Due to its unique properties, such as favorable neutronic characteristic, low melting point(～125 ?C) and highboiling point (> 1 600 ?C), good natural circulation and chemical inertness with water and air (unlike s...Due to its unique properties, such as favorable neutronic characteristic, low melting point(～125 ?C) and highboiling point (> 1 600 ?C), good natural circulation and chemical inertness with water and air (unlike sodium), etc,lead bismuth eutectic (LBE) has been considered as perspective coolant and spallation target for accelerator drivensystems (ADS)[1;2]. The spallation structural materials of ADS will be long-term irradiated with fast neutrons whilesimultaneous being contact with LBE coolant. In the past few decades, irradiation or LBE corrosion behaviors invarious of materials have been massively investigated for the purpose of developing ADS. However, there are onlya few experiment data on the combined effect of irradiation and LBE corrosion on structural materials due to lackof related experimental setups[3;4]. Such tests are not only essential for ensuring the safety and reliability of ADS,but also necessary for building a database for licensing any materials for use in LBE cooled nuclear systems.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
Because of their good mechanical properties under irradiation up to 500 ?C, ferritic/martensitic steels are consideredto be the promising structural materials for advanced nuclear reactors. However, severe corrosion o...Because of their good mechanical properties under irradiation up to 500 ?C, ferritic/martensitic steels are consideredto be the promising structural materials for advanced nuclear reactors. However, severe corrosion of structuralmaterials occurs in the presence of LBE in advanced nuclear reactors, especially at high temperature[1]. Therefore,the selection of the structural material exposed to LBE is an extremely complex problem and compatibility testsare required.展开更多
With the implementation of the concept of new generation IV fission reactor,the proceedings of the plans of Accelerator Driven Sub-critical System(ADS)and International Thermonuclear Experimental Reactor(ITER),and the...With the implementation of the concept of new generation IV fission reactor,the proceedings of the plans of Accelerator Driven Sub-critical System(ADS)and International Thermonuclear Experimental Reactor(ITER),and the rapid development of space science,the selection of anti-irradiated material faces challenges of high energy neutron irradiation with high dose and thermal irradiation High-entropy alloys(HEAs),as a new class of metallic material composing with four or more principal elements in equal-molar or near equal-molar constituents,have drawn great attentions of material scientists in recent years[1].HEAs whose structure is similar with the metallic glass possesses high entropy effect,hysteresis diffusion effect,lattice distortion effect and the effect of the“cocktail”,all these effects make HEAs have excellent mechanical property,great corrosion resistance,strong oxidation resistance,and high temperature irradiation stability[2].展开更多
The gravity-driven dense granular flow target(DGT)is a new type of concept of high power spallation target proposed to satisfy ultra-high beam power in ADS system[1].Using gravity-driven dense solid particle flow as t...The gravity-driven dense granular flow target(DGT)is a new type of concept of high power spallation target proposed to satisfy ultra-high beam power in ADS system[1].Using gravity-driven dense solid particle flow as target material and heat carrier,the essential idea of the granular flow target is to treat the power deposit offline easily,while avoiding many fatal defects,such as unstable flow of liquid lead and bismuth(LBE),material corrosion and abrasion,chemical toxicity leakage.A potential solution is provided,in order to meet the ultimate challenge posed by the ADS system with tens of MW beam power.展开更多
Lead bismuth eutectic(LBE)has been proposed as a core coolant for Lead-cooled Fast Reactor(LFR)due to its several advantages,low melting point,chemically inert and good natural circulation[1].However,the LFR presents ...Lead bismuth eutectic(LBE)has been proposed as a core coolant for Lead-cooled Fast Reactor(LFR)due to its several advantages,low melting point,chemically inert and good natural circulation[1].However,the LFR presents a harsh environment where the core components and mainly steels will suffer not only from the irradiation damage produced by neutrons,but also from the corrosion induced by the liquid LBE.Over the past decades,the irradiation effect and corrosion mechanism of LBE in both ferritic/martensitic alloys and austenitic steels have been investigated separately by both experimental and theoretical approach.However,the synergistic effects of irradiation and LBE corrosion on structural materials have rarely been studied[2,3].展开更多
Silicon carbide(SiC)is regarded as an important material in nuclear energy system and semiconductor industry,because of its excellent physical,electronic and optical properties.It is inevitable that dense atomic He at...Silicon carbide(SiC)is regarded as an important material in nuclear energy system and semiconductor industry,because of its excellent physical,electronic and optical properties.It is inevitable that dense atomic He atoms produced by(n,)nuclear transmutation reaction.Due to the low solubility of He atoms in SiC,He atoms are easy to be trapped by vacancies to form helium-vacancy clusters.After thermal annealing,helium atoms will escape from vacancies,to form cavities.In semiconductor technology,He implantation-induced cavities have lots of important applications.Therefore,the study of He-implanted SiC is critical.He-implantation-induced cavities have been extensively investigated.He-implantation-induced dislocation loops also have been investigated.Chen et al.observed interstitial-type dislocation loops associated with He bubbles due to the release of bubble interior pressure via emitting interstitials[1].These interstitials agglomerate into dislocation loops.It is consistent with previous results observed in the case of He-implanted 6H-SiC[2].What’s more,Barbot et al.regarded that the growth of the Frank loops lead to the formation of stacking faults,which do not result from the agglomeration of interstitials[3].展开更多
