Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process
1Effect of cracks on the oxidation properties of Cr-coated Zr is investigated.2Microstructures of Cr-coated Zr with cracks during oxidation process are analyzed.3Cracks in Cr coatings are self-healed when the temperature increased to 1000 °C.4Cr coatings with cracks can still protect the substrate w...
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Veröffentlicht in: | Journal of nuclear materials 2022-01, Vol.558, p.153327, Article 153327 |
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container_title | Journal of nuclear materials |
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creator | Ma, Hai-Bin Zhao, Ya-Huan Liu, Yang Zhu, Jing-Ting Yan, Jun Liu, Tong Ren, Qi-Sen Liao, Ye-Hong Liu, Gang Lin, Xiao-Dong Yao, Mei-Yi |
description | 1Effect of cracks on the oxidation properties of Cr-coated Zr is investigated.2Microstructures of Cr-coated Zr with cracks during oxidation process are analyzed.3Cracks in Cr coatings are self-healed when the temperature increased to 1000 °C.4Cr coatings with cracks can still protect the substrate well in oxidation conditions.
Cr-coated Zr alloy claddings, prepared via physical vapor deposition (PVD), were used to study the damage evolution under a series of high-temperature steam oxidation conditions. Through-thickness cracks were initially produced within the Cr coat by internal pressure creep test. The Cr-coated samples with cracks were then oxidized at temperatures from 800 °C to 1200 °C in water steam environment. Microstructures of the samples before and after oxidation were characterized in comparison by scanning electronic microscopy, transmission electronic microscopy and energy dispersion spectrometry. The results showed that a large proportion of cracks would be self-healed when the temperature increased to 1000 °C. At the places where the cracks have survived, the corresponding Zr substrate regions were oxidized to form semi-spherical or fan-shaped ZrO2. However, the maximum depth of ZrO2 under the unhealed cracks was smaller than that of the uncoated claddings at the same oxidation conditions. |
doi_str_mv | 10.1016/j.jnucmat.2021.153327 |
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Cr-coated Zr alloy claddings, prepared via physical vapor deposition (PVD), were used to study the damage evolution under a series of high-temperature steam oxidation conditions. Through-thickness cracks were initially produced within the Cr coat by internal pressure creep test. The Cr-coated samples with cracks were then oxidized at temperatures from 800 °C to 1200 °C in water steam environment. Microstructures of the samples before and after oxidation were characterized in comparison by scanning electronic microscopy, transmission electronic microscopy and energy dispersion spectrometry. The results showed that a large proportion of cracks would be self-healed when the temperature increased to 1000 °C. At the places where the cracks have survived, the corresponding Zr substrate regions were oxidized to form semi-spherical or fan-shaped ZrO2. However, the maximum depth of ZrO2 under the unhealed cracks was smaller than that of the uncoated claddings at the same oxidation conditions.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2021.153327</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Accident tolerant fuel (ATF) cladding ; Chromium coating ; Claddings ; Coatings ; Cracks ; Creep tests ; Heat resistant alloys ; High temperature ; Internal pressure ; Microscopy ; Oxidation ; Oxidation behavior ; Oxidation process ; Physical vapor deposition ; Self-healing ; Spectrometry ; Steam ; Substrates ; Zirconium base alloys ; Zirconium dioxide</subject><ispartof>Journal of nuclear materials, 2022-01, Vol.558, p.153327, Article 153327</ispartof><rights>2021</rights><rights>Copyright Elsevier BV Jan 2022</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-405454c607a2d26f2acf0850b28e0ba56e7c9a28d13718b50dc7543a6abc5fe63</citedby><cites>FETCH-LOGICAL-c337t-405454c607a2d26f2acf0850b28e0ba56e7c9a28d13718b50dc7543a6abc5fe63</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.jnucmat.2021.153327$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids></links><search><creatorcontrib>Ma, Hai-Bin</creatorcontrib><creatorcontrib>Zhao, Ya-Huan</creatorcontrib><creatorcontrib>Liu, Yang</creatorcontrib><creatorcontrib>Zhu, Jing-Ting</creatorcontrib><creatorcontrib>Yan, Jun</creatorcontrib><creatorcontrib>Liu, Tong</creatorcontrib><creatorcontrib>Ren, Qi-Sen</creatorcontrib><creatorcontrib>Liao, Ye-Hong</creatorcontrib><creatorcontrib>Liu, Gang</creatorcontrib><creatorcontrib>Lin, Xiao-Dong</creatorcontrib><creatorcontrib>Yao, Mei-Yi</creatorcontrib><title>Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process</title><title>Journal of nuclear materials</title><description>1Effect of cracks on the oxidation properties of Cr-coated Zr is investigated.2Microstructures of Cr-coated Zr with cracks during oxidation process are analyzed.3Cracks in Cr coatings are self-healed when the temperature increased to 1000 °C.4Cr coatings with cracks can still protect the substrate well in oxidation conditions.
