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Fretting wear behavior of Zr alloy cladding tube mated with Zr alloy dimple under mixed fretting regime in simulated primary water of PWR

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Journal of Materials Science & Technology 2023年第27期158卷 43-52页

作者： Yusheng Zhang hongliang ming Jiang Lai Lixia Gao Jianqiu Wang En-Hou Han CAS Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang 110016China School of Materials Science and Engineering University of Science and Technology of ChinaShenyang 110016China Nuclear Power Institute of China Chengdu 610213China

The fretting wear behavior of Zr alloy cladding tube under mixed fretting regime in a high-temperature pressurized water was *** main wear mechanism is adhesive wear,with characters of small-scale delamination at the center of worn area and serious delamination on the worn edge.A long crack throughout the worn area and other cracks propagated towards the substrate are *** cross-sectional microstructure of worn area can be divided into a thick third-body layer,thin inner oxide layer and thick tribologically transformed structure layer,and their formation mechanisms are analyzed in ***,the mixed fretting regime process and the microstructural evolution during fretting wear are discussed.

关键词： Fretting wear Mixed fretting regime Zr alloy tube High temperature pressurized water Microstructure

Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR

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Acta Metallurgica Sinica(English Letters) 2023年第5期36卷 865-880页

作者： Yusheng Zhang Jiang Lai hongliang ming Lixia Gao Jianqiu Wang En-Hou Han School of Materials Science and Engineering University of Science and Technology of ChinaShenyang110016China CAS Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang110016China Nuclear Power Institute of China Chengdu610213China

The effect of normal force on fretting wear behavior of zirconium alloy tube mated with grid dimple in simulated primary water of pressurized water reactor nuclear power plant was *** showed that the maximum wear depth,wear volume and wear coefficient of Zr alloy tube in simulated primary water at 315℃ gradually increased with increasing normal force,while the friction coefficient gradually *** process could be divided into four stages according to the variation of friction coefficient during *** normal force exceeds 30 N,the fretting regime would transition from gross slip regime to partial slip regime after 3×10^(7 )*** was aggravated with increasing normal force,while abrasive wear became slighter.A thicker third-body layer with monoclinic ZrO_(2) was formed by the tribo-sintering mechanism under higher normal *** addition,the schematic evolution processes of delamination and third-body layer formation were displayed according to morphology observation.

关键词： Zirconium alloy tube Fretting wear Grid-to-rod High-temperature pressurized water Normal force

Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant:Microstructure and stress corrosion cracking

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Journal of Materials Science & Technology 2022年第18期113卷 229-245页

作者： Bin Wu hongliang ming Fanjiang Meng Yifeng Li Guangqing He Jianqiu Wang En-Hou Han School of Materials Science and Engineering University of Science and Technology of ChinaShenyang 110016China Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang 110016China Shanghai Nuclear Engineering Research and Design Institute Ltd.Co. Shanghai 200233China Instrumental Analysis and Research Center Shanghai UniversityShanghai 200444China Department of Materials Science Fudan UniversityShanghai 200433China Shanghai Electric Nuclear Power Equipment Co. Ltd.Shanghai 201306China

Alloy 690TT tube samples with different scratch depths were repaired by grinding treatments using abra-sive papers of two different particle *** microstructure and stress corrosion cracking(SCC)behavior were studied in *** grinding,the plastic accumulation zone vulnerable to SCC was ***,some residual slip steps remained in the scratched *** tests lasting 1000,2000,3000,and 4000 h show that the sensitivity and risk of SCC in the scratched area are decreased by *** using abrasive particles of a smaller size is more ***,deep scratches remained hazardous even after the grinding.

关键词： Alloy 690TT Scratch Surface Stress corrosion High temperature corrosion Intergranular corrosion

Multilayer Graphene:A Potential Anti-oxidation Barrier in Simulated Primary Water

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Journal of Materials Science & Technology 2014年第11期30卷 1084-1087页

作者： hongliang ming Jianqiu Wang Zhiming Zhang Siyan Wang En-Hou Han Wei Ke Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of Sciences

Multilayer graphene as a potential anti-oxidation barrier to protect nickel foils from oxidation was studied in simulated primary water of pressurized water reactors （PWRs）. The results show that after immersion for 1000 h, the structure of the multilayer graphene remains unchanged and no obvious oxide film formed on the graphene coated nickel foils, indicating multilayer graphene can effectively act as the anti-oxidation barrier to protect the substrate from oxidation and hence can improve the heat transfer efficiency of the substrate in simulated primary water of PWRs.

