The radiation damages and helium behaviors of CSNS target

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:weiqiangting
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 radiation damages had been performed for Chinese Spallation Neutron Source(CSNS)target components that relies on Monte Carlo simulation code MCNPX2.5.0.During the calculation,Bertini intra-nuclear cascade model,three level-density formulation GCCI,and the multistage pre-equilibrium model MPM on which are provided within MNCPX were employed.We also compared the effects on the radiation damage due to two different physics models and the proton beam profiles.Based on these results and the allowable DPA values we had estimated the lifetime of the tungsten target and its vessel.
其他文献
15-15Ti stainless steel has better anti irradiation swelling and corrosion resistance compared with 316L,as the same time,it has better mechanical properties and processing properties corresponding to
In the past three decades,9~12%Cr ferritic/martensitic(such as T/P92,X20)and high alloyed austenitic steels(such as TP347,Super304H and HR3C)were widely used as heat exchangers in the boiler tube syst
Material property degradation of Tungsten(W)by neutron irradiation is one of key issues for plasma facing components in fusion power reactor.Displacement damage will cause irradiation hardening and em
Fuel cladding chemical interaction(FCCI)has long been acknowledged as a problem in the fuel/cladding system,and is likely to be exacerbated at high fuel burn-ups and during the use of metallic fuels b
The material is one of the most important issues in nuclear fission and fusion energy technology,and we have made some attempts at catalyst for WDS/TEP,tritium breeder for TBM,palladium alloy membrane
The conceptual design activity of the LHD-type helical reactor FFHR-d1 is being intensively conducted under the Fusion Engineering Research Project FERP at NIFS.The present activity incorporates the m
This report covers the worlds nuclear fuel cycle and MOX fuel policy,strategies and practices,explore the history and current situation of the nuclear fuel cycle,and analyze the challenges and opportu
This paper outlines the DEMO design and related R&D activities in SWIP.The basic definition and development strategy of the DEMO plant based on the Chinese fusion energy development program are presen
Helium(He)is a typical impurity in metals,which is produced from(n,α)transmutation reactions in both fission and fusion.It is well known that He atoms are energetically favorable clustering with each
Reduced activation ferritic/martensitic steels are considered as one of the most suitable materials in the application of international thermonuclear experimental reactor.One of the important requirem