Investigation on the magnetic field distortion by ferromagnetism of the blanket for the helical fusi

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：chf012183

【摘要】

：

【作者】

：

Xiang Ji Nagato Yanagi Takuya Goto Hitoshi Tamura Junichi Miyazawa Akio Sagara Songke Wang Minzhong Qi Yuntao Song

【机构】

：

National Institute for Fusion Science,322-6 Oroshi-cho,Toki 509-5292,Japan;Institute of Plasma Physi

【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】

：

Ferritic steel HHFR Magnetic field Corresponding author

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

　　In the future fusion reactors,ferritic steel is a realistic candidate to be used as a structural material of the blanket,because of the low activation characteristics after neutron irradiation which can reduce the issue of radioactive waste disposal.However,since the ferritic steel is a ferromagnetic material,distortion of magnetic field produced by the magnet coils is a concern on the plasma confinement due to island formation and partial changes of magnetic surfaces.

其他文献

First-principles investigation on the hydrogen permeation properties of Cr2O3/Al2O3 interface fabric

Al2O3 and Cr2O3 are two representative materials of tritium permeation barriers and composite coating has become a trend to develop the tritium permeation barriers.The mechanism for diffusion of hydro

会议

Cr2O3Al2O3InterfaceFirst-principlesHydrogen diffusion

LBE corrosion on the iron-based structure materials in ADS

Liquid lead(Pb)-bismuth(Bi)eutectic(LBE)is a promising candidate as coolant in the accelerator driven nuclear system(ADS),but it will result in degradation of iron-based structure materials due to the

会议

Iron-based structure materialsLBEDissolution corrosionDiffusion

Solubility calculation of the corrosion products in water-cooled reactors and its application in CAT

Activated corrosion products(ACPs)in the cooling loops are the dominant radioactive source in water-cooled reactors and have great influence on shielding design,personnel protection,and consequences o

会议

Activated Corrosion ProductsSolubilityChemical EquilibriumCATEPCCL

The different behavior of iron surfaces under irradiation

The mechanical and physical properties of structural materials in fission/fussion system could be changed under the energetic particle irradiation.These effects are due to microstructural changes that

会议

Iron-based structure materialsRadiation damageSurface effect

Characterization on the oxide/matrix interface structure and its effect on the mechanical properties

Oxide dispersion strengthened(ODS)ferritic steels are considered as the most promising candidate materials for future fission and fusion structural materials.The ODS-CLAM steel was fabricated by mecha

会议

ODS-CLAMnano-particlesinterfacial structuremechanical property

Concepts development of FDS series fusion reactors and liquid PbLi blankets

A series of fusion reactor(named FDS series)have been designed and assessed for the examination of the feasibility and the safety,environmental and economic potential of fusion with emphasizing the bl

会议

Fusion power plantLiquid PbLi blanketTest Blanket ModuleFusion test reactor

Residual radioactivity analysis of China Low Activation Martensitic steel after neutron irradiation

The Reduces Activation Ferritic/Martensitic(RAFM)steel is considered as the primary candidate structural material for demonstration plant(DEMO)and the first fusion plant,and widely studied in the worl

会议

Low activationCLAMNeutron irradiationResidual radioactivity

Thermal-stress analysis on the crack formation of tungsten during fusion relevant transient heat loa

In the fusion devices,tungsten based plasma-facing materials will be exposed to transient heat loads during plasma disruptions,edge localized modes and vertical displacement events,which would cause d

会议

plasma-facing materialsTungstenFEAcrack thresholdFatigue lifetime

Research on noise reduction technology of fast neutron radiography

Here presented the system of fast neutron radiography on Cockcroft-Walton Neutron Generator in China Institute of Atomic Energy,based on 14.1MeV neutron source.Its been done to investigate the positio

会议

Fast Neutron RadiographyNoise ReductionProton Crosstalkneutron source

The grey correlation degree analysis of the influence factors on control rod dropping in Lead-Bismut

The work presented in this paper focuses on the assess of the role of liquid velocity,control rods weight,mechanical friction,temperature and composition of Lead-Bismuth Eutectic(LBE)in control rod dr

会议

LBERods DroppingGrey correlation degree

Investigation on the magnetic field distortion by ferromagnetism of the blanket for the helical fusi

其他学术论文