The martensite steels are accepted material used in nuclear power plant.In this study,self-ion irradiation was used to simulate the damage caused by fast neutrons in two kinds of martensite steels,SIMP and T91,under t...The martensite steels are accepted material used in nuclear power plant.In this study,self-ion irradiation was used to simulate the damage caused by fast neutrons in two kinds of martensite steels,SIMP and T91,under the temperature of 300℃.The contrast experiment on the steel samples was carried out with 352.8 MeV Fe-ions.S parameter is a statistical conclusion about vacancy damage caused by irradiation,and it is positively related to the density of vacancy defects Figs.1 and 2 show the change of the S parameter with the irradiation dose.Whereas Figs.3 and 4 show the different S parameters for two kind of steels.展开更多
Due to its unique properties, e:g: high melting temperature, high thermal conductivity and low sputtering erosion, tungsten has been selected as one of the most promising candidate materials for the divertor in ITER a...Due to its unique properties, e:g: high melting temperature, high thermal conductivity and low sputtering erosion, tungsten has been selected as one of the most promising candidate materials for the divertor in ITER and future fusion devices. In the extreme environment of fusion reactors, tungsten will not only be exposed to high energy particles such as hydrogen, helium and neutrons, which lead to heavy radiation damages, but also suffer from the combined high thermal fluxes and high mechanical stresses.展开更多
Tungsten has been selected as one of the most promising candidate materials for the divertor in the International Thermonuclear Experimental Reactor (ITER) and future fusion devices due to its unique properties, e:g: ...Tungsten has been selected as one of the most promising candidate materials for the divertor in the International Thermonuclear Experimental Reactor (ITER) and future fusion devices due to its unique properties, e:g: high melting temperature, high thermal conductivity and low sputtering erosion. In fusion reactors, tungsten will be exposed to high-energy particles, which result in microstructure and property changes[1], affecting the lifetime of divertor and reactor.展开更多
Due to its good physical properties such as low coefficient, high thermal conductivity, high resistance of irradiation swelling, and good geometric stability, the F/M steel T91 and SIMP are two kinds of accepted mater...Due to its good physical properties such as low coefficient, high thermal conductivity, high resistance of irradiation swelling, and good geometric stability, the F/M steel T91 and SIMP are two kinds of accepted material used in nuclear reactor. So it’s necessary for us to make some research on them.展开更多
The RAFM (Reduced Activation Ferritic/Martensitic) steel is considered as one of the promising candidatestructural materials for LFRs (Lead alloy-cooled Fast Reactors) and ADS (Accelerator Driven Sub-critical system),...The RAFM (Reduced Activation Ferritic/Martensitic) steel is considered as one of the promising candidatestructural materials for LFRs (Lead alloy-cooled Fast Reactors) and ADS (Accelerator Driven Sub-critical system),and its compatibility with liquid metal and radiation-resistant properties have been extensively studied because ofthe requirements of reliability and safety of the blanket[1]. A number of corrosion experiments of RAFMs (Eurofer97, T91 and 316L, etc.) in liquid LiPb alloy have been investigated, and the corrosion results show that these Febasedsteels suffered more serious corrosion attack from 480 to 550 ?C, and the corrosion layer is made of the oxidelayer (Fe3O4 and CrxFe3?xO4) at steels' surface. Generally speaking, during the stage degeneration of material, theformation of corrosion layer is one of the important features of the process[2]. Cracking, blistering, embrittlementand other changes in materials may be induced by corrosion layers, and the corrosion layers have independentcompositions, structures and radiation-resistant properties with distinguished from the alloy matrix. In a word, inorder to further clarify the applicability of Fe-based structural materials in nuclear facilities, we should study notonly the RAFM steel itself but also its corrosion layer (Fe3O4, mainly). So we report on modifications of mechanicalproperties of Fe3O4 corrosion layer irradiated with high-energy ion.展开更多
When swift heavy ion (SHI) passes through metallic multilayers, the kinetic energy of the ion is mainly depositedto target electron subsystem (electronic energy loss, Se) by the inelastic collisions involving excitati...When swift heavy ion (SHI) passes through metallic multilayers, the kinetic energy of the ion is mainly depositedto target electron subsystem (electronic energy loss, Se) by the inelastic collisions involving excitation and ionizationof the target atoms, which could induce atomic displacements and modify the interfacial structure [1?6]. Therefore,through the study of the process of the interfacial atoms diffusion induced by SHI irradiation, we could explore thepossible mechanism of atomic displacement induced by swift heavy ion irradiation.展开更多
Plasma-facing materials (PFMs) for a fusion reactor suffer hydrogen/helium plasma bombardment, neutronirradiation and high temperature, etc. Tungsten is a promising candidate PFM due to its low sputtering yield forthe...Plasma-facing materials (PFMs) for a fusion reactor suffer hydrogen/helium plasma bombardment, neutronirradiation and high temperature, etc. Tungsten is a promising candidate PFM due to its low sputtering yield forthe light elements, high thermal conductivity, high mechanical strength, and high melting point. Helium couldbe introduced by helium bombardment and neutron irradiation and trapped in tungsten at different sinks. It ispossible that the trapped helium atoms re-emit to the core plasma due to thermal desorption which affects thesafety. In this work, the thermal desorption behavior of helium implanted into tungsten at different temperatureswas investigated.展开更多
文摘The martensite steels are accepted material used in nuclear power plant.In this study,self-ion irradiation was used to simulate the damage caused by fast neutrons in two kinds of martensite steels,SIMP and T91,under the temperature of 300℃.The contrast experiment on the steel samples was carried out with 352.8 MeV Fe-ions.S parameter is a statistical conclusion about vacancy damage caused by irradiation,and it is positively related to the density of vacancy defects Figs.1 and 2 show the change of the S parameter with the irradiation dose.Whereas Figs.3 and 4 show the different S parameters for two kind of steels.
