期刊文献+

弥散核燃料燃烧演化过程中的关键力学问题 被引量:4

Key Mechanical Problems in Dispersion Nuclear Fuels During Their Burning Evolution Process
下载PDF
导出
摘要 为了实现核能的可持续发展,需要研发第四代先进核能系统,其同时具有高安全性、高经济性、核废料最小化和防核扩散的特点.加速器驱动的次临界系统(Accelerator-Driven Subcritical System,简称ADS)是具有上述特点的一种先进核能系统,弥散核燃料在其中具有良好的应用前景.弥散核燃料是一种非均质核燃料,在结构上类似于颗粒复合材料,也称为惰性基体燃料.本文主要针对ADS用弥散核燃料,给出其在反应堆高温、高压和辐照环境中的关键力学问题,阐述其所具有的多尺度和多场耦合特征,介绍其在理论建模和数值求解等方面的相关研究进展,并提出研究展望. In order to realize the sustainable development of nuclear energy, research and development for the Generation-IV advanced nuclear systems need to be performed. They should have the characteristics being of high safety and economic benefits together with minimal wastes and proliferation resistance. Accelerator-Driven Subcritical System(ADS) is such a kind of advanced system. The performances of nuclear fuels directly relate to the safety, the economic benefits and the reliability of nuclear reactors, and dispersion nuclear fuels have a promising application prospect in advanced nuclear systems. Dispersion nuclear fuels are a kind of heterogeneous fuel, similar to particle composites in the structure, and are also called Inert-Matrix Fuels(IMF). Mainly for the dispersion nuclear fuels used in ADS, the key mechanical problems under the high-temperature, high-pressure and irradiation environment are given in this review and the characteristics of multi-scale and multi-field coupling are elaborated. Besides, the relevant research status and progress in theoretical modeling and numerical solution are given and some research trends are pointed out.
作者 丁淑蓉 龚辛 赵云妹 崔羿 霍永忠 魏洪杨 DING Shurong;GONG Xin;ZHAO Yunmei;CUI Yi;HUO Yongzhong;WEI Hongyang(Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University, Shanghai 200433, Chin)
出处 《力学季刊》 CSCD 北大核心 2018年第1期1-21,共21页 Chinese Quarterly of Mechanics
基金 国家自然科学基金(11772095 11572091 91226102 11172068 10772049) 国家重点研发计划(2016YFB0700103) 中国核动力研究设计院核反应堆系统设计技术重点实验室项目 中国科学院近代物理研究所项目(XDA03030000)
关键词 弥散(非均质)核燃料 惰性基体燃料 颗粒复合材料 辐照效应 本构方程 多尺度和多场耦合 dispersion (heterogeneous) nuclear fuels inert matrix fuel particle composites irradiation effects constitutive equations multi-scale and multi-field coupling
  • 相关文献

参考文献4

二级参考文献56

  • 1唐纳德·奥兰德,核反应堆燃料元件基本问题.上,1983年,295页
  • 2Massih,A.R. and Forsberg,K., Calculation of grain boundary gaseous swelling in UO2. Journal of Nuclear Materials, 2008, 377: 406-408.
  • 3Azevedo,C.R.F., A review on neutron-irradiation-induced hardening of metallic components. Engineering Failure Analysis, 2011, 18: 1921-1942.
  • 4Pieroy, G.B., Mechanisms for the in-reactor creep of zirconium alloys. Journal of Nuclear Materials, 1968, 26: 18-50.
  • 5Soba,A. and Denis,A., Simulation with DIONISIO 1.0 of thermal and mechanical pellet-cladding interaction in nuclear fuel rods. Journal of Nuclear Materials, 2008, 374: 32-43.
  • 6Denis,A. and Soba,A., Simulation of pellet-cladding thermomechanical interaction and fission gas release. Nuclear Engineering and Design, 2003, 223: 211-229.
  • 7Feltus,M.A. and Lee,K., Evaluation of the FRANCO finite element fuel rod analysis code. Annals of Nuclear Energy, 1996, 23(7): 553-565.
  • 8Marchal,N., Campos,C. and Garnier,C., Finite element simulation of Pellet-Cladding Interaction (PCI) in nuclear fuel rods. Computational Materials Science, 2009, 45: 821-826.
  • 9Struzik,C., Moyne,M. and Piron,J.P., High burn-up modeling of UO2 and MOX fuel with ME- TEOR/TRANSURANUS version 1.5. ANS International Topical Meeting on Light Water Reactor Puel Performance, Portland., 1997.
  • 10Newman,C, Hansen,G. and Gaston,D., Three dimensional coupled simulation of thermomechanics, heat, and oxygen diffusion in UO2 nuclear fuel rods. Journal of Nuclear Materials, 2009, 392: 6-15.

共引文献39

同被引文献21

引证文献4

二级引证文献6

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