The Microstructure and Mechanical and Corrosion Behaviors of Thermally Aged Z3CN20-09M Cast Stainless Steel for Primary Coolant Pipes of Nuclear Power Plants
The effects of thermal aging time at 400 °C on the microstructure and mechanical and corrosion behaviors of Z3CN20.09M cast stainless steel were investigated; and the corresponding thermal aging mechanism was studied. It was revealed that the changes in mechanical properties after thermal aging were...
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Veröffentlicht in: | Coatings (Basel) 2021-08, Vol.11 (8), p.870, Article 870 |
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description | The effects of thermal aging time at 400 °C on the microstructure and mechanical and corrosion behaviors of Z3CN20.09M cast stainless steel were investigated; and the corresponding thermal aging mechanism was studied. It was revealed that the changes in mechanical properties after thermal aging were mainly caused by the iron-rich phase (α) and the chromium-rich phase (α’) produced by the amplitude-modulation decomposition of ferrite. A similar trend of thermoelectric potential during thermal aging was determined in relation to the Charpy impact energy. However, the corrosion resistance of Z3CN20.09M cast stainless steel deteriorates as thermal aging time increases. When the thermal aging is longer than 3000 h, the precipitation of G phase has a great influence on the corrosion resistance. The interfacial matching relationship between G phase and the surrounding ferrite was established by selected area electron diffraction of HRTEM. The relationship is of cube-on-cube phase boundary type. The impact fracture mechanisms in relation to thermal aging time were also studied and compared. |
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It was revealed that the changes in mechanical properties after thermal aging were mainly caused by the iron-rich phase (α) and the chromium-rich phase (α’) produced by the amplitude-modulation decomposition of ferrite. A similar trend of thermoelectric potential during thermal aging was determined in relation to the Charpy impact energy. However, the corrosion resistance of Z3CN20.09M cast stainless steel deteriorates as thermal aging time increases. When the thermal aging is longer than 3000 h, the precipitation of G phase has a great influence on the corrosion resistance. The interfacial matching relationship between G phase and the surrounding ferrite was established by selected area electron diffraction of HRTEM. The relationship is of cube-on-cube phase boundary type. The impact fracture mechanisms in relation to thermal aging time were also studied and compared.</description><identifier>ISSN: 2079-6412</identifier><identifier>EISSN: 2079-6412</identifier><identifier>DOI: 10.3390/coatings11080870</identifier><language>eng</language><publisher>Basel: MDPI AG</publisher><subject>Aging ; Aging (metallurgy) ; Chromium ; Corrosion resistance ; Crack initiation ; Crack propagation ; Electrodes ; Electron diffraction ; Ferrites ; Fracture mechanics ; Mechanical properties ; Microstructure ; Morphology ; Nuclear energy ; Nuclear power plants ; Nuclear reactors ; Particle size ; Phase matching ; Pipes ; Spectrum analysis ; Stainless steel ; Stainless steels ; Stress concentration</subject><ispartof>Coatings (Basel), 2021-08, Vol.11 (8), p.870, Article 870</ispartof><rights>2021 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/). 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The impact fracture mechanisms in relation to thermal aging time were also studied and compared.</description><subject>Aging</subject><subject>Aging (metallurgy)</subject><subject>Chromium</subject><subject>Corrosion resistance</subject><subject>Crack initiation</subject><subject>Crack propagation</subject><subject>Electrodes</subject><subject>Electron diffraction</subject><subject>Ferrites</subject><subject>Fracture mechanics</subject><subject>Mechanical properties</subject><subject>Microstructure</subject><subject>Morphology</subject><subject>Nuclear energy</subject><subject>Nuclear power plants</subject><subject>Nuclear reactors</subject><subject>Particle size</subject><subject>Phase matching</subject><subject>Pipes</subject><subject>Spectrum analysis</subject><subject>Stainless steel</subject><subject>Stainless steels</subject><subject>Stress concentration</subject><issn>2079-6412</issn><issn>2079-6412</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><recordid>eNp1kU1LAzEQhhdRULR3jwHPq5Ok290cdfEL2lqoJy9LNp3YSNzUJKv0x_hfTVsPUnAOmQl53neYTJadU7jkXMCVcjKa7jVQChVUJRxkJwxKkY-GlB3-qY-zQQhvkEJQXlFxkn0_L5FMjPIuRN-r2HsksluQCaql7IySdnutnU-EcR25waX8NM4H4jRJYv8urV2T61dckBdeTxnkICakliGSeZSmsxhCqhAt0c6TmTfv0q-To7Oyi2RmVrj1mvbKokyA-8J0bh7DWXakpQ04-M2n2fzu9rl-yMdP94_19ThXnPKYDzloXkrdMtBUwUJXjCNlEoUQrRiKdqRbFKVuC6aqBW25ZBUwLEEXbVvw0-xi57ry7qPHEJs31_suNWxYMSpADIuCJwp21OavgkfdrHajNBSazRaa_S0kyWhPokxMjOuil8b-L_wBumqQQA</recordid><startdate>20210801</startdate><enddate>20210801</enddate><creator>Xue, Fei</creator><creator>Shi, Fangjie</creator><creator>Zhang, Chuangju</creator><creator>Zheng, Qiaoling</creator><creator>Yi, Dawei</creator><creator>Li, Xiuqing</creator><creator>Li, Yefei</creator><general>MDPI AG</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>8BQ</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>D1I</scope><scope>DWQXO</scope><scope>HCIFZ</scope><scope>JG9</scope><scope>KB.