检索结果-南通市图书馆

Oxide formation mechanism of a corrosion-resistant CZ1 zirconium alloy

Journal of Materials Science & Technology 2023年第16期147卷 6-15页

作者： Jing Hu Weitong Lin Qingyang Lv Changyuan Gao Jun Tan China Nuclear Power Technology Research Institute Shenzhen 518000GuangdongChina

Tailoring microstructure and microchemistry by altering elemental compositions and thermomechanical treatment parameters enables superior corrosion performance in zirconium alloys for nuclear applications.However,our understanding of the relationship between various defects and the corrosion process remains limited in the newly developed zirconium alloys.Here we report the oxide formation mechanism of a CZ1 zirconium alloy with corrosion resistance surpassing many other zirconium alloy systems,such as Zircaloy-4 and Zr-1Nb-1Sn alloys.Autoclave experiments of CZ1 alloy and Zr1Nb-1Sn model alloy were performed in 360°C water for up to 820 d.We quantitively determined oxide phases by transmission Kikuchi diffraction(TKD)and examined lateral cracks,nano-porosity,and second-phase particles in oxide scales by transmission electron microscopy(TEM).Compared to the Zr-1Nb-1Sn model alloy,CZ1 alloy with lower Nb and Sn concentrations has shown smaller and lower-density lateral cracks but slightly larger oxide grains,reducing the diffusion route for oxidating species.Using analytical scanning and transmission electron microscopy,we demonstrate that due to the lower content of Sn(∼0.9 wt.%),there is less tetragonal ZrO_(2) phase formed in the oxide,and the level of tetragonal to the monoclinic phase transition is reduced.Although the Nb content(0.1 wt.%–0.3 wt.%)is lower than the solid solution limit of Nb in Zr,by introducing minor elements such as Fe,Cr,and Cu,there are still a reasonable number of second-phase particles to relieve the high stress associated with the metal-to-oxide transformation.These mechanisms have substantially changed the density and distribution of lateral cracks in the oxide,thus reducing the corrosion rate of zirconium alloys.

关键词： zirconium alloy Corrosion Oxide microstructure Lateral crack Tetragonal phase Nano-porosity

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

Improvement of multi-functional properties by fabricating micro-pillar arrays structures on zirconium alloy surface

引用

Science China(Technological Sciences) 2022年第6期65卷 1243-1252页

作者： WANG XiaoLiang WANG HaoYu LIU YongDa QI Min REN QuanYao XU Jie SHAN DeBin GUO Bin Key Laboratory of Micro-systems and Micro-structures Manufacturing of Ministry of Education Harbin Institute of TechnologyHarbin 150080China School of Materials Science and Engineering Harbin Institute of TechnologyHarbin 150001China Science and Technology on Reactor System Design Technology Laboratory Chengdu 610041China

Although using the microstructure of a surface to enhance specific functions has immense applicability in numerous fields,few studies have been conducted on the multi-functional properties of nuclear fuel elements in harsh environments.In this study,surfaces with zirconium alloy micro-pillar arrays were prepared using micro-milling and ultraviolet nanosecond laser technology,and their functional properties such as the wettability,structural stability,and corrosion resistance were investigated.It was found that the geometric dimension of the micro-pillar arrays prepared using these two methods could meet the design requirements,but the micro-milling process had the best dimensional accuracy.Micro-nano multi-scale structures were obtained by laser ablation.However,these multi-scale structures exhibited weak structural stability,and the nanostructures were easily corroded.By contrast,the micro-pillar arrays manufactured using micro-milling were confirmed to have better structural stability and corrosion resistance.On one hand,the area mass loss of the micro-milled structure was lower than that of a flat surface after experiencing high-pressure fluid scouring at 8 and 38 m/s.On the other hand,the oxidation weight gain of the surface with the micro-milled structure was lower than that of a flat surface,and the oxide film was 22.5% thinner after 100 days of deionized water corrosion at 360℃ and 18.7 MPa.