In order to accumulate the experimental data for building accelerator driven sub-critical systems(ADS),a high temperature and high pressure water circuit setup has been built.It is mainly used to study heat transfer d...In order to accumulate the experimental data for building accelerator driven sub-critical systems(ADS),a high temperature and high pressure water circuit setup has been built.It is mainly used to study heat transfer deterioration of high temperature and high pressure water vapor in the circuit,flow instability mechanism and heat exchange efficiency of fuel rod in primary loop.Lots of similar experimental setups have been built by scientific research institution around the world[1-3].Unlike the existing experimental setup,flow rate of high temperature and high pressure water vapor was considered as a significant parameter to study above-mentioned research proposal.展开更多
Because of excellent electronic and optical properties,GaN has been used in the laser diodes,microwave,ultrahigh power switches and other fields.Due to an attractive process for selective region doping of semiconducto...Because of excellent electronic and optical properties,GaN has been used in the laser diodes,microwave,ultrahigh power switches and other fields.Due to an attractive process for selective region doping of semiconductor devices,ion implantation has widely been applied to GaN fabrication processing.However,ion implantation introduces extensive damage that can degrade the performance,properties as well as lifetimes of the devices.Thus,it is very important to understand the ion-beam damage processes in the fabrication of GaN-based devices.The effects of ion implantation into GaN have been extensively investigated.展开更多
Due to its favorable thermal-physical and chemical properties,lead-bismuth eutectic(LBE)is one of primary candidate materials for coolant in advanced nuclear reactors.However,severe corrosion of structural materials o...Due to its favorable thermal-physical and chemical properties,lead-bismuth eutectic(LBE)is one of primary candidate materials for coolant in advanced nuclear reactors.However,severe corrosion of structural materials occurs in the presence of LBE in advanced nuclear reactors,especially at high temperature[1;2].Therefore,the selection of the structural material exposed to LBE is an extremely complex problem and compatibility tests are required.Because of their good mechanical properties under irradiation up to 500℃,ferritic/martensitic steels are considered to be one of the promising structural materials for advanced nuclear reactors,and so the compatibility tests of SIMP and T91 steel specimens were conducted at 450℃with saturated oxygen.展开更多
Spallation target is one of the key constituent parts of the Accelerator Driven Sub-critical System(ADS),but the existing spallation targets are difficult to satisfy the power requirements of the commercial ADS in the...Spallation target is one of the key constituent parts of the Accelerator Driven Sub-critical System(ADS),but the existing spallation targets are difficult to satisfy the power requirements of the commercial ADS in the future.In order to solve this problem,the scientists of the Institute of Modern Physics(IMP)originally proposed a new concept—the granular flow spallation target[1]which is quite different from the current spallation targets in the world.This novel spallation target with complete intellectual property rights incorporates the advantages of existing solid spallation targets and liquid metal spallation targets.Solid particles are delivered to the outside of the target area for heat transfer.展开更多
文摘Due to its unique properties, such as favorable neutronic characteristic, low melting point(～125 ?C) and highboiling point (> 1 600 ?C), good natural circulation and chemical inertness with water and air (unlike sodium), etc,lead bismuth eutectic (LBE) has been considered as perspective coolant and spallation target for accelerator drivensystems (ADS)[1;2]. The spallation structural materials of ADS will be long-term irradiated with fast neutrons whilesimultaneous being contact with LBE coolant. In the past few decades, irradiation or LBE corrosion behaviors invarious of materials have been massively investigated for the purpose of developing ADS. However, there are onlya few experiment data on the combined effect of irradiation and LBE corrosion on structural materials due to lackof related experimental setups[3;4]. Such tests are not only essential for ensuring the safety and reliability of ADS,but also necessary for building a database for licensing any materials for use in LBE cooled nuclear systems.
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.
文摘Because of their good mechanical properties under irradiation up to 500 ?C, ferritic/martensitic steels are consideredto be the promising structural materials for advanced nuclear reactors. However, severe corrosion of structuralmaterials occurs in the presence of LBE in advanced nuclear reactors, especially at high temperature[1]. Therefore,the selection of the structural material exposed to LBE is an extremely complex problem and compatibility testsare required.
文摘With the implementation of the concept of new generation IV fission reactor,the proceedings of the plans of Accelerator Driven Sub-critical System(ADS)and International Thermonuclear Experimental Reactor(ITER),and the rapid development of space science,the selection of anti-irradiated material faces challenges of high energy neutron irradiation with high dose and thermal irradiation High-entropy alloys(HEAs),as a new class of metallic material composing with four or more principal elements in equal-molar or near equal-molar constituents,have drawn great attentions of material scientists in recent years[1].HEAs whose structure is similar with the metallic glass possesses high entropy effect,hysteresis diffusion effect,lattice distortion effect and the effect of the“cocktail”,all these effects make HEAs have excellent mechanical property,great corrosion resistance,strong oxidation resistance,and high temperature irradiation stability[2].
