Influence of vanadium content on the hardening of 9Cr-WVTiN reduced activation martensitic steel und

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：wangyang062011

【摘要】

：

【作者】

：

Zheng Yang Guo Liping Shuoxue Jin Fengfeng Luo Zhongcheng Zheng Zhenyu Shen Weiping Zhang

【机构】

：

Hubei Nuclear Solid Physics Key Laboratory,Key Laboratory of Artificial Micro-and Nano-structures of

【出处】

：

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)

【发表日期】

：

2016年3期

【关键词】

：

9Cr-WVTiN reduced activation martensitic/ferritic steel helium in alloys nanoind

下载到本地 , 更方便阅读

下载此文赞助VIP

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

　　9Cr-WVTiN reduced activation martensitic steels with two different vanadium concentrations were subjected to nanoindentation tests after being implanted with 300 keV helium ions at 250 °C.The specimen with higher vanadium content was found to be more resistant to the hardening effect of helium.Doppler broadening measurements of the positron annihilation lines indicated that the reduced hardening tendency in the high vanadium steel was related to VX precipitates.

其他文献

Heat flux characteristics of helium plasmas in linear plasma device

In a fusion reactor,the high heat flux of the plasma will lead to the first wall material damage.Impurities generated in damage process can have some impact on the normal of operation of the device.In

会议

Heat fluxhelium plasmasdischarge powerflow ratemagnetic field

The corrosion behavior of 316L stainless steel welds in liquid lithium with LIBS

Liquid lithium was regarded as the candidate materials of the coolant.The liquid lithium of the strong corrosive may be corrosion the structural materials.In this study in order to provide some refere

会议

Liquid lithium316L stainless steel weldsCorrosionLIBS

Research on characteristics of helium plasma and irradiation damage to tungsten surface in cascade a

In fusion reactor,the divertor is used to filter the helium ash produced in the reaction.Tungsten is a plausible candidate for divertor material in ITER,because it has a high melting,low sputtering yi

会议

Arc dischargeDivertorHeliumElectron temperatureElectron densityOptical radi

Corrosion behavior of high density helium plasma irradiated molybdenum in liquid lithium

Molybdenum(Mo)is considered as the primary candidate of substrate materials for liquid lithium(Li)plasma-facing components(PFCs)in fusion devices,due to itssignificant advantages of corrosion resistan

会议

MolybdenumLiquid LithiumPlasma-surface interactionsCorrosion

Optical design of Thomson scattering system for PSI-SCU

High spatial and temporal resolution Thomson scattering diagnostic system can provide accurate profiles of plasma temperature and density,which play an important role in the study of linear plasma gen

会议

optical designThomson scatteringelectron temperature

Deuterium behavior in tungsten with and without prior stress-relief annealing

As one of the promising plasma-facing materials in fusion reactor,tungsten will inevitably be exposed to high-fluxes of plasma species(deuterium and tritium).Deuterium behavior in polycrystalline tung

会议

deuteriumtungstenstress-relief annealing

Tritium permeation characterization of Al2O3/FeAl coating as tritium permeation barrier on type 321

Accurate tritium transport properties of prospective tritium permeation barriers(TPBs)are essential to design practical tritium systems for fusion reactors.By passing a temperature and rate controlled

会议

Al2O3/FeAltritium permeation barrier321 stainless steel

Effects of helium implantation and subsequent electron irradiation on the microstructure of Fe-11Cr

The effects of helium atoms on the nucleation and growth of dislocation loops and cavities in Fe-11Cr model alloy under electron irradiation have been investigated by high-voltage transmission electro

会议

helium implantationsubsequent electronFe-11Cr model alloy

H/He co-irradiation induced structural change of Li4SiO4 ceramic breeder

To study the H/He co-irradiation induced structural change of lithium silicate as tritium breeder,Li4SiO4 film was prepared by sol-gel method,and KeV H/He co-irradiation experiments of Li4SiO4 with di

会议

H/He IrradiationTritium BreederDamageclusters

Radiation damage measurement of Si MCZ detector irradiated by 800MeV proton

The displacement damage of n-type Si MCZ detector induced by 800MeV proton irradiation was simulated and detected with I_DLTs.The detector charge collection characteristics,leakage current and depleti

会议

Si MCZ detectorProton radiation damageRadiation defects measurement

Influence of vanadium content on the hardening of 9Cr-WVTiN reduced activation martensitic steel und

其他学术论文