Bi-Directional hydrogen isotopes permeation through a reduced activation ferritic steel alloy F82H

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:chamcham
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
  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-directional hydrogen isotopes permeation by two different mechanisms: in one direction by edge plasma-driven permeation(PDP)of deuterium as well as tritium into blankets,and in the other direction by bred tritium gas-driven permeation(GDP)into the edge plasma.It is important to note that deuterium PDP will lower the recovery efficiency of tritium from the breeder,and GDP,acting as fueling,will increase the particle recycling in the first wall region.
其他文献
The first-principle method based on the density function theory was used to investigate the formation energy,the migration barrier energy of first nearest neighbor(1NN)and second nearest neighbor(2NN)
Material radioactivity caused by neutron activation is very important to radiation protection in both fusion reactor and fission reactor.In this paper,the Chebyshev rational approximation method(CRAM)
Ferritic/martensitic(F/M)steel is regarded as one of the most promising candidate structural materials for GEN IV,fusion reactor and accelerator driven system(ADS),which have been widely studied in th
A novel model with built-in tungsten filament on the basis of join W/Cu functionally graded layer was proposal and investigated.Using the ABAQUS software on the basis of finite element method,the dist
Helium(He)behavior in metals has been a subject of both scientific interest and technological significance for decades.Because of its extremely low solubility,high mobility and self-trapping character
In the design of future fusion reactors,tungsten(W)is currently a leading material choice for plasma facing materials(PFMs)for divertor.For plasma facing components(PFCs)with relatively small particle
In the High temperature gas cooled reactor(HTGR),the radio nuclides produced by fission and activating reactions would be carried into circulation by helium.Tritium is one of the most important radioa
Tritium breeder materials are significant for blanket design of fusion reactor.However,during blanket operation,the ceramic breeder materials will be subjected to neutron irradiation which could be de
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