U_3Si_2燃料芯块的制备与显微组织研究
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摘要
使用电弧熔炼破碎制备U_3Si_2粉末,通过粉末冶金工艺制备获得U_3Si_2燃料芯块,研究了芯块制备过程中U_3Si_2芯块成型能力以及烧结工艺对密度和显微组织的影响。结果表明,加入质量分数为0.5%的聚乙二醇(PEG)成型剂,在260～300MPa压力下压制成型,在1550℃烧结2～4h后,U_3Si_2芯块密度最高达到11.4 g/cm~3,达到理论密度的的93%以上;芯块晶粒大小均匀,约为60μm,局部区域存在着少量U相或UO_2相夹杂;芯块的热导率明显优于UO_2,且随温度的升高,其热导率呈线性升高趋势。
Uranium silicide is formed from ingot of uranium and silicon in near stoichiometric quantities by arc melting. And then uranium silicide pellets were produced by conventional powder metallurgy. The effect of pellet compression molding and sintering on density and the microstructure of U_3Si_2 pellets were studied. It turned out that,0.5% of PEG was added to be binder and the green pellets was got with a pressure ranging from approximately 260 to 300 MPa, then the pellets were sintered with a temperature of 1550°C for 2-4 h. To this end, high phase purity U_3Si_2 with density 11.4 g/cm~3,which is above 93% of theory density, is produced. The pellet size is uniform and the average grain size is about 60μm, but there is a little U or UO_2 impurity in sample U_3Si_2 pellet. The thermal conductivity of U_3Si_2 pellet is superior to UO_2, and rise approximate linearity with the increasing of temperature.
Uranium silicide is formed from ingot of uranium and silicon in near stoichiometric quantities by arc melting. And then uranium silicide pellets were produced by conventional powder metallurgy. The effect of pellet compression molding and sintering on density and the microstructure of U_3Si_2 pellets were studied. It turned out that,0.5% of PEG was added to be binder and the green pellets was got with a pressure ranging from approximately 260 to 300 MPa, then the pellets were sintered with a temperature of 1550°C for 2-4 h. To this end, high phase purity U_3Si_2 with density 11.4 g/cm~3,which is above 93% of theory density, is produced. The pellet size is uniform and the average grain size is about 60μm, but there is a little U or UO_2 impurity in sample U_3Si_2 pellet. The thermal conductivity of U_3Si_2 pellet is superior to UO_2, and rise approximate linearity with the increasing of temperature.
引文
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[2]Leenaers A,Van den Berghe S,Koonen E,et al.Microstructure of U3Si2 fuel plates submitted to a high heat flux[J].Journal of nuclear materials,2004,327(2-3):121-129.
[3]Durazzo M,de Carvalho E F U,Silva A M S,et al.Current status of U3Si2 fuel elements fabrication in Brazil[C].Prague:International Meeting on Reduced Enrichment for Research and Test Reactors-RERTR2007,2007:23-27.
[4]Harp J M,Lessing P A,Hoggan R E.Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation[J].Journal of Nuclear Materials,2015,466:728-738.
[5]White J T,Nelson A T,Dunwoody J T,et al.Thermophysical properties of U3Si2 to 1773 K[J].Journal of Nuclear Materials,2015,456:442-448.
[6]B?ning K,Petry W.Test irradiations of full-sized U3Si2-Al fuel plates up to very high fission densities[J].Journal of Nuclear Materials,2009,383(3):254-263.
[7]Gan J,Jr D D K,Miller B D,et al.Microstructure of the irradiated U3Si2/Al silicide dispersion fuel[J].Journal of Nuclear Materials,2011,419(1):97-104.
[8]Albarhoum M.The use of U3Si2,dispersed fuel in low-power research reactors[J].Annals of Nuclear Energy,2011,38(5):1206-1210.
[9]Berche A,Rado C,Rapaud O,et al.Thermodynamic study of the U-Si system[J].Journal of Nuclear Materials,2009,389(1):101-107.
[10]Snelgrove J L,Domagala R F,Hofman G L,et al.The use of U3Si2 dispersed in aluminum in plate-type fuel elements for research and test reactors[R].Chicago:Argonne National Lab.,1987.
[11]Wiencek T C.Summary report on fuel development and miniplate fabrication for the RERTR Program,1978 to1990[R].Washington D.C.:Office of Scientific&Technical Information Technical Reports,1995.
[12]Salibasilva A M,Durazzo M,De Carvalho E F U,et al.Fabrication of U3Si2 powder for fuels used in IEA-R1nuclear research reactor[J].Materials Science Forum,2008,591-593:194-199.