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Journal of Materials Science & Technology 2022年第12期107卷 14-25页

作者： Yipeng Li Guang Ran Xinyi Liu Qing Han Xiuyin Huang Yifan Ding College of Energy Xiamen UniversityXiamen 361102China Fujian Research Center for Nuclear Engineering Xiamen 361102China

Through in-situ TEM observation during 30 keV H_(2)^(+)-He^(+) dual-beam irradiation at 723 K,the reaction and transformation of dislocation loops in pure Mo were investigated,especially for*** could directly cause the formation of 1/2loops andloops,but 1/2loops were ***-situ observation confirmed the formation mechanism ofloops,including direct irradiation induced mechanism,1/2loop direct conversion mechanism,and reaction mechanism of two 1/2***,the reaction of two 1/2loops to produceloop should not require the strict size similarity *** reaction between 1/2loops could also produce 1/2loop,which was essentially a process in which one loop absorbed another *** yield strength increment caused by irradiation-induced loops was analyzed,and its saturation value reached0.48 GPa at 0.06 *** with single He+irradiation,the number density and average diameter of loops increased significantly and more serious damage was caused under the synergistic effect of hydrogen and *** mechanism based on in-situ experimental observation was discussed in depth.

关键词： In-situ TEM observation Dislocation loop Hydrogen helium irradiation Molybdenum irradiation hardening

Theoretical models for irradiation hardening and embrittlement in nuclear structural materials:a review and perspective

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Acta Mechanica Sinica 2020年第2期36卷 397-411页

作者： Xiazi Xiao Dmitry Terentyev Haijian Chu Huiling Duan Department of Mechanics School of Civil EngineeringCentral South UniversityChangsha 410075China Structural Materials Group Institute of Nuclear Materials ScienceSCK-CEN2400 MolBelgium Shanghai Key Laboratory of Mechanics in Energy Engineering Shanghai Institute of Applied Mathematics and MechanicsSchool of Mechanics and Engineering ScienceShanghai UniversityShanghai 200444China State Key Laboratory for Turbulence and Complex System Department of Mechanics and Engineering Science College of EngineeringPeking UniversityBeijing 100871China CAPT HEDPS and IFSA CollaborativeInnovation Center of MoEBIC-ESATPeking UniversityBeijing 100871China

The study of irradiation hardening and embrittlement is critically important for the development of next-generation structural materials tolerant to neutron irradiation,and could dramatically affect the approach to the design of components for advanced nuclear *** addition,a growing interest is observed in the field of research and development of irradiation-resistant *** review aims to provide an overview of the theoretical development related to irradiation hardening and embrittlement at moderate irradiation conditions achieved in recent years,which can help extend our fundamental knowledge on nuclear structural *** a general introduction to the irradiation effects on metallic materials,recent research progress covering theoretical modelling is summarized for different types of structural *** fundamental mechanisms are elucidated within a wide range of temporal and spatial *** review closes with the current understanding of irradiation hardening and embrittlement,and puts some perspectives deserving further study.

关键词： irradiation hardening irradiation embrittlement Theoretical models Fundamental mechanisms

Effect of tellurium(Te^(4+))irradiation on microstructure and associated irradiation-induced hardening

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Chinese Physics B 2021年第5期30卷 87-92页

作者： Hefei Huang Jizhao Liu Guanhong Lei Ondrej Muránsky Tao Wei Mihail Ionescu Shanghai Institute of Applied Physics Chinese Academy of SciencesShanghai 201800China School of Nuclear Science and Technology University of Chinese Academy of SciencesBeijing 100049China Australian Nuclear Science and Technology Organisation(ANSTO) Lucas HeightsSydneyNSW2234Australia University of New South Wales(UNSW) KensingtonSydneyNSW2052Australia

The GH3535 alloy samples were irradiated using 15-MeV Te^(4+) ions at 650℃to a dose of 0.5,3.0,10,and 20 dpa,*** Te atoms distribution and microstructure evolution were examined by electron probe microanalysis(EPMA)and transmission electron microscopy(TEM).The nano-indenter was then used to measure the nano-hardness changes of samples before and after *** results showed the formation of dislocation loops in the irradiated *** mean diameters increase with the increase of irradiation dose and tends to be saturated when irradiation dose exceeds 10 *** ratio of yield strength increments calculated by dispersed barrier hardening(DBH)model is basically consistent with that of nano-hardness increments measured by *** addition,the relationship between the nano-hardness increments and dpa for the GH3535 alloy irradiated by Te ions has been revealed in the study.

