Thermal-stress analysis on the crack formation of tungsten during fusion relevant transient heat loa

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:liongliong591
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
  In the fusion devices,tungsten based plasma-facing materials will be exposed to transient heat loads during plasma disruptions,edge localized modes and vertical displacement events,which would cause damages like plastic deformation,cracks,even fatigue cracks.These damages were closely related to stress-strain event caused by thermal extension [1].
其他文献
Plasma disruption would induce large eddy current and generate huge electromagnetic force in the vacuum vessel and other in vessel components of the Tokamak fusion reactor.To evaluate the safety of To
真三维视频获取与显示已成为未来立体影像的终极发展目标,集成成像技术由于能够再现具有近视连续视差、彩色以及大规模真实立体场景,已逐渐成为当今研究的热点。如何用小的代价采集到高保真影像信息、如何获得立体元图像阵列和高清晰显示已成为集成成像发展的关键所在。
会议
α-Al2O3 and AlPO4 have been proved remarkable performance to hinder diffusion of tritium,the composite material,α-Al2O3/AlPO4,prepared by selective laser sintering develop the performances of tritium
Al2O3 and Cr2O3 are two representative materials of tritium permeation barriers and composite coating has become a trend to develop the tritium permeation barriers.The mechanism for diffusion of hydro
Liquid lead(Pb)-bismuth(Bi)eutectic(LBE)is a promising candidate as coolant in the accelerator driven nuclear system(ADS),but it will result in degradation of iron-based structure materials due to the
Activated corrosion products(ACPs)in the cooling loops are the dominant radioactive source in water-cooled reactors and have great influence on shielding design,personnel protection,and consequences o
The mechanical and physical properties of structural materials in fission/fussion system could be changed under the energetic particle irradiation.These effects are due to microstructural changes that
Oxide dispersion strengthened(ODS)ferritic steels are considered as the most promising candidate materials for future fission and fusion structural materials.The ODS-CLAM steel was fabricated by mecha
A series of fusion reactor(named FDS series)have been designed and assessed for the examination of the feasibility and the safety,environmental and economic potential of fusion with emphasizing the bl
The Reduces Activation Ferritic/Martensitic(RAFM)steel is considered as the primary candidate structural material for demonstration plant(DEMO)and the first fusion plant,and widely studied in the worl