Long-term Thermal-aging stability of ODS ferritic steels with different Cr content at 753 K

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:q258007
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
  Oxide-dispersion strengthened(ODS)ferritic steels are promising candidates for structural applications in the future nuclear reactors.The higher chromium contents of ODS ferritic steels()the better the corrosion resistance will be,which can meet the harsh corrosion environment of the advanced reactors.But the increasing of the Cr content may also lead to the brittle of the ODS steels when service at high temperatures.
其他文献
During the R&D of ITER,tungsten has been recognized as one of the most hopeful materials for PFMs.However,its intrinsic brittle,low recrystallization temperature and radiation embrittlement are urgent
Metallic clad plates have a widespread application in nuclear power plant for safety injection tank.A novel bi-layers steel clad plates comprising of austenite stainless steel and low carbon steel has
The oxidation behavior of ferritic-martensitic(F-M)alloys in the water coolant of ITER was studied in order to assessment of the activated corrosion products under ITER working conditions.A series of
Divertor plays a vital role in a fusion reactor,not only the fusion reaction ash,unburnt fuel and eroded particles,but also about 15%of the total thermal power is removed through the divertor.This wor
As one of the most promising tritium permeation barriers,α-Al2O3 has attracted increasing attention in the field of nuclear fusion reactors,because of its high chemical stability and outstanding abili
The change of microstructure and mechanical properties of China Low Activation Martensitic(CLAM)steel thermal aging at 823k up to 3000h were investigated in this study.The results showed that CLAM ste
China Low Activation Martensitic(CLAM)steel is considered as the primary structural materials for the China designed International Thermonuclear Experimental Reactor(ITER)test blanket module because o
314 stainless steel and Q235 carbon steel were successfully bonded by vacuum multiple hot rolling at 1100℃.SEM and OM microscopic shows a gradient grain distribution near the interface between stainle
Continuous silicon carbide fiber reinforced silicon carbide matrix composites(SiCf/SiC)have been considered as promising candidates for nuclear materials because of their potential application for hig
Li4SiO4 is the tritium breeder material for helium cooled solid breeder blanket concept.The thermal properties of ceramic pebble beds provide important support for the design of solid breeder test bla