The feasibility and benefits of applying grain boundary engineering to the fuel cladding materials o

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:zhanghui1860
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
  The feasibility and benefits of applying grain boundary engineering(GBE)to the fuel cladding material 15-15Ti austenitic stainless steels of liquid-metal-cooled-fast-reactor for reducing the void swelling,corrosion in liquid metal and creep were discussed.The GBE can be used to greatly enhance the proportion of low ΣCSL grain boundaries which are mainly of annealing twins and its variants.The cladding materials were normally subjected to 20%cold working after solid solution annealing before using,which by virtue of providing a dislocation strewn matrix microstructure,contributes to the annihilation of irradiation-induced point defects.If the proportion of low ΣCSL grain boundaries were greatly enhanced via GBE prior to the cold working,the transfer of slip across the special-structured grain boundaries or pile-up against them during deformation may alter the distribution of the dislocations of the microstructure,which may accommodate more defects that generated during being irradiated.In the current work,the effects of thermal-mechanical processing on the grain boundary character distribution of 15-15Ti austenitic stainless steel were investigated.The microstructures of the cold-worked GBE samples were analyzed and compared with that of the conventional samples.
其他文献
The irradiation defects will be introduced to plasma facing materials,especially tungsten(W)by both energetic ions and 14 MeV neutrons produced by fusion reaction,where hydrogen isotopes would be stab
Process of adding yttrium into the melt is not a common method for ODS RAFM steel production.In this paper,the oxide dispersion strengthened steel(9Cr-ODS)was prepared by adding Y(mass fraction 0.25%)
Oxide dispersion strengthened(ODS)steels have been developed for several decades as the most promising structural material for next-generation fission reactors and future fusion energy systems due to
Oxide dispersion strengthened(ODS)ferritic steels contain a high number density of nano-sized oxides and fine grains that provide remarkably high tensile strength,good creep resistance or dimensional
In this work,a theoretical framework is proposed for the depth profile of hardness with ion irradiation effect,which can effectively depict the defect gradient effect(DGE),indentation size effect(ISE)
The ODS steel with oxide phase of good thermal stability and chemical stability can be used in fusion engineering to sustain high temperature and strong radiation.In fusion engineering structure,the w
As a study of the mechanism of hydrogen absorption into promising hydrogen storage materials,two ZrNiAl type uranium intermetallic compounds,UNiAl and UPtAl,were investigated with the ab initio calcul
Due to the good radiation resistance and low activation performance,the reduced activation ferritic/martensitic(RAFM)steel has been selected as the primary candidate structural material for the fusion
Irradiation-induced hardening and premature fracture are major concerns for the intermediate-temperature application of high Cr ferritic/martensitic steels as structural materials in nuclear reactors
The combination of irradiation tolerance,high strength,and thermal stability is a key requirement for structural materials used in nuclear reactor cores.It is challenging to develop bulk materials pos