关键词： zirconium alloy micro-pillar arrays wettability structural stability corrosion

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

Solid solubility extension and microstructure evolution of cast zirconium yttrium alloy

引用

Rare Metals 2016年第4期35卷 325-330页

作者： Jia-Qing Peng Yang Chen Guo-Qing Yan Ming Wu Li-Jun Wang Jing-She Li Division of Rare Metals Metallurgy and Materials General Research Institute for Nonferrous Metals School of Metallurgical and Ecological Engineering University of Science and Technology Beijing

Yttrium addition can improve the oxidation resistance, mitigate hydrogen embrittlement and thus enhance the mechanical properties of the zirconium alloy. To study solid solubility extension of yttrium in zirconium alloy, the lattice parameters of ：t-Zr phase in Zr-Y alloy were accurately determined by X-ray diffraction （XRD）. Yttrium exhibits solid solubility extension in the cast zirconium alloy which forms a metastable supersaturated solid solution with solubility limit of around 3 wt%. The effect of yttrium and thermal treatment on the microstructure of the alloys was investigated by optical microscopy （OM） and scanning electron microscope （SEM）. The cast Zr-Y alloy shows a normal polycrys- talline structure with dispersed α-Y particles when Y content is lower than 4 wt%, while the alloy shows a eutectic structure with dendrites formation when the Y content is higher. Yttrium exhibits a strong grain refining effect on zirconium alloy and precipitates from the metastable supersaturated Zr matrix after annealing at 700 and 900 ℃.

关键词： zirconium alloy Yttrium addition Solidsolubility extension Microstructure

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

Interfacial reaction between zirconium alloy and graphite mold/yttrium oxide ceramic mold

引用

China Foundry 2014年第2期11卷 85-90页

作者： Xie Huasheng Liu Hongyu Zhao Jun Liu Shibing Shi Kun Shenyang Research Institute of Foundry

zirconium alloys are active in the molten state and tend to react with the mold during casting. The casting technology of zirconium is not yet well established; especially in selecting the mold materials, which are diffi cult to determine. In the present work, the interfacial reactions between zirconium casting and casting mold were studied. The zirconium alloy was melted in a vacuum arc skull furnace and then cast into the graphite mold and ceramic mold, respectively. The zirconium casting samples were characterized using SEM, EDS and XRD with an emphasis on the chemical diffusion of elements. A reaction layer was observed at the casting surface. Chemical analysis shows that chemical elements C, O and Y from the mold are diffused into the molten zirconium, and new phases, such as ZrC, Zr3O, YO1.335 and Y6ZrO11, are formed at the surface. In addition, an end product of zirconium valve cast in a yttria mold has a compact structure and good surface quality.

关键词： graphite mold yttrium oxide ceramic mold zirconium alloy reaction layer

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

Fretting Wear Characteristics of Nuclear Fuel Cladding in High-Temperature Pressurized Water

引用

Chinese Journal of Mechanical Engineering 2023年第4期36卷 326-338页

作者： Jun Wang Haojie Li Zhengyang Li Yujie Lei Quanyao Ren Yongjun Jiao Zhenbing Cai Key Lab of Advanced Technologies of Materials Tribology Research InstituteSouthwest Jiaotong UniversityChengdu 610031China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

In pressurized water reactor(PWR),fretting wear is one of the main causes of fuel assembly failure.Moreover,the operation condition of cladding is complex and harsh.A unique fretting damage test equipment was developed and tested to simulate the fretting damage evolution process of cladding in the PWR environment.It can simulate the fretting wear experiment of PWR under different temperatures(maximum temperature is 350℃),displacement amplitude,vibration frequency,and normal force.The fretting wear behavior of Zr-4 alloy under different temperature environments was tested.In addition,the evolution of wear scar morphology,profile,and wear volume was studied using an optical microscope(OM),scanning electron microscopy(SEM),and a 3D white light interferometer.Results show that higher water temperature evidently decreased the cladding wear volume,the wear mechanism of Zr-4 cladding changed from abrasive wear to adhesive wear and the formation of an oxide layer on the wear scar reduced the wear volume and maximum wear depth.

关键词： Fretting wear Cladding High temperature and high pressure zirconium alloy

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

Relations of Microstructural Attributes and Strength-Ductility of zirconium alloys with Hydrides

引用

Chinese Journal of Mechanical Engineering 2023年第4期36卷 407-419页

作者： Chao Fang Xiang Guo Jianghua Li Gang Chen School of Mechanical Engineering Tianjin UniversityTianjin 300354China Tianjin Key Laboratory of Nonlinear Dynamics and Control Tianjin 300072China State Key Laboratory of Nonlinear Mechanics Institute of MechanicsChinese Academy of SciencesBeijing 100190China School of Chemical Engineering and Technology Tianjin UniversityTianjin 300072China

