期刊文献+

基于最小势能原理的快堆堆芯多组件接触非线性计算理论研究

Contact Nonlinear Computation Method for Multi-Subassemblies Interaction in Fast Reactor Core
原文传递
导出
摘要 重点研究堆芯多组件的接触非线性计算理论,证明俄罗斯学者Likhachev发展的方法的可扩展性和解决中国实验快堆(CEFR)堆芯组件变形接触计算的可行性。在Likhachev发展的组件接触非线性方法基础上,考虑组件有3个可能的接触高度,建立变形协调条件和系统势能方程,利用最小势能原理求解接触力。为了简化推导,使用正交变换和拉格朗日对偶问题变换等方法。研究结果将接触非线性计算化为带不等式约束条件的二次函数极值优化问题。结论:Likhachev方法可以由2个接触高度扩展到3个接触高度,具备一般性;多组件接触非线性转化为最优化数学理论中的常规问题,数值上可解。 The study focuses on the contact nonlinear computation method for multi-subassemblies interaction, and tries to verify the extendibility of the method proposed by Likhachev and the viability of resolving CEFR subassembly contact problem. Based on the computation method developed by Likhachev, the consistent deformation conditions and the system potential energy equations for multi-subassemblies are established at three contact levels instead of two levels. The minimum potential energy principle is utilized to acquire the contact forces. For simplicity, orthogonal transform and Lagrangian-double-problem transformation are used. Finally, the nonlinear contact analysis turns into the optimization of a quadratic function with conditional inequality constraints. Conclusions are as follows: Likhachev method can be extended for three contact levels from two, and is generally practicable; the final derived expression is a common problem in optimization theory, which could be easily solved numerically.
作者 高付海 李楠
出处 《核动力工程》 EI CAS CSCD 北大核心 2015年第5期50-53,共4页 Nuclear Power Engineering
基金 国家高技术研究发展计划(863计划)资助(2011AA050302)
关键词 多组件 接触 最小势能 优化 Multi-subassemblies, Contact, Minimum potential energy, Optimization
  • 相关文献

参考文献4

  • 1高付海,付浩,李楠,杨孔雳,王明政.计入辐照效应的快堆燃料组件外套管截面变形有限元分析[J].核技术,2013,36(4):319-323. 被引量:2
  • 2查波得卡著,李耀鑫译.快堆燃料组件运行性能[M].北京:中国原子能科学研究院快堆研究中心,1994.
  • 3Likhachev Yu I, Matveenko L V. Interaction forces and deformation of fast-reactor fuel assemblies[J]. Atomic Energy, 1985, 58(4), DOI: 10.1007/BF01207212, 259-265.
  • 4袁亚湘,孙文瑜.最优化理论与方法[M].北京:科学出版社,2010.

二级参考文献6

  • 1HARMONIE user manual[R]. CADARACHE, CEA, France. 1986:1-10.
  • 2Likhachev Yu I, Matveenko L V. Interaction forces and deformation of fast-reactor fuel assemblies[J]. DOI:10.1007/BF01207212. Atomic Energy, 1985, 58(4): 259-265.
  • 3Masatoshi NAKAGAWA. Verification and validation of core mechanical performance code ARKAS with IAEA benchmark problems (II)[J] and Technology, 1993, 30(5) Journal of Nuclear Science 389-412.
  • 4Waiters L C, McVay G L, Hudman G D. Irradiation-induced creep in 316 and 304L stainless steels[C]. Proc of Int Conf Rad Effects in Breeder Reactor Structural Materials. Scottsdale, Arisona. 1977:277-294.
  • 5ABAQUS User Manual[R], Version 6.6. HKS Inc Pawtucket, USA, 2006.
  • 6付浩,王明政,文静,高付海,李楠,杨孔雳.快堆燃料组件六角形外套管截面变形的计算方法研究[J].核科学与工程,2012,32(2):138-142. 被引量:3

共引文献3

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