Vanadium carbide coating for mitigating the fuel cladding chemical interactions

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:trung
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
  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 bearing transuranic elements,as may be the case for sodium-cooled fast reactors(SFR).In this work,a low temperature coating process using an organometallic precursor,vanadocene Cp2V(Cp=C5H5)was developed.An innovative coating setup has been built to deposit a uniform nanostructured vanadium carbide layer.Diffusion couples of HT9/VC/Ce annealed up to a temperature of 600°C,and compared to the diffusion behavior of uncoated HT9/Ce.These preliminary results strongly advocate that VC coatings may be feasible as diffusion barriers against Ce and possibly other lanthanide fission products.
其他文献
A tightly coupled multi-physics model for MSR system involving the reactor core and the rest of the primary loop has been developed and employed in an in-house developed computer code TANG-MSR.In this
Combination of ion-irradiation method and nanoindentation techniques has been widely used for investigating irradiation hardening behavior of fusion and fission reactor materials.Extended Nix-Gao mode
China low activation martensitic(CLAM)steel,one of the three main reduced activation ferritic/martensitic steels(RAFMs)under development in the world,has been selected as the primary structural materi
The compatibility of the reduced activation ferritic martensitic(RAFM)steel,JLF-1,with liquid lead(Pb)lithium(Li)eutectic alloy(LLE)is one of the critical issues for the development of LLE type blanke
Ferritic/martensitic steels are promising structural material for nuclear and non-nuclear applications.Because structural materials of these components are suffered by cyclic loading,fatigue life eval
Residual stresses introduced by fabrication process especially welding process can cause distortion and reduced the ultimate strength of welded structure.Non homogeneous heat distribution during weldi
Distribution of hardness,grain boundary chemistry,types of grain boundary and fraction,local deformation and stress corrosion cracking of Ni-base Alloys 600 and 690 heat-affected zones in simulated pr
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