As the first safety barrier of nuclear reactors,zirconium alloy cladding tubes have attracted extensive attention because of its good mechanical properties.The strength and ductility of zirconium alloy are of great significance to the service process of cladding tubes,while brittle hydrides precipitate and thus deteriorate the overall performance.Based on the cohesive finite element method,the effects of cohesive strength,interfacial characteristics,and hydrides geometric characteristics on the strength and ductility of two-phase material(zirconium alloy with hydrides)are numerically simulated.The results show that the fracture behavior is significantly affected by the cohesive strength and that the overall strength and ductility are sensitive to the cohesive strength of the zirconium alloy.Furthermore,the interface is revealed to have prominent effects on the overall fracture behavior.When the cohesive strength and fracture energy of the interface are higher than those of the hydride phase,fracture initiates in the hydrides,which is consistent with the experimental phenomena.In addition,it is found that the number density and arrangement of hydrides play important roles in the overall strength and ductility.Our simulation provides theoretical support for the performance analysis of hydrogenated zirconium alloys during nuclear reactor operation.

关键词： zirconium alloy Hydride Strength and ductility Cohesive finite element method Microcrack initiation and propagation

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

Microstructure of Bi-containing zirconium alloys

引用

Rare Metals 2022年第10期41卷 3566-3573页

作者： Han-Pei Zhao Mei-Yi Yao Jiao Huang Jin-Long Zhang Jian-Chao Peng Bang-Xin Zhou Laboratory for Microstructure Shanghai UniversityShanghai200444China Institute of Materials Shanghai UniversityShanghai200072China

The effect of Bi addition(0.05 wt%-0.50 wt%)on the microstructure of zirconium alloys,including T5(Zr-0.7 S n-1.0 Nb-0.3 Fe-0.1 Cr),S5(Zr-0.8 Sn-0.35 Nb-0.4 Fe-0.1 Cr),Zr-4(Zr-1.5 Sn-0.2 Fe-0.1 Cr) and Zr-1 Nb,was investigated by transmission electron microscopy(TEM),energy-dispersive spectroscopy(EDS) and selected area electron diffraction(SAED).Results show that with the increase in Bi content,h-Zr(Fe,Cr,Nb)2,o-Zr(Fe,Sn,Bi)_(2) and Zr-Fe-Cr-Nb-Sn-Bi second-phase particles(SPPs) precipitate successively in the T5+xBi and S5+xBi alloys;in the Zr-4+xBi alloys,h-Zr(Fe,Cr)2,o-Zr(Fe,Sn,Bi)2,Zr-Fe-Cr-Sn-Bi and Zr-Fe-Cr-Bi SPPs are detected successively.While as for Zr-1 Nb+xBi alloys,Bi-free SPPs appear.The addition of Bi promotes the precipitation of SPPs with Sn in the alloys.The concentration of Bi dissolved in α-Zr matrix increases with the decrease in Sn content in the alloys.Adding reasonable Bi has little influence on the solid solution content of Nb in α-Zr matrix.

关键词： zirconium alloy Bismuth Second-phase particles Microstructure

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

Microstructure and properties of as-cast Zr-2.5Nb-1X(X=Ru,Mo,Ta and Si) alloys for biomedical application

引用

Rare Metals 2023年第10期42卷 3497-3509页

作者： Xi-Nu Tan Fei-Tao Li Yu-Shun Liu Ri-Sheng Qiu Qing Liu Electron Microscopy Center College of Materials Science and EngineeringChongqing UniversityChongqing400044China International Joint Laboratory for Light alloys(MOE) College of Materials Science and EngineeringChongqing UniversityChongqing400044China TU Ilmenau Chair Materials for Electrical Engineering and ElectronicsInstitute of Materials Science and Engineering and Institute of Micro-and Nanotechnologies MacroNanoIlmenau98693Germany Department of Mechanical Engineering University of ManitobaWinnipegMBR3T 5V6Canada Key Laboratory for Light-Weight Materials Nanjing Tech UniversityNanjing210009China