文摘The gravity-driven dense granular flow target(DGT)is a new type of concept of high power spallation target proposed to satisfy ultra-high beam power in ADS system[1].Using gravity-driven dense solid particle flow as target material and heat carrier,the essential idea of the granular flow target is to treat the power deposit offline easily,while avoiding many fatal defects,such as unstable flow of liquid lead and bismuth(LBE),material corrosion and abrasion,chemical toxicity leakage.A potential solution is provided,in order to meet the ultimate challenge posed by the ADS system with tens of MW beam power.
文摘Lead bismuth eutectic(LBE)has been proposed as a core coolant for Lead-cooled Fast Reactor(LFR)due to its several advantages,low melting point,chemically inert and good natural circulation[1].However,the LFR presents a harsh environment where the core components and mainly steels will suffer not only from the irradiation damage produced by neutrons,but also from the corrosion induced by the liquid LBE.Over the past decades,the irradiation effect and corrosion mechanism of LBE in both ferritic/martensitic alloys and austenitic steels have been investigated separately by both experimental and theoretical approach.However,the synergistic effects of irradiation and LBE corrosion on structural materials have rarely been studied[2,3].
文摘Silicon carbide(SiC)is regarded as an important material in nuclear energy system and semiconductor industry,because of its excellent physical,electronic and optical properties.It is inevitable that dense atomic He atoms produced by(n,)nuclear transmutation reaction.Due to the low solubility of He atoms in SiC,He atoms are easy to be trapped by vacancies to form helium-vacancy clusters.After thermal annealing,helium atoms will escape from vacancies,to form cavities.In semiconductor technology,He implantation-induced cavities have lots of important applications.Therefore,the study of He-implanted SiC is critical.He-implantation-induced cavities have been extensively investigated.He-implantation-induced dislocation loops also have been investigated.Chen et al.observed interstitial-type dislocation loops associated with He bubbles due to the release of bubble interior pressure via emitting interstitials[1].These interstitials agglomerate into dislocation loops.It is consistent with previous results observed in the case of He-implanted 6H-SiC[2].What’s more,Barbot et al.regarded that the growth of the Frank loops lead to the formation of stacking faults,which do not result from the agglomeration of interstitials[3].
文摘In order to accumulate the experimental data for building accelerator driven sub-critical systems(ADS),a high temperature and high pressure water circuit setup has been built.It is mainly used to study heat transfer deterioration of high temperature and high pressure water vapor in the circuit,flow instability mechanism and heat exchange efficiency of fuel rod in primary loop.Lots of similar experimental setups have been built by scientific research institution around the world[1-3].Unlike the existing experimental setup,flow rate of high temperature and high pressure water vapor was considered as a significant parameter to study above-mentioned research proposal.
文摘Because of excellent electronic and optical properties,GaN has been used in the laser diodes,microwave,ultrahigh power switches and other fields.Due to an attractive process for selective region doping of semiconductor devices,ion implantation has widely been applied to GaN fabrication processing.However,ion implantation introduces extensive damage that can degrade the performance,properties as well as lifetimes of the devices.Thus,it is very important to understand the ion-beam damage processes in the fabrication of GaN-based devices.The effects of ion implantation into GaN have been extensively investigated.
文摘Due to its favorable thermal-physical and chemical properties,lead-bismuth eutectic(LBE)is one of primary candidate materials for coolant in advanced nuclear reactors.However,severe corrosion of structural materials occurs in the presence of LBE in advanced nuclear reactors,especially at high temperature[1;2].Therefore,the selection of the structural material exposed to LBE is an extremely complex problem and compatibility tests are required.Because of their good mechanical properties under irradiation up to 500℃,ferritic/martensitic steels are considered to be one of the promising structural materials for advanced nuclear reactors,and so the compatibility tests of SIMP and T91 steel specimens were conducted at 450℃with saturated oxygen.
文摘Spallation target is one of the key constituent parts of the Accelerator Driven Sub-critical System(ADS),but the existing spallation targets are difficult to satisfy the power requirements of the commercial ADS in the future.In order to solve this problem,the scientists of the Institute of Modern Physics(IMP)originally proposed a new concept—the granular flow spallation target[1]which is quite different from the current spallation targets in the world.This novel spallation target with complete intellectual property rights incorporates the advantages of existing solid spallation targets and liquid metal spallation targets.Solid particles are delivered to the outside of the target area for heat transfer.
基金National Natural Science Foundation of China(12005269,U1832206)Key Program of the Chinese Academy of Sciences(Research on the Development of Nuclear Power Materials and Service Security Technology,ZDRW-CN-2017-1)。
