Zirconium carbide(ZrC)nanoparticles with an average size of 5.6 nm were synthesized through laser fragmentation(LF)from as-received 20-60 nm ZrC particles,and LF-ZrC nanoparticle dispersion-strengthened tungsten(LF-WZ...Zirconium carbide(ZrC)nanoparticles with an average size of 5.6 nm were synthesized through laser fragmentation(LF)from as-received 20-60 nm ZrC particles,and LF-ZrC nanoparticle dispersion-strengthened tungsten(LF-WZC)samples were fabricated by spark plasma sintering method.The average grain size of LF-WZC is 1.91μm and most ZrC particles in LF-WZC are smaller than 10 nm.LF-WZC exhibits finer grain size,higher yield strength and hardness but lower ductility as compared with W-ZrC samples using as-received ZrC(WZC).The results showed that finer ZrC nanoparticles dispersed in tungsten can enhance the strength by hindering the motion of dislocations,but they may also introduce stress concentra-tion and thus reduce the ductility.The thermal shock resistance of the WZC and LF-WZC samples was investigated using an electron beam device.The LF-WZC sample also exhibits a higher cracking threshold(0.33-0.44 GW·m^(−2))than WZC(0.22-0.33 GW·m^(−2))at room temperature.The enhanced thermal shock resistance of LF-WZC could be attributed to its high yield strength.展开更多
As promising candidates for plasma-facing materials,tungsten-based materials suffer the irradiation of high-energy neutrons in addition to the hydrogen isotopes and helium irradiation and the high-thermal flux.Radiati...As promising candidates for plasma-facing materials,tungsten-based materials suffer the irradiation of high-energy neutrons in addition to the hydrogen isotopes and helium irradiation and the high-thermal flux.Radiation-produced defects,e.g.self-interstitial atoms(SIAs)and vacancies(Vs),can induce the hardening and embrittlement of tungsten,meanwhile enhancing the retention of hydrogen isotopes and helium in tungsten.Reducing the grain size of materials to introduce a high density of defect sinks,e.g.,grain boundaries(GBs)prevalent in nano-/ultrafine-crystalline materials,was demonstrated to be an effective approach for mitigating irradiation damage in tungsten.In this paper,we reviewed the theoretical advances in exploring radiation-resistance of nano-structured tungsten at across scales.It was concentrated on the results of molecular dynamics,molecular statics,and the object kinetic Monte Carlo simulations on the fundamental interaction of the radiation-created Vs and SIAs with the GB.These mechanisms include GB-promoted V/SIA migration and SIA-V recombination,interstitial-emission induced annihilation,coupling of the V migration close to the GB with the SIA motion within the GB,and interstitial reflection by the locally dense GB structure.We proposed the remaining scientific issues on the defect-GB interactions at across scales and their relation to experimental observations.We prospected the possible trends for simulating the radiation damage accumulation and healing processes in nano-structured tungsten in terms of the development of the across-scale computational techniques and efficiency of the GB-enhanced tolerance of tungsten to irradiation under complex in-service conditions.展开更多
基金This work was financially supported by the National Key R&D Program of China(Grant Nos.2017YFE0302400,2017YFA0402800,and 2017YFE0300403)the National Natural Science Foundation of China(Grant Nos.51671184,11735015,51801203,and 11575231).
文摘Zirconium carbide(ZrC)nanoparticles with an average size of 5.6 nm were synthesized through laser fragmentation(LF)from as-received 20-60 nm ZrC particles,and LF-ZrC nanoparticle dispersion-strengthened tungsten(LF-WZC)samples were fabricated by spark plasma sintering method.The average grain size of LF-WZC is 1.91μm and most ZrC particles in LF-WZC are smaller than 10 nm.LF-WZC exhibits finer grain size,higher yield strength and hardness but lower ductility as compared with W-ZrC samples using as-received ZrC(WZC).The results showed that finer ZrC nanoparticles dispersed in tungsten can enhance the strength by hindering the motion of dislocations,but they may also introduce stress concentra-tion and thus reduce the ductility.The thermal shock resistance of the WZC and LF-WZC samples was investigated using an electron beam device.The LF-WZC sample also exhibits a higher cracking threshold(0.33-0.44 GW·m^(−2))than WZC(0.22-0.33 GW·m^(−2))at room temperature.The enhanced thermal shock resistance of LF-WZC could be attributed to its high yield strength.
基金This work was financially supported by the National Key Research and Development Program of China(Grant Nos.2017YFE0302400,2017YFA0402800,and 2018YFE0308102)the National Natural Science Foundation of China(Grant Nos.11735015,51871207,51671185,U1832206,51771181,U1967211 and 51971212)the Center for Computation Science,Hefei Institutes of Physical Sciences.
文摘As promising candidates for plasma-facing materials,tungsten-based materials suffer the irradiation of high-energy neutrons in addition to the hydrogen isotopes and helium irradiation and the high-thermal flux.Radiation-produced defects,e.g.self-interstitial atoms(SIAs)and vacancies(Vs),can induce the hardening and embrittlement of tungsten,meanwhile enhancing the retention of hydrogen isotopes and helium in tungsten.Reducing the grain size of materials to introduce a high density of defect sinks,e.g.,grain boundaries(GBs)prevalent in nano-/ultrafine-crystalline materials,was demonstrated to be an effective approach for mitigating irradiation damage in tungsten.In this paper,we reviewed the theoretical advances in exploring radiation-resistance of nano-structured tungsten at across scales.It was concentrated on the results of molecular dynamics,molecular statics,and the object kinetic Monte Carlo simulations on the fundamental interaction of the radiation-created Vs and SIAs with the GB.These mechanisms include GB-promoted V/SIA migration and SIA-V recombination,interstitial-emission induced annihilation,coupling of the V migration close to the GB with the SIA motion within the GB,and interstitial reflection by the locally dense GB structure.We proposed the remaining scientific issues on the defect-GB interactions at across scales and their relation to experimental observations.We prospected the possible trends for simulating the radiation damage accumulation and healing processes in nano-structured tungsten in terms of the development of the across-scale computational techniques and efficiency of the GB-enhanced tolerance of tungsten to irradiation under complex in-service conditions.