Helium bubbles nucleation and growth in metals or metal tritide is a long-standing problem attracting considerable attention in nuclear industry but the mechanism remains indistinct and predicting the growth rate of helium bubble is inexistence still up to new. Here, the rate of helium bubbles nucleation and growth in metal tritide is developed based on a dynamical model, which describes the diameter of helium bubbles increasing linearly as t**(1/3) in titanium tritide at room temperature, agreeing quite well with the experimental phenomenon. The way of reducing storage temperature from 300 to 225 K or increasing the helium atoms diffusion barrier from 0.81 to 1.1 eV can effectively restrain bubbles growth and prolong lifetime of titanium tritide more than 4 times, which provides a useful reference to relevant experiment exploration and applications. This model also can be used to predict lifetime of new tritium-storage materials and plasma facing materials in nuclear industry.
Comparative study on radiation resistance of WTaCrV high-entropy alloy and tungsten in helium-containing conditions
NOMATEN Centre of Excellence, National Centre for Nuclear Research(国家核研究中心 NOMATEN 卓越中心);National Center for nuclear Research, Materials Research Laboratory(国家核研究中心材料研究实验室);Department of Applied Physics, Aalto University(阿尔托大学应用物理系)
Graph neural network prediction of temperature-dependent hydrogen diffusion and thermal conductivity tensors of tungsten containing helium bubbles and grain boundaries
Graduate School of Science and Engineering, Yamagata University(山形大学理工学研究科);National Institute for Fusion Science(国立研究開発法人核融合科学研究所)
Cross-sectional helium irradiation reveals interface-controlled bubble evolution in Cr/CrAlSiN multilayer coatings on zirconium alloys
Ningbo Institute of Materials Technology and Engineering, Chinese Academy of Sciences(中国科学院宁波材料技术与工程研究所);Ningbo University of Technology(宁波工程学院);Harbin Engineering University(哈尔滨工程大学);Southwest University of Science and Technology(西南科技大学);Czech Technical University in Prague(布拉格捷克理工大学);Qianwan Institute of CNITECH(国创中心千湾研究院);Advanced Energy Science and Technology Guangdong Laboratory(先进能源科学与技术广东省实验室);University of Chinese Academy of Sciences(中国科学院大学);University of Southampton(南安普顿大学)
Irradiation of TiBe12 and CrBe12 with He+ ions and ex-situ transmission electron microscopy to investigate ion damage as a proxy for neutron irradiation damage in nuclear fusion