关键词： Graphene Raman spectroscopy X-ray photoelectron spectroscopy Anti-oxidation barrier Simulated primary water

Transferred Monolayer Graphene as a Potential Anti-Oxidation Barrier for Alloy 690TT in Simulated Primary Water

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Journal of Materials Science & Technology 2015年第12期31卷 1171-1174页

作者： hongliang ming Siyan Wang Zhiming Zhang Jianqiu Wang En-Hou Han Wei Ke Key Laboratory of Nuclear Materials and Safety Assessment Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear MaterialsInstitute of Metal ResearchChinese Academy of Sciences

To explore the usage of monolayer graphene as an anti-oxidation barrier in simulated primary water of pressurized water reactors（PWRs）,we transferred the monolayer graphene synthesized by low pressure chemical vapor deposition（LPCVD） on Cu foil to Alloy 690 *** a 500 h immersion,strong oxidation resistance was obtained from the graphene coated Alloy 690 TT sample,indicating that the transferred monolayer graphene can act as an effective barrier to protect the substrate from oxidation in simulated primary water of PWRs.

关键词： Graphene Oxidation 690TT Simulated primary water

A new method to determine the synergistic effects of area ratio and microstructure on the galvanic corrosion of LAS A508/309 L/308 L SS dissimilar metals weld

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Journal of Materials Science & Technology 2021年第19期78卷 38-50页

作者： Bright O.Okonkwo hongliang ming Jianqiu Wang En-Hou Han Ehsan Rahimi Ali Davoodi Saman Hosseinpour CAS Key Laboratory of Nuclear Materials and Safety Assessment Institute of Metal ResearchChinese Academy of SciencesShenyang 110016China School of Materials Science and Engineering University of Science and Technology of ChinaShenyang 110016China Materials and Metallurgical Engineering Department Faculty of EngineeringFerdowsi University of MashhadMashhad ***Iran Polytechnic Department of Engineering and Architecture University of Udine33100 UdineItaly John A.Paulson School of Engineering and Applied Sciences Harvard UniversityCambridgeMA 02138USA Institute of Particle Technology(LFC) Friedrich-Alexander-Universitdt-Erlangen-Numberg(FAU)91058 ErlangenGermany

The synergistic effects of area ratio and microstructure on the galvanic corrosion of A508/309 L/308 L dissimilar metals weld(DMW)are studied by a multi-analytical *** was demonstrated that decreasing the anode/cathode surface area ratio obviously enhances the corrosion rate of A508,both locally and *** analyses of the AFM results enabled quantitative comparison of the corrosion behaviour of the different surface *** was revealed that in the galvanic interaction of the DMW,the grain refined region corrodes most,followed by the partial grain refined region and base metal matrix of the A508,*** electrochemical localization index(LI)estimation method and AFM analysis both confirmed the presence of a mixed(localized and uniform)corrosion phenomenon occurring on the surface of the A508 anode metal in the galvanic interaction of the dissimilar ***,the degree of synergism equation was utilized to describe the synergistic effects of anode/cathode area ratio and the microstructure of the samples on the galvanic corrosion of LAS A508/309 L/308 L SS DMW.

关键词： Low alloy steel Stainless steel SEM AFM Galvanic corrosion Inclusion

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管线钢氢渗透行为的研究进展

中国腐蚀与防护学报 2023年第2期43卷 209-219页

作者：姚婵陈健明洪亮王俭秋中国科学院金属研究所沈阳110016 北京科技大学国家材料服役安全科学中心北京100083

天然气管道掺氢输送是现阶段氢能输送最为经济有效的方式之一,但必须重视管材与氢的相容性问题。天然气中掺入氢气后,氢通过吸附、扩散等过程进入金属管材内部,部分被氢陷阱捕获,部分在晶格间扩散。进入金属管材内部的氢是影响管线钢服... 详细信息

