Effect of yttrium and titanium addition on inclusion and mechanical properties of 9Cr RAFM steel fab

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:liyongdede
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
  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%)or Y(mass fraction 0.25%)and Ti(mass fraction 0.1%)directly into 9Cr steel through vacuum induction melting.Optical microscopy(OM)is used to count the size and number of the second phase particles,and scanning electron microscopy(SEM)is used to examine the types of the second phase particles,and transmission electron microscopy(TEM)is used to measure the composition of smaller second phase particles.Size of most of inclusions in casting is micron level.
其他文献
Excellent irradiation stability has been reported for SiC at wide temperature ranges and damage levels under neutron irradiation.The Fukushima accident once again stimulated the research a fuel materi
SiC fiber reinforced SiC matrix(SiC/SiC)composites are reliable high temperature structural materials due to their enhanced fracture resistance compared to those of monolithic SiC.Thus,there were many
According to the fusion blanket concepts with liquid tritium breeding materials,the development of a functional coating as a tritium permeation barrier with corrosion resistance is required.In our pre
The ternary layered MAX-phase materials combining the merits of both metals and ceramics,which could have high radiation damage tolerance and novel damage self-healing abilities due to their special s
Tungsten(W),which possesses higher energy threshold for sputtering,low ability to hydride formation and low hydrogen solubility level,has been selected as the most likely candidate of plasma facing ma
Ion cyclotron wall condoning(ICWC)is a candidate wall conditioning methods under strong magnetic fields in ITER and DEMO [1-2].Advantages of ICWC are removals of hydrogen isotopes on surfaces of plasm
It is important to evaluate the influence of re-deposited tungsten formed on plasma facing wall on tritium retention in the vessel of a fusion reactor from a viewpoint of safety.In this work,deposited
Tungsten(W)is the most promising candidate for plasma facing material(PFM)in fusion reactors.However,the high ductile-brittle transition temperature(DBTT)and low ductility at low temperatures limit th
Nowadays,advanced nuclear power plants(NPPs)are designed to produce more electricity with less fuel at high temperature.This requires the structural materials to possess excellent mechanical propertie
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