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Improvement of carbon fiber surface properties using electron beam irradiation 被引量:5
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作者 Eddy Segura PINO Luci Diva Brocardo MACHADO claudia giovedi 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第1期39-41,共3页
Carbon fiber-reinforced advance composites have been used for structural applications,mainly on account of their mechanical properties.The main factor for a good mechanical performance of carbon fiber-reinforced com- ... Carbon fiber-reinforced advance composites have been used for structural applications,mainly on account of their mechanical properties.The main factor for a good mechanical performance of carbon fiber-reinforced com- posite is the interfacial interaction between its components,which are carbon fiber and polymeric matrix.The aim of this study is to improve the surface properties of the carbon fiber using ionizing radiation from an electron beam to obtain better adhesion properties in the resultant composite.EB radiation was applied on the carbon fiber itself before preparing test specimens for the mechanical tests.Experimental results showed that EB irradiation improved the ten- sile strength of carbon fiber samples.The maximum value in tensile strength was reached using doses of about 250 kGy.After breakage,the morphology aspect of the tensile specimens prepared with irradiated and non-irradiated car- bon fibers were evaluated.SEM micrographs showed modifications on the carbon fiber surface. 展开更多
关键词 碳纤维 表面性质 电子束辐射 改性
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Revisiting Stainless Steel as PWR Fuel Rod Cladding after Fukushima Daiichi Accident
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作者 Alfredo Abe claudia giovedi +1 位作者 Daniel de Souza Gomes Antonio Teixeira e Silva 《Journal of Energy and Power Engineering》 2014年第6期973-980,共8页
In the past, stainless steel was utilized as cladding in many PWRs (pressurized water reactors), and its performance under irradiation was excellent. However, stainless steel was replaced by zirconium-based alloy as... In the past, stainless steel was utilized as cladding in many PWRs (pressurized water reactors), and its performance under irradiation was excellent. However, stainless steel was replaced by zirconium-based alloy as cladding material mainly due to its lower neutron absorption cross section. Now, stainless steel cladding appears as a possible solution for safety problems related to hydrogen production and explosion as occurred in Fukushima Daiichi accident. The aim of this paper is to discuss the steady-state irradiation performance using stainless steel as cladding. The results show that stainless steel rods display higher fuel temperatures and wider pellet-cladding gaps than Zircaloy rods and no gap closure. The thermal performance of the two rods is very similar and the neutron absorption penalty due to stainless steel use could be compensating by combining small increase in U-235 enrichment and pitch size changes. 展开更多
关键词 Austenitic stainless steel cladding Zircaloy cladding PWR fuel rod steady-state fuel performance codes.
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