The micro structure and properties of as-cast Zr-2.5Nb-1X(X=Ru,Mo,Ta and Si) alloy are screened to explore novel biomedical zirconium alloys for magnetic resonance applications.Corresponding micro structure and phase transformation were characterized using X-ray diffraction(XRD),scanning electron microscope(SEM)and transmission electron microscope(TEM).Hardness test,magnetic detection and electrochemical corrosion measurements are taken to present properties.The results show that all alloys consist of α-Zr,β-Zr and ω-Zr.α-Zr and β-Zr mainly exist in the form of parallel and intersecting plates,and nanoscale ω-Zr is dispersed in β-Zr plate.Especially,blocky ω-Zr with needle-like α-Zr is only found in plate-free blocks of Zr-2.5Nb-1Mo/Ru alloy.The orientation relationship(OR) between α-Zr and ω-Zr follows [1120]_α//[1101]_ω and(0001)_α//([1011]_ω 011)_ω.Combining this OR with the OR between β-Zr and ω-Zr,the transformation relationship between β-Zr/ω-Zr and α-Zr is also discussed.Zr-2.5Nb-1Ru alloy with high corrosion potential(-0.500 V),low corrosion rate(0.949 μm·year^(-1)) and low magnetic susceptibility(92×10^(-6)) shows great potential to be a novel biomedical implant with magnetic resonance imaging compatibility.Based on the experimental results,the possible relationship among alloying elements,micro structure and properties has been established in these Zr-2.5Nb-1X alloys.

关键词： zirconium alloy Microstructure Phase transformation Electrochemical corrosion Magnetic susceptibility

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

CREEP BEHAVIOR OF Zr-1.5Nb-0.4Sn-0.1Fe-0.1Cu alloy

引用

Acta Mechanica Solida Sinica 2008年第4期21卷 308-311页

作者： Ji Young Kim Kwang Su Na Yong Duck Kim Ji Hui Kim Kwon Yeong Lee Ki Nam Kim Seon Jin Kim Division of Advanced Materials Science and Engineering Hanyang University133-791Korea Technical Research Center Sheet Products Design TeamHyundai Steel CompanyKodae-RiSongak-MyeonDangjin-GunChungnam167-32Korea

Creep behavior of the Zr-1.5Nb-0.4Sn-0.1Fe-0.1Cu alloy sheet is investigated from 300℃ to 400℃ in the stress range from 50 MPa to 180 MPa along the rolling direction. The measured strain rates range from 8.8 × 10^-10 s^-1 to 4.7 × 10^-7 s^-1. The activation energies are estimated to assess the creep deformation mechanisms in this alloy. The strain rate is slightly different at low stress, while it shows a distinct difference at high stresses. Stress exponents of this alloy increase with increasing applied stress at all testing temperatures. It is concluded that the creep deformation of the Zr-1.5Nb-0.4Sn-0.1Fe-0. 1 Cu alloy is controlled by the diffusion creep at low stress region and by the climbing of dislocations at high stress region.

关键词： creep zirconium alloy nuclear cladding

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

High-zirconium bulk metallic glasses with high strength and large ductility

引用

Science China(Physics,Mechanics & Astronomy) 2013年第3期56卷 540-544页

作者： YANG YaoWei HUA NengBin LI Ran PANG ShuJie ZHANG Tao Key Laboratory of Aerospace Materials and Performance(Ministry of Education) School of Materials Science and EngineeringBeihang University

In this paper,high-zirconium Zr66+2xAl9-x(Ni1/3Cu2/3) 25-x(x=0,1,2 at.%) bulk metallic glasses with high strength and large ductility were fabricated by copper mould casting.The effects of zirconium content on the glass-forming ability(GFA),thermal properties and mechanical properties were investigated using X-ray diffractometer(XRD),differential scanning calorimeter(DSC),and mechanical testing system in compressive and three-point bending modes,respectively.The high-zirconium BMGs show the critical diameters of 3-5 mm,the supercooled liquid region ranging from 70 K to 99 K,and the yield strength of over 1700 MPa.The Zr 70 Al 7(Ni1/3Cu2/3) 23 BMG exhibits a large compressive plastic strain up to 21% and a high notch toughness value of 60.6 MPa m 1/2.The increase in Zr content results in the decrease in GFA and thermostability,and in the improvement of plasticity under compressive and three-point bending conditions.The superior plasticity of high-zirconium BMGs is attributed to their high Poisson’s ratio and small elastic modulus ratio /B.

关键词： bulk metallic glass zirconium alloy mechanical property elastic modulus

来源：

同方期刊数据库评论

在线全文

同方期刊数据库

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

在线全文

在线全文

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

在线全文

在线全文

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：