文摘Due to its unique properties, e:g: high melting temperature, high thermal conductivity and low sputtering erosion, tungsten has been selected as one of the most promising candidate materials for the divertor in ITER and future fusion devices. In the extreme environment of fusion reactors, tungsten will not only be exposed to high energy particles such as hydrogen, helium and neutrons, which lead to heavy radiation damages, but also suffer from the combined high thermal fluxes and high mechanical stresses.
文摘Tungsten has been selected as one of the most promising candidate materials for the divertor in the International Thermonuclear Experimental Reactor (ITER) and future fusion devices due to its unique properties, e:g: high melting temperature, high thermal conductivity and low sputtering erosion. In fusion reactors, tungsten will be exposed to high-energy particles, which result in microstructure and property changes[1], affecting the lifetime of divertor and reactor.
文摘Due to its good physical properties such as low coefficient, high thermal conductivity, high resistance of irradiation swelling, and good geometric stability, the F/M steel T91 and SIMP are two kinds of accepted material used in nuclear reactor. So it’s necessary for us to make some research on them.
文摘The RAFM (Reduced Activation Ferritic/Martensitic) steel is considered as one of the promising candidatestructural materials for LFRs (Lead alloy-cooled Fast Reactors) and ADS (Accelerator Driven Sub-critical system),and its compatibility with liquid metal and radiation-resistant properties have been extensively studied because ofthe requirements of reliability and safety of the blanket[1]. A number of corrosion experiments of RAFMs (Eurofer97, T91 and 316L, etc.) in liquid LiPb alloy have been investigated, and the corrosion results show that these Febasedsteels suffered more serious corrosion attack from 480 to 550 ?C, and the corrosion layer is made of the oxidelayer (Fe3O4 and CrxFe3?xO4) at steels' surface. Generally speaking, during the stage degeneration of material, theformation of corrosion layer is one of the important features of the process[2]. Cracking, blistering, embrittlementand other changes in materials may be induced by corrosion layers, and the corrosion layers have independentcompositions, structures and radiation-resistant properties with distinguished from the alloy matrix. In a word, inorder to further clarify the applicability of Fe-based structural materials in nuclear facilities, we should study notonly the RAFM steel itself but also its corrosion layer (Fe3O4, mainly). So we report on modifications of mechanicalproperties of Fe3O4 corrosion layer irradiated with high-energy ion.
文摘When swift heavy ion (SHI) passes through metallic multilayers, the kinetic energy of the ion is mainly depositedto target electron subsystem (electronic energy loss, Se) by the inelastic collisions involving excitation and ionizationof the target atoms, which could induce atomic displacements and modify the interfacial structure [1?6]. Therefore,through the study of the process of the interfacial atoms diffusion induced by SHI irradiation, we could explore thepossible mechanism of atomic displacement induced by swift heavy ion irradiation.
文摘Plasma-facing materials (PFMs) for a fusion reactor suffer hydrogen/helium plasma bombardment, neutronirradiation and high temperature, etc. Tungsten is a promising candidate PFM due to its low sputtering yield forthe light elements, high thermal conductivity, high mechanical strength, and high melting point. Helium couldbe introduced by helium bombardment and neutron irradiation and trapped in tungsten at different sinks. It ispossible that the trapped helium atoms re-emit to the core plasma due to thermal desorption which affects thesafety. In this work, the thermal desorption behavior of helium implanted into tungsten at different temperatureswas investigated.
