H/He co-irradiation induced structural change of Li4SiO4 ceramic breeder

来源 :第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) | 被引量 : 0次 | 上传用户:gunnie0095
下载到本地 , 更方便阅读
声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架
论文部分内容阅读
  To study the H/He co-irradiation induced structural change of lithium silicate as tritium breeder,Li4SiO4 film was prepared by sol-gel method,and KeV H/He co-irradiation experiments of Li4SiO4 with different ion influences were carried out under room temperature.The structural change of irradiated samples was characterized by TEM,FTIR,RAMAN and GIXRD techniques.The results suggest the water content,acid content and the adding sequence of the metal precursors have influence on the crystalline phase of the dense Li4SiO4 films.Concerning H/He co-implanted samples,it was found that after implantation,H and He ions stayed at interstitial sites of the host lattice,thus the significant lattice swelling occurs,the lattice parameter increases with the ion influence.
其他文献
Liquid lithuim,due to its large thermal shock resistance,high heat loads and radio-resistance to nutron irradiation,is perceived as a promising firstwall material in future fusion reactors[1].However,
Enhancement of hydrogen isotope retention in tungsten due to neutron irradiation is one of the most important issues for a future fusion device.In this study,properties of deuterium retention in recry
In a fusion reactor,the high heat flux of the plasma will lead to the first wall material damage.Impurities generated in damage process can have some impact on the normal of operation of the device.In
Liquid lithium was regarded as the candidate materials of the coolant.The liquid lithium of the strong corrosive may be corrosion the structural materials.In this study in order to provide some refere
In fusion reactor,the divertor is used to filter the helium ash produced in the reaction.Tungsten is a plausible candidate for divertor material in ITER,because it has a high melting,low sputtering yi
Molybdenum(Mo)is considered as the primary candidate of substrate materials for liquid lithium(Li)plasma-facing components(PFCs)in fusion devices,due to itssignificant advantages of corrosion resistan
High spatial and temporal resolution Thomson scattering diagnostic system can provide accurate profiles of plasma temperature and density,which play an important role in the study of linear plasma gen
As one of the promising plasma-facing materials in fusion reactor,tungsten will inevitably be exposed to high-fluxes of plasma species(deuterium and tritium).Deuterium behavior in polycrystalline tung
Accurate tritium transport properties of prospective tritium permeation barriers(TPBs)are essential to design practical tritium systems for fusion reactors.By passing a temperature and rate controlled
The effects of helium atoms on the nucleation and growth of dislocation loops and cavities in Fe-11Cr model alloy under electron irradiation have been investigated by high-voltage transmission electro