检索结果-南通市图书馆

Microstructure,hardening and Deuterium retention in CVD tungsten irradiated with neutrons at temperatures of defect recovery stagesⅡandⅢ

引用

Tungsten 2022年第3期4卷 248-260页

作者： Xiao-Ou Yi Tatsuya Kuwabara Vladimir KhAlimov Yu-Feng Du Wen-Tuo Han Ping-Ping Liu Bin-You Yan Jiu-Peng Song Kenta Yoshida Takeshi Toyama Fa-Rong Wan Somei Ohnuki Yuji Hatano Yasuyoshi Nagai School of Materials Science and Engineering University of Science and Technology BeijingBeijing100083China Graduate School of Engineering Nagoya UniversityFuro-choChikusa-kuNagoya464-8063Japan Frumkin Institute of Physical Chemistry and Electrochemistry Russian Academy of SciencesMoscow119071Russia Institute for Materials Research Tohoku UniversityNarita-cho 2145-2OaraiIbaraki311-1313Japan Xiamen Tungsten Co.Ltd. Xiamen361021China School of Materials Science and Engineering Xihua UniversityChengdu610039China Hydrogen Isotope Research Center University of ToyamaToyama930-8555Japan

Samples of ultra-high-purity tungsten prepared using chemical vapour deposition(CVD)technique were irradiated with neutrons at temperatures T_(irr)=373-483 K(stage Ⅱ of defect recovery)and T_(irr)=573-673 K(stage Ⅲ)up to 0.15 displacements per atom(dpa)in the Belgian reactor(BR2).The study of the microstructure of neutron-damaged samples using transmission electron microscopy(TEM)revealed visible defects with a predominance of dislocation loops.With an increase in the neutron irradiation temperature,the spatial distribution of the loops acquired pronounced inhomogeneity,and their average size moderately increased.Cavities and voids were not observed.Irradiation-induced hardening was found and a linear correlation was obtained between Vickers microhardness and nanohardness for undamaged and neutron-irradiated CVD-W samples.Irradiation of tungsten with neutrons led to a significant increase in the retention of deuterium,which accumulated mainly in vacancy-type traps.Furthermore,the influence of the columnar grain structure in low-dose neutron-irradiated tungsten seemed to be non-trivial upon Deuterium retention.

关键词： CVD-W Neutron irradiation Microstructure Hardening Deuterium retention

来源：

维普期刊数据库

同方期刊数据库评论

在线全文

学校读者我要写书评

暂无评论

Deuterium retention in SiC-Coated Graphite Tiles of EAST

引用

Plasma Science and Technology 2014年第3期16卷 193-196页

作者：赵利平王万景周海山吴婧谢春意李强杨钟时罗广南 Institute of Plasma Physics Chinese Academy of Sciences Research Center of Laser Fusion China Academy of Engineering Physics

Fuel retention and recycling in plasma facing materials is a crucial issue for fusion devices, especially for the long pulse discharge devices. In this work, the Deuterium retention and the surface erosion of SiC-coated graphite tiles exposed to EAST plasmas have been studied by post-mortem analyses, i.e., thermal desorption spectroscopy （TDS）, secondary ion mass spec- troscopy （SIMS） and scanning electron microscopy （SEM）. The results show that the sample cut from the high field side （HF） tile has been intensely eroded due to deuterium bombardment on plasma facing surfaces in the initial phase of discharges and trapped highest amount of deuterium. Lower Deuterium retention has been found in the inner divertor sample, which is presumably due to the particular exposure history in the 2010 spring campaign.

关键词： Deuterium retention post-mortem analyses SiC-coated graphite tiles EAST

来源：

维普期刊数据库

同方期刊数据库评论

在线全文

学校读者我要写书评

暂无评论

Erosion and Deuterium retention behavior of tungsten exposed to impurity-seeded deuterium plasma

引用

Tungsten 2021年第4期3卷 448-458页

作者： Hong Zhang Han-Wen Zhang Li Qiao Xue-Xi Zhang Ran He Peng Wang State Key Laboratory of Solid Lubrication Lanzhou Institute of Chemical PhysicsChinese Academy of SciencesLanzhou 730000China Center of Materials Science and Optoelectronics Engineering University of Chinese Academy of SciencesBeijing 100049China School of Nuclear Science and Technology Lanzhou UniversityLanzhou 730000China

The effect of plasma impurity seeding on erosion and deuterium(D)retention behavior of tungsten(W)is investigated on linear experimental plasma system(LEPS).The incident D energy is 38 and 71 eV per D,and the D fluence varies from 3×10^(23)to 1×10^(26)D·m^(-2).The results of erosion reveal that argon(Ar)seeding strongly enhances erosion,helium(He)seed-ing slightly increases sputtering yield depending on the ratio of He in plasma,while nitrogen(N)seeding inhibits erosion and reduces the sputtering yield.Furthermore,O impurity dominates the erosion behavior during pure D plasma exposure when the D incident energy is lower than the sputtering threshold of W by D.For blistering and D retention behavior,compared with pure D exposure,Ar seeding reduces the amount and increases the size of blister,and leads to the increase of D inven-tory.He seeding has the opposite result,showing almost no blisters at sample surface and a dramatic drop in D retention.D retention decreases with increasing N content,and ruptured blisters are observed at a high D fluence of 1×10^(26)D·m^(-2).

关键词： Tungsten Erosion Deuterium retention Impurity seeding

来源：

维普期刊数据库

同方期刊数据库评论

在线全文

学校读者我要写书评

暂无评论

Overview of wall probes for erosion and deposition studies in the TEXTOR tokamak

引用

Matter and Radiation at Extremes 2017年第3期2卷 87-104页

作者： M.Rubel S.Brezinsek J.W.Coenen A.Huber A.Kirschner A.Kreter P.Petersson V.Philipps A.Pospieszczyk B.Schweer G.Sergienko T.Tanabe Y.Ueda P.Wienhold Department of Fusion Plasma Physics Royal Institute of TechnologyS-10044 StockholmSweden Forschungszentrum Julich GmbH Institut fur Energie-und Klimaforschung-PlasmaphysikPartner of the Trilateral Euregio Cluster(TEC)52425 JulichGermany Interdisciplinary Graduate School of Engineering Science Kyushu UniversityJapan Graduate School of Engineering Osaka UniversityOsaka 565-0871Japan

An overview of diagnostic tools e test limiters and collector probes e used over the years for material migration studies in the TEXTOR tokamak is presented.Probe transfer systems are shown and their technical capabilities are described.This is accompanied by a brief pre-sentation of selected results and conclusions from the research on material erosion e deposition processes including tests of candidate materials(e.g.W,Mo,carbon-based composites)for plasma-facing components in controlled fusion devices.The use of tracer techniques and methods for analysis of materials retrieved from the tokamak are summarized.The impact of research on the reactor wall technology is addressed.

关键词： Erosion-deposition Material migration Deuterium retention Carbon Tungsten TEXTOR

来源：

维普期刊数据库评论

在线全文

维普期刊数据库

学校读者我要写书评

暂无评论

欢迎您,

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

在线全文

在线全文

在线全文

在线全文

请选择保存的检索档案：

请选择收藏分类：

通借通还

欢迎您,

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

在线全文

在线全文

在线全文

在线全文

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：