Cr-coated Zr alloy claddings, prepared via physical vapor deposition (PVD), were used to study the damage evolution under a series of high-temperature steam oxidation conditions. Through-thickness cracks were initially produced within the Cr coat by internal pressure creep test. The Cr-coated samples with cracks were then oxidized at temperatures from 800 °C to 1200 °C in water steam environment. Microstructures of the samples before and after oxidation were characterized in comparison by scanning electronic microscopy, transmission electronic microscopy and energy dispersion spectrometry. The results showed that a large proportion of cracks would be self-healed when the temperature increased to 1000 °C. At the places where the cracks have survived, the corresponding Zr substrate regions were oxidized to form semi-spherical or fan-shaped ZrO2. However, the maximum depth of ZrO2 under the unhealed cracks was smaller than that of the uncoated claddings at the same oxidation conditions.</description><subject>Accident tolerant fuel (ATF) cladding</subject><subject>Chromium coating</subject><subject>Claddings</subject><subject>Coatings</subject><subject>Cracks</subject><subject>Creep tests</subject><subject>Heat resistant alloys</subject><subject>High temperature</subject><subject>Internal pressure</subject><subject>Microscopy</subject><subject>Oxidation</subject><subject>Oxidation behavior</subject><subject>Oxidation process</subject><subject>Physical vapor deposition</subject><subject>Self-healing</subject><subject>Spectrometry</subject><subject>Steam</subject><subject>Substrates</subject><subject>Zirconium base alloys</subject><subject>Zirconium dioxide</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLxDAUhYMoOD5-ghBw3fEmadq6Ehl8geBC3biJt8mtk9JpxiQj-u_tMO5d3c13zuF-jJ0JmAsQ1UU_78eNXWGeS5BiLrRSst5jM9HUqigbCftsBiBloYTQh-wopR4A9CXoGXt_pqErloSDHz94S0v88iHy0PFFLGzATI6_RY7DEH64HdC5LedHvvQfS55ptaaIeROJp0y44uHbO8w-jHwdg6WUTthBh0Oi0797zF5vb14W98Xj093D4vqxsErVuShBl7q0FdQonaw6ibaDRkMrG4IWdUW1vUTZOKFq0bQanK11qbDC1uqOKnXMzne90-7nhlI2fdjEcZo0spKiaSpQMFF6R9kYUorUmXX0K4w_RoDZyjS9-ZNptjLNTuaUu9rlaHrhy1M0yXoaLTkfyWbjgv-n4RdgrYBa</recordid><startdate>202201</startdate><enddate>202201</enddate><creator>Ma, Hai-Bin</creator><creator>Zhao, Ya-Huan</creator><creator>Liu, Yang</creator><creator>Zhu, Jing-Ting</creator><creator>Yan, Jun</creator><creator>Liu, Tong</creator><creator>Ren, Qi-Sen</creator><creator>Liao, Ye-Hong</creator><creator>Liu, Gang</creator><creator>Lin, Xiao-Dong</creator><creator>Yao, Mei-Yi</creator><general>Elsevier B.V</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SR</scope><scope>7ST</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>SOI</scope></search><sort><creationdate>202201</creationdate><title>Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process</title><author>Ma, Hai-Bin ; Zhao, Ya-Huan ; Liu, Yang ; Zhu, Jing-Ting ; Yan, Jun ; Liu, Tong ; Ren, Qi-Sen ; Liao, Ye-Hong ; Liu, Gang ; Lin, Xiao-Dong ; Yao, Mei-Yi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c337t-405454c607a2d26f2acf0850b28e0ba56e7c9a28d13718b50dc7543a6abc5fe63</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>Accident tolerant fuel (ATF) cladding</topic><topic>Chromium coating</topic><topic>Claddings</topic><topic>Coatings</topic><topic>Cracks</topic><topic>Creep tests</topic><topic>Heat resistant