Atomic simulations of effect of Ne on H retention in bcc Fe

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:fiona_01
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
  Fe-based alloys of bcc phase are considered as the promising structural materials in fusion reactor.Large amounts of H impurities are produced concurrently along with irradiation damage in the structural materials under neutron irradiations.Ions irradiations have been carried out to study neutron irradiation damage effect in fusion materials,e.g.,Ne and H/He ions.As a continuation of our previous efforts on H/He behavior with vacancy in bcc Fe [1-3],to understand effects of Ne on H retention in Fe based alloys,in this work,we investigated the preference sites of Ne and interaction between Ne and H within bcc Fe host lattices using first-principles calculations.
其他文献
Vanadium alloy is considered as the first candidate material for self-cooled lithium blanket for its excellent neutron resistance、mechanical property and compatibility with lithium.In the real applica
W-ZrC composites reinforced with Sc2O3 particles were produced through powder metallurgy(PM)and subsequent spark plasma sintering(SPS)at 1700 °C and 13.7 KN.The microstructure and properties of the co
Reduced activation ferritic steel alloys such as F82H are the candidate materials for the first wall of DEMO reactors.For self-cooled breeding blankets,the first wall will be subjected to bi-direction
The transient thermal shock performances and relevant damage mechanism of pure W and lutecium doped W alloys were investigated via a repetitive laser beam heat load test to simulate the transient heat
W-3wt%Lu2O3 composites were prepared by mechanical milling and spark plasma sintering.The W-3wt%Lu2O3 composites were maintained in a vacuum at room temperature,and irradiated with a He+(He+ion beam f
Austenitic stainless steels 316L have been widely utilized for industrial application,especially,as the candidate structural materials for fusion reactor.It is well known that helium atoms can be trap
Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder(HCCB)test blanket module(TBM)which is the primary option of the Chinese TBM program.The character of the mi
Tungsten-based materials form a prime candidate of plasma facing components in fusion power reactors,and are subject to substantial amount of radiation damage from the bombardments of fast neutrons,as
The source term caused by activated corrosion products(ACPs)is an important radiation hazard in water-cooled fusion reactor,which directly determines the occupational radiation exposure during operati
随着显示产业的发展,对于器件柔性化的需求开始受到包括学术界和产业界的广泛重视。柔性显示器件通常采用塑料等可挠曲基板材料,因此对于器件的制作温度有明确的限制,不能采用传统的高温制程。溶液加工技术,包括常用的旋转旋涂,刮涂,以及近年来受到关注的印刷技术,就成为柔性显示器件制作的首选方案。
会议