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	Irradiation testing of matrix material for spherical HTR-10 fuel elements
	Tang, C. ; Ziqiang Li ; Yanwen Zou ; Xiaoming Fu
	2010-05-10 ; 2010-05-10
关键词	Practical Experimental/ bending strength electrical resistivity fission reactor design fission reactor fuel moulding neutron effects porosity/ irradiation testing matrix material spherical HTR-10 fuel elements coated fuel particles reactor design high temperature gas-cooled reactor Russian IVV-2M reactor fast neutron porosity electrical resistance bending strength quasiisostatic room-temperature moulding process structural material temperature 1000 C/ A2842D Fission reactor fuel elements A2841D Fission reactor design A2850I Gas cooled reactors A8140L Deformation, plasticity and creep A6220F Deformation and plasticity A2842Q Fission reactor structural and shielding materials A6180H Neutron effects B8220B Nuclear reactors/ temperature 1.27315E+03 K
中文摘要	In order to evaluate if the fuel elements and their components (matrix material and coated fuel particles) can meet the design requirements of 10 MW high temperature gas-cooled reactor (HTR-10), an irradiation testing with four spherical fuel elements, 60 matrix material specimens of 5 mm * 5 mm * 40 mm and 13,500 coated fuel particles was performed in Russian IVV-2M reactor from July 2000 to February 2003. The irradiation temperature was 1000 degrees C. The fast neutron fluence of matrix material specimens reached 1.3*10/sup 21/cm/sup -2/ (E>0.1 MeV). Post-irradiation examination contained the visual inspection, dimension measurement and determining the density, porosity, specific electrical resistance and bending strength. The irradiation results are given in this paper, and show that the matrix material for spherical HTR-10 fuel elements made from the domestic raw materials and fabricated by the quasi-isostatic room-temperature moulding process is suitable as a structural material for spherical HTR fuel elements. [All rights reserved Elsevier].
语种	英语 ; 英语
出版者	Elsevier Science B.V. ; Netherlands
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/23064]
专题	清华大学
推荐引用方式 GB/T 7714	Tang, C.,Ziqiang Li,Yanwen Zou,et al. Irradiation testing of matrix material for spherical HTR-10 fuel elements[J],2010, 2010.
APA	Tang, C.,Ziqiang Li,Yanwen Zou,&Xiaoming Fu.(2010).Irradiation testing of matrix material for spherical HTR-10 fuel elements..
MLA	Tang, C.,et al."Irradiation testing of matrix material for spherical HTR-10 fuel elements".(2010).

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