</scope><scope>PDBOC</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PRINS</scope></search><sort><creationdate>20210801</creationdate><title>The Microstructure and Mechanical and Corrosion Behaviors of Thermally Aged Z3CN20-09M Cast Stainless Steel for Primary Coolant Pipes of Nuclear Power Plants</title><author>Xue, Fei ; Shi, Fangjie ; Zhang, Chuangju ; Zheng, Qiaoling ; Yi, Dawei ; Li, Xiuqing ; Li, Yefei</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c313t-430f37afb20f1c0df823e12ae999b949b6fbe97fb52c8d1b3a2802e70f5bb53</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Aging</topic><topic>Aging (metallurgy)</topic><topic>Chromium</topic><topic>Corrosion resistance</topic><topic>Crack initiation</topic><topic>Crack propagation</topic><topic>Electrodes</topic><topic>Electron diffraction</topic><topic>Ferrites</topic><topic>Fracture mechanics</topic><topic>Mechanical properties</topic><topic>Microstructure</topic><topic>Morphology</topic><topic>Nuclear energy</topic><topic>Nuclear power plants</topic><topic>Nuclear reactors</topic><topic>Particle size</topic><topic>Phase matching</topic><topic>Pipes</topic><topic>Spectrum analysis</topic><topic>Stainless steel</topic><topic>Stainless steels</topic><topic>Stress concentration</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Xue, Fei</creatorcontrib><creatorcontrib>Shi, Fangjie</creatorcontrib><creatorcontrib>Zhang, Chuangju</creatorcontrib><creatorcontrib>Zheng, Qiaoling</creatorcontrib><creatorcontrib>Yi, Dawei</creatorcontrib><creatorcontrib>Li, Xiuqing</creatorcontrib><creatorcontrib>Li, Yefei</creatorcontrib><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central (Alumni Edition)</collection><collection>ProQuest Central UK/Ireland</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Materials Science Collection</collection><collection>ProQuest Central Korea</collection><collection>SciTech Premium Collection</collection><collection>Materials Research Database</collection><collection>Materials Science Database</collection><collection>Materials Science Collection</collection><collection>Publicly Available Content Database</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>ProQuest Central China</collection><jtitle>Coatings (Basel)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Xue, Fei</au><au>Shi, Fangjie</au><au>Zhang, Chuangju</au><au>Zheng, Qiaoling</au><au>Yi, Dawei</au><au>Li, Xiuqing</au><au>Li, Yefei</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>The Microstructure and Mechanical and Corrosion Behaviors of Thermally Aged Z3CN20-09M Cast Stainless Steel for Primary Coolant Pipes of Nuclear Power Plants</atitle><jtitle>Coatings (Basel)</jtitle><date>2021-08-01</date><risdate>2021</risdate><volume>11</volume><issue>8</issue><spage>870</spage><pages>870-</pages><artnum>870</artnum><issn>2079-6412</issn><eissn>2079-6412</eissn><abstract>The effects of thermal aging time at 400 °C on the microstructure and mechanical and corrosion behaviors of Z3CN20.09M cast stainless steel were investigated; and the corresponding thermal aging mechanism was studied. It was revealed that the changes in mechanical properties after thermal aging were mainly caused by the iron-rich phase (α) and the chromium-rich phase (α’) produced by the amplitude-modulation decomposition of ferrite. A similar trend of thermoelectric potential during thermal aging was determined in relation to the Charpy impact energy. However, the corrosion resistance of Z3CN20.09M cast stainless steel deteriorates as thermal aging time increases. When the thermal aging is longer than 3000 h, the precipitation of G phase has a great influence on the corrosion resistance. The interfacial matching relationship between G phase and the surrounding ferrite was established by selected area electron diffraction of HRTEM. The relationship is of cube-on-cube phase boundary type. 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subjects | Aging Aging (metallurgy) Chromium Corrosion resistance Crack initiation Crack propagation Electrodes Electron diffraction Ferrites Fracture mechanics Mechanical properties Microstructure Morphology Nuclear energy Nuclear power plants Nuclear reactors Particle size Phase matching Pipes Spectrum analysis Stainless steel Stainless steels Stress concentration |
title | The Microstructure and Mechanical and Corrosion Behaviors of Thermally Aged Z3CN20-09M Cast Stainless Steel for Primary Coolant Pipes of Nuclear Power Plants |
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