:1
  • 3Conover W J,崔恒健.实用非参数统计[M]. 3版.北京:人民邮电出版社,2006: 225-239. 被引量:2
  • 4OECD. CSNI status summary on utilization of best estimate methodology in safety analysis and licensing[R]. Paris: OECD, 1996. 被引量:1
  • 5LIN Chengge, LIU Zhitao, ZHAO Ruichang. Research on best estimate method in PWR loss of coolant accident[J]. Nuclear Safety, 2010 (1) : 1 12(in Chinese). 被引量:1
  • 6YOUNG M Y, BAJOREK S M, NISSLEY M E, et al. Application of code scaling applicability and uncertainty methodology to the large break loss of coolant[J].Nuclear Engineering and Design, 1998, 186(1-2): 39-52. 被引量:1
  • 7MATRIN R P, O'DELL D L. AREVA's realistic large break LOCA analysis methodology[J]. Nuclear Engineering and Design, 2005, 235 (16): 1 713-1 725. 被引量:1
  • 8HECK C. Best estimate plus uncertainty methodologies for non-LOCA applications[R]. Dubrovnik; 3D-SUNCOP Workshop, 2012. 被引量:1
  • 9SOLLIMA C, D' AURIA F, MISAK J, et al. Framework and strategies for the introduction of best estimate models into the licensing process [J]. Transactions of the American Nuclear Soci ety, 2005, 92: 378-380. 被引量:1
  • 10FREPOLI C. An overview of Westinghouse real istic large break LOCA evaluation model[J]. Science and Technology of Nuclear Installations, 2008. 被引量:1

共引文献10

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