期刊文献+

UO_2弥散型燃料辐照后高温失效时显微分析 被引量:10

Microstructural Analysis of Irradiated UO_2 Dispersed Fuel during High Temperature Failure
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摘要 对辐照后燃料板进行退火试验,用显微镜观察了UO2颗粒的微观形貌随着温度的升高的变化情况。在高温下裂变气体膨胀,在UO2颗粒内气孔贯通形成裂纹穿破涂层,引起UO2颗粒局部破碎脱落,UO2涂层外的反应层由于高温加剧的扩散反应还形成了明显的孔洞。 The blister annealing has been performed on UO2 dispersed fuel plate under various tempera-ture conditions.The microstructure of UO2 particles changing with the rise of temperature is studied by using the microscope.Fission gas releases at high temperature and the bubbles burst the coat to generate cracks and result in the local fracture and fall off of UO2 particles.A lot of holes occur in the reaction layer outside of UO2 coat because of the diffusion reaction intensified by the high temperature.
出处 《核动力工程》 EI CAS CSCD 北大核心 2012年第1期74-77,共4页 Nuclear Power Engineering
基金 四川省青年基金(08ZQ026-024)
关键词 弥散燃料 辐照 高温失效 显微形貌 Dispersed fuel Irradiation High temperature failure Microstructure
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参考文献2

  • 1Hofinan G L, Yeon Soo Kim, Ho Jin Ryu, et al. Improved Irradiation Behavior of U-Mo/AI Dispersion Fuel[C]. 11^th International Topical Meeting on Research Reactor Fuel Management, Lyon, France, 2007.
  • 2Keiser D D, Robinson A B, Janney D E,et al. Results of Recent Microstructural Characterization of Irradiated U-Mo Dispersion Fuels with A1 Alloy Matrices that Contaln Si[C]. 12^th International Topical Meeting on Re- search Reactor Fuel Management, Hamburg, Germany, 2008.

同被引文献28

  • 1吕俊男,赵毅,龙冲生.弥散燃料细观失效机理的力学建模及参数分析[J].核动力工程,2020(S01):178-182. 被引量:3
  • 2杨文斗.反应堆材料学[M].北京:原子能出版社,2006:195-202.
  • 3TERRANI K A. Fabrication and preliminary evaluation of metal matrix microencapsulated fu- els[J]. Journal of Nuclear Materials, 2012, 427: 79-86.
  • 4WEIR J R. A failure analysis for the low-temper- ature performance of dispersion fuel elements, ORNL-2902[R]. USA: ORNL, 1961.
  • 5BECK S D. Failure analysis of dispersion fuel el- ements based on matrix cracking, APAEMEMO- 294[R]. USA: ORNL, 1961.
  • 6DING Shurong, JIANG Xin, HUO Yongzhong, et al. Reliability analysis of dispersion nuclear fuel elements[J]. Journal of Nuclear Materials, 2008, 374: 453-460.
  • 7UNE K K, SHIRATORI N T, HAYASHI K. Rim structure formation of isothermally irradia- ted UO2 fuel discs[J]. Journal of Nuclear Mate- rials, 2001, 288: 20-28.
  • 8ROMANO A. Evolution of porosity in the high- burnup fuel structure[J]. Journal of Nuclear Ma- terials, 2007, 361:62-68.
  • 9TERRANI K A. Fabrication and preliminary evaluation of metal matrix microencapsulated fuels[J]. Journal of Nuclear Materials, 2012, 427: 79-86.
  • 10REST J. The DART dispersion analysis research tool: A mechanistic model for predicting fission- product induced swelling of aluminum dispersion fuels, ANL295/36[R]. USA: ANL, 1995.

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