天然气管道掺氢输送是现阶段氢能输送最为经济有效的方式之一,但必须重视管材与氢的相容性问题。天然气中掺入氢气后,氢通过吸附、扩散等过程进入金属管材内部,部分被氢陷阱捕获,部分在晶格间扩散。进入金属管材内部的氢是影响管线钢服役性能的关键,因此,研究管线钢氢渗透行为具有十分重要的意义。本文从管线钢的氢渗透研究方法以及影响因素等方面综述了管线钢氢渗透行为的研究进展。

关键词：管线钢氢渗透扩散扩散系数

国产核电安全端异种金属焊接件的微观结构及局部性能研究

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金属学报 2017年第1期53卷 57-69页

作者：明洪亮张志明王俭秋韩恩厚苏明星中国科学院金属研究所核用材料与安全评价重点实验室辽宁省核电材料安全与评价技术重点实验室沈阳110016 中国科学院大学北京100049 上海核电装备焊接及检测工程技术研究中心上海201306

利用OM、SEM、显微硬度仪、微小试样拉伸实验及慢应变速率拉伸实验对国产带热丝隔离层核电安全端焊接件不同部位的微观结构及局部的力学性能和应力腐蚀敏感性进行了研究。发现,在SA508/52Mb界面处的52Mb中具有大量的对应力腐蚀敏感的I... 详细信息

利用OM、SEM、显微硬度仪、微小试样拉伸实验及慢应变速率拉伸实验对国产带热丝隔离层核电安全端焊接件不同部位的微观结构及局部的力学性能和应力腐蚀敏感性进行了研究。发现,在SA508/52Mb界面处的52Mb中具有大量的对应力腐蚀敏感的I型晶界及II型晶界,导致此界面具有最高的应力腐蚀敏感性;SA508热影响区存在明显的组织过渡;316LN热影响区中随着距熔合线距离的增加,重位点阵(CSL)晶界的数量分数逐渐增大,Σ3晶界与理想的Σ3晶界的偏差角减小,残余应变逐渐减小,残余应变的最高值出现在对接焊底焊位置处的316LN热影响区中,导致316LN的热影响区也具有较高的应力腐蚀敏感性。焊接件不同部位的力学性能存在较大的差异。对于硬度分布而言,显微硬度变化最剧烈的位置在SA508/52Mb界面附近,且此界面附近的52Mb具有最高的硬度,此界面附近的SA508脱C区具有最低的硬度。强度的变化趋势与硬度的变化趋势类似。一般强度高的地方断裂应变低。焊接件不同位置的性能差异主要取决于不同部位的微观结构(包含组织、成分等)差异。

关键词：异种金属焊接微观结构局部力学性能应力腐蚀敏感性残余应变

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输氢管道氢脆研究现状及进展

油气储运 2023年第10期42卷 1107-1117页

作者：杜建伟明洪亮王俭秋中国科学技术大学材料科学与工程学院中国科学院金属研究所·中国科学院核材料与安全评价重点实验室

管道输氢在实现氢能产业发展、促进能源高效利用中具有极高的经济价值,是加速实现能源转型战略的重要一环,而氢与钢质管道的相容性评价是管道输氢安全应用的前提。氢进入材料后引发的氢脆给管道安全输氢带来了极大的挑战,但氢脆机理尚... 详细信息

管道输氢在实现氢能产业发展、促进能源高效利用中具有极高的经济价值,是加速实现能源转型战略的重要一环,而氢与钢质管道的相容性评价是管道输氢安全应用的前提。氢进入材料后引发的氢脆给管道安全输氢带来了极大的挑战,但氢脆机理尚未形成统一的共识,也缺乏行之有效的防护方法。钢质管道材料氢脆行为研究能够直观给出氢进入材料后导致的力学性能变化规律,在机理研究及工程应用中均具有重要的意义。从输氢管道材料、氢脆机理、氢脆行为研究方法及影响因素等方面总结了输氢管道氢脆研究现状,从实验方法及条件与材料微观组织两个方面阐述了其对输氢管道材料氢脆行为的影响,探讨了当前所采用实验方法及结果的合理性,并提出了未来工作中需加以关注的研究方向。

关键词：管线钢氢脆氢陷阱输氢