alloys</topic><topic>High temperature</topic><topic>Internal pressure</topic><topic>Microscopy</topic><topic>Oxidation</topic><topic>Oxidation behavior</topic><topic>Oxidation process</topic><topic>Physical vapor deposition</topic><topic>Self-healing</topic><topic>Spectrometry</topic><topic>Steam</topic><topic>Substrates</topic><topic>Zirconium base alloys</topic><topic>Zirconium dioxide</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Ma, Hai-Bin</creatorcontrib><creatorcontrib>Zhao, Ya-Huan</creatorcontrib><creatorcontrib>Liu, Yang</creatorcontrib><creatorcontrib>Zhu, Jing-Ting</creatorcontrib><creatorcontrib>Yan, Jun</creatorcontrib><creatorcontrib>Liu, Tong</creatorcontrib><creatorcontrib>Ren, Qi-Sen</creatorcontrib><creatorcontrib>Liao, Ye-Hong</creatorcontrib><creatorcontrib>Liu, Gang</creatorcontrib><creatorcontrib>Lin, Xiao-Dong</creatorcontrib><creatorcontrib>Yao, Mei-Yi</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Ma, Hai-Bin</au><au>Zhao, Ya-Huan</au><au>Liu, Yang</au><au>Zhu, Jing-Ting</au><au>Yan, Jun</au><au>Liu, Tong</au><au>Ren, Qi-Sen</au><au>Liao, Ye-Hong</au><au>Liu, Gang</au><au>Lin, Xiao-Dong</au><au>Yao, Mei-Yi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process</atitle><jtitle>Journal of nuclear materials</jtitle><date>2022-01</date><risdate>2022</risdate><volume>558</volume><spage>153327</spage><pages>153327-</pages><artnum>153327</artnum><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>1Effect of cracks on the oxidation properties of Cr-coated Zr is investigated.2Microstructures of Cr-coated Zr with cracks during oxidation process are analyzed.3Cracks in Cr coatings are self-healed when the temperature increased to 1000 °C.4Cr coatings with cracks can still protect the substrate well in oxidation conditions.
Cr-coated Zr alloy claddings, prepared via physical vapor deposition (PVD), were used to study the damage evolution under a series of high-temperature steam oxidation conditions. Through-thickness cracks were initially produced within the Cr coat by internal pressure creep test. The Cr-coated samples with cracks were then oxidized at temperatures from 800 °C to 1200 °C in water steam environment. Microstructures of the samples before and after oxidation were characterized in comparison by scanning electronic microscopy, transmission electronic microscopy and energy dispersion spectrometry. The results showed that a large proportion of cracks would be self-healed when the temperature increased to 1000 °C. At the places where the cracks have survived, the corresponding Zr substrate regions were oxidized to form semi-spherical or fan-shaped ZrO2. However, the maximum depth of ZrO2 under the unhealed cracks was smaller than that of the uncoated claddings at the same oxidation conditions.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2021.153327</doi></addata></record> |
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subjects | Accident tolerant fuel (ATF) cladding Chromium coating Claddings Coatings Cracks Creep tests Heat resistant alloys High temperature Internal pressure Microscopy Oxidation Oxidation behavior Oxidation process Physical vapor deposition Self-healing Spectrometry Steam Substrates Zirconium base alloys Zirconium dioxide |
title | Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process |
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