关键词： GH3535 alloy Te ions irradiation microstructural evolution irradiation hardening

Unusual He-ion irradiation strengthening and inverse layer thickness-dependent strain rate sensitivity in transformable high-entropy alloy/metal nanolaminates:A comparison of Fe_(50)Mn_(30)Co_(10)Cr_(10)/Cu vs Fe_(50)Mn_(30)Co_(10)Ni_(10)/Cu

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Journal of Materials Science & Technology 2022年第21期116卷 199-213页

作者： Y.F.Zhao H.H.Chen D.D.Zhang J.Y.Zhang Y.Q.Wang K.Wu G.Liu J.Sun State Key Laboratory for Mechanical Behavior of Materials Xi’an Jiaotong UniversityXi’an 710049China

In this work,we prepare transformable HEA/Cu nanolaminates(NLs)with equal individual layer thick-ness(h)by the magnetron sputtering technique,i.e.,Fe_(50)Mn_(30)Co_(10)Cr_(10)/Cu and Fe_(50)Mn_(30)Co_(10)Ni_(10)/Cu,and comparatively study He-ion irradiation effects on their microstructure and mechanical *** ap-pears that the as-deposited HEA/Cu NLs manifest two size h-dependent hardness regimes(i.e.,increased hardness at small h and hardness plateau at large h),while the He-implanted ones exhibit monotonically increased *** to the fashion that smaller h renders less irradiation hardening in bimetal NLs,the Fe_(50)Mn_(30)Co_(10)Cr_(10)/Cu NLs manifest the trend that smaller h leads to greater irradiation *** contrast,the Fe_(50)Mn_(30)Co_(10)Ni_(10)/Cu NLs exhibit the maximum irradiation hardening at a critical h=50 *** this critical size,smaller h results in lower radiation hardening(similar to bimetal NLs),while above this size,smaller h results in greater radiation hardening(similar to Fe_(50)Mn_(30)Co_(10)Cr_(10)/Cu NLs).Moreover,these transformable HEA/Cu NLs display inverse h-dependent strain rate sensitivity(SRS m)before and after He-ion ***,compared with as-deposited samples,the irradi-ated Fe_(50)Mn_(30)Co_(10)Cr_(10)/Cu NLs display reduced SRS,while the irradiated Fe_(50)Mn_(30)Co_(10)Ni_(10)/Cu NLs dis-play enhanced *** unusual size-dependent irradiation strengthening and inverse h effect on SRS in irradiated samples were rationalized by considering the blocking effects of He bubbles on dislocation nucleation and motion,i.e.,dislocations shearing or bypassing He bubbles.

关键词： High entropy alloy/metal nanolaminates Interfaces irradiation hardening Strain rate sensitivity Size effects

irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding

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Journal of Materials Science & Technology 2021年第25期84卷 230-238页

作者： Zijian Zhang En-Hou Han Chao Xiang Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang110016China School of Materials Science and Engineering University of Science and Technology of ChinaShenyang110016China School of Materials Science and Engineering Northeastern UniversityShenyang110819China

