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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

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The effect of Laves phase on heavy-ion radiation response of Nb-containing FeCrAl alloy for accident-tolerant fuel cladding

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Fundamental Research 2022年第3期2卷 437-446页

作者： Hang Xu Shuyao Si Yipeng Li Xiangbing Liu Wenqing Li Changzhong Jiang Shijun Zhao Hui Wang Xiangheng Xiao Department of Physics and Hubei Nuclear Solid Physics Key Laboratory Wuhan UniversityWuhan 430072China Institute of Science and Technology of The 404 Company Limited China National Nuclear CorporationJiayuguan 735100China College of Energy Xiamen UniversityXiamen 361102China Suzhou Nuclear Power Research Institute Suzhou 215004China Department of Mechanical Engineering City University of Hong KongHong Kong 999077China Science and Technology Reactor fuel and Material Laboratory Nuclear Power Institute ChinaChengdu 610041China

As a promising candidate material for the accident tolerant fuel cladding in light water reactors,the Nb-containing FeCrAl alloy has shown outstanding out-of-pile service performance due to the Laves phase *** this work,the radiation response in FeCrAl alloys with gradient Nb content under heavy ion radiation has been *** focus is on the effect of the Laves phase on irradiation-induced defects and *** found that the phase boundary between the matrix and Laves phase can play a critical role in capturing radiation defects,as verified by in-situ heavy-ion radiation experiments and molecular dynamic ***,the evolution of Laves phase under radiation is ***-induced amorphization and segregations observed at high radiation doses will deepen the fundamental understanding of the stability of Laves phases in the radiation environment.

关键词： accident-tolerant fuel cladding FeCrAl Laves phase In-situ radiation Segregation

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