High-entropy alloys(HEAs)are potential alternative materials for accident-tolerant fuel cladding due to their excellent irradiation resistance and high-temperature corrosion *** this work,two novel body-centered cubic(bcc)structured Mo_(0.5)Nb Ti VCr_(0.25)and Mo_(0.5)Nb Ti V_(0.5)Zr_(0.25)HEAs were ***-ion irradiation was performed on the two HEAs to simulate neutron irradiation,and the crystal structure,hardness,and microstructure evolution were *** crystal structure of the Mo_(0.5)NbTiVCr_(0.25)HEA remained stable at low fluences,while amorphization may occur at high fluences in the two *** irradiation hardening value of the Mo_(0.5)NbTiVCr_(0.25)was 0.77 GPa at fluences of 1×10^(17)ions/cm^(2)and 1.49 GPa at fluences of 5×10^(17)ions/cm^(2),while the hardening value of the Mo_(0.5)NbTiV_(0.5)Zr_(0.25)was 1.36 GPa at ion fluences of 5×10^(17)ions/cm^(2).In comparison with most of the conventional alloys,the two HEAs showed slight irradiation *** helium bubbles and dislocation loops with small size were observed in the two HEAs after *** is the first time to report the formation of a dislocation loop in bcc-structure HEAs after ***,voids and precipitates were not observed in the two HEAs which could be ascribed to the high lattice distortion and compositional complexity of *** research revealed that the two HEAs show outstanding irradiation resistance,which may be promising accident-tolerant fuel cladding materials.

关键词： High-entropy alloy Accident-tolerant fuel cladding Helium-ion irradiation Microstructure irradiation hardening

Effects of MeV Fe Ions irradiation on the Microstructure and Property of Nuclear Grade 304 Stainless Steel:Characterized by Positron Annihilation Spectroscopy,Transmission Electron Microscope and Nanoindentation

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Acta Metallurgica Sinica(English Letters) 2021年第12期34卷 1695-1703页

作者： Honglin Yan Zhiming Zhang Jianqiu Wang Bright O.Okonkwo En-Hou Han Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang 110016China School of Materials Science and Engineering University of Science and Technology of ChinaShenyang 110016China

Nuclear grade 304 stainless steel was irradiated by 3.5 MeV Fe ions,with fluxes of 3.05E+15 ions/cm^(2)and 1.55E+16 ions/cm^(2).irradiation effects were studied by positron annihilation spectroscopy(PAS),transmission electron microscope(TEM)and nanoindentation *** results showed that different types of defects were produced after irradiation and that there was significant variance in defects formed when the samples were subjected to different irradiation *** characterization showed that the irradiation-induced dislocation loops enlarged in average size,but decreased in number density at higher irradiation *** test showed obvious irradiation hardening phenomenon,which was in good agreement with the PAS and TEM *** hardening effect increased with an increase in irradiation dose and saturation occurred with an increase in irradiation dose from 3.2 to 16 *** statistical analysis showed that barrier strength of the Frank loop depends on the loop size and density produced by the ion irradiation.

关键词： Stainless steel irradiation hardening Positron annihilation Nanoindentation

SIMULATION OF THE IN-PILE BEHAVIORS EVOLUTION IN NUCLEAR FUEL RODS WITH THE irradiation DAMAGE EFFECTS

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Acta Mechanica Solida Sinica 2014年第6期27卷 551-567页

作者： Xin Gong Yijie Jiang Shurong Ding Yongzhong Huo Canglong Wang Lei Yang Department of Mechanics and Engineering Science Fudan University Institute of Modern Physics Chinese Academy of Sciences

Based on the commercial computational software, a three-dimensional finite ele- ment model to simulate the thermo-mechanical behaviors in a nuclear fuel rod is established; By taking into consideration irradiation-swelling of the pellet and the irradiation damage effects in the cladding together with the coupling effects between the temperature field and the mechanical field, the user subroutines to define the special material performance and boundary conditions have been developed independently and validated. Three-dimensional numerical simulation of the thermo-mechanical coupling behaviors in a nuclear fuel rod is carried out, and the evolution rules of the important thermal and mechanical variables are obtained and analyzed. The research re- sults indicate that：（i） the fuel pellets will be in contact with the cladding at high burnup, which will induce a strong mechanical interaction between them; （2） the irradiation creep effect plays an important role in the mechanical behavior evolution in the nuclear fuel rod.

关键词： irradiation hardening irradiation creep large-deformation thermo-mechanicalcoupling FEM