Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions
AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radia...
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| Veröffentlicht in: | Acta metallurgica sinica : English letters 2017, Vol.30 (1), p.89-96 |
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| creator | Zheng, Zhong-Cheng Yu, Yan-Xia Zhang, Wei-Ping Shen, Zhen-Yu Luo, Feng-Feng Guo, Li-Ping Ren, Yao-Yao Tang, Rui |
| description | AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops. |
| doi_str_mv | 10.1007/s40195-016-0490-2 |
| format | Article |
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Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.</description><identifier>ISSN: 1006-7191</identifier><identifier>EISSN: 2194-1289</identifier><identifier>DOI: 10.1007/s40195-016-0490-2</identifier><language>eng</language><publisher>Beijing: The Chinese Society for Metals</publisher><subject>Austenitic stainless steels ; Burgers vector ; Characterization and Evaluation of Materials ; Chemistry and Materials Science ; Corrosion and Coatings ; Corrosion resistance ; Dislocation loops ; Evolution ; High temperature ; Hydrogen ; Hydrogen ions ; Investigations ; Materials Science ; Metallic Materials ; Microstructure ; Nanotechnology ; Nucleation ; Organometallic Chemistry ; Point defects ; Radiation ; Radiation effects ; Spectroscopy/Spectrometry ; Stainless steel ; Tribology</subject><ispartof>Acta metallurgica sinica : English letters, 2017, Vol.30 (1), p.89-96</ispartof><rights>The Chinese Society for Metals and Springer-Verlag Berlin Heidelberg 2016</rights><rights>The Chinese Society for Metals and Springer-Verlag Berlin Heidelberg 2016.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c386t-4837d2710ca56a6e5e06dc72b7929397fdd2d7f4bbc887a4705802f5231584583</citedby><cites>FETCH-LOGICAL-c386t-4837d2710ca56a6e5e06dc72b7929397fdd2d7f4bbc887a4705802f5231584583</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Uhttp://image.cqvip.com/vip1000/qk/86672X/86672X.jpg</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s40195-016-0490-2$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://www.proquest.com/docview/2932745581?pq-origsite=primo$$EHTML$$P50$$Gproquest$$H</linktohtml><link.rule.ids>314,780,784,4024,21388,27923,27924,27925,33744,41488,42557,43805,51319,64385,64389,72469</link.rule.ids></links><search><creatorcontrib>Zheng, Zhong-Cheng</creatorcontrib><creatorcontrib>Yu, Yan-Xia</creatorcontrib><creatorcontrib>Zhang, Wei-Ping</creatorcontrib><creatorcontrib>Shen, Zhen-Yu</creatorcontrib><creatorcontrib>Luo, Feng-Feng</creatorcontrib><creatorcontrib>Guo, Li-Ping</creatorcontrib><creatorcontrib>Ren, Yao-Yao</creatorcontrib><creatorcontrib>Tang, Rui</creatorcontrib><title>Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions</title><title>Acta metallurgica sinica : English letters</title><addtitle>Acta Metall. Sin. (Engl. Lett.)</addtitle><addtitle>Acta Metallurgica Sinica（English Letters）</addtitle><description>AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.</description><subject>Austenitic stainless steels</subject><subject>Burgers vector</subject><subject>Characterization and Evaluation of Materials</subject><subject>Chemistry and Materials Science</subject><subject>Corrosion and Coatings</subject><subject>Corrosion resistance</subject><subject>Dislocation loops</subject><subject>Evolution</subject><subject>High temperature</subject><subject>Hydrogen</subject><subject>Hydrogen ions</subject><subject>Investigations</subject><subject>Materials Science</subject><subject>Metallic Materials</subject><subject>Microstructure</subject><subject>Nanotechnology</subject><subject>Nucleation</subject><subject>Organometallic Chemistry</subject><subject>Point defects</subject><subject>Radiation</subject><subject>Radiation effects</subject><subject>Spectroscopy/Spectrometry</subject><subject>Stainless steel</subject><subject>Tribology</subject><issn>1006-7191</issn><issn>2194-1289</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2017</creationdate><recordtype>article</recordtype><sourceid>AFKRA</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><recordid>eNp9kE1LAzEYhIMoWKs_wFvQ82qSzedR6kcLRQ9a8Baym2zdsiZtshX6703dojdP7zvwzAwMAJcY3WCExG2iCCtWIMwLRBUqyBEYEaxogYlUx2CUIV4IrPApOEtplRWhTIzA4uErdNu-DR6GBt63qQu1-ZHzENYJth7ezQv-_gxfe9P6zqWUP-e6BGcxGtua3llY7eB0Z2NYOg9nwadzcNKYLrmLwx2DxePD22RazF-eZpMcWJeS9wWVpbBEYFQbxg13zCFua0EqoYgqlWisJVY0tKpqKYWhAjGJSMNIiZmkTJZjcD3krmPYbF3q9Spso8-VOgcQQRmTOFN4oOoYUoqu0evYfpq40xjp_Xp6WE_n9fR-PU2yhwyelFm_dPEv-T_T1aHoI_jlJvt-m7jAlCFMUPkN4Rt7iA</recordid><startdate>2017</startdate><enddate>2017</enddate><creator>Zheng, Zhong-Cheng</creator><creator>Yu, Yan-Xia</creator><creator>Zhang, Wei-Ping</creator><creator>Shen, Zhen-Yu</creator><creator>Luo, Feng-Feng</creator><creator>Guo, Li-Ping</creator><creator>Ren, Yao-Yao</creator><creator>Tang, Rui</creator><general>The Chinese Society for Metals</general><general>Springer Nature B.V</general><scope>2RA</scope><scope>92L</scope><scope>CQIGP</scope><scope>W92</scope><scope>~WA</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>8FE</scope><scope>8FG</scope><scope>ABJCF</scope><scope>AFKRA</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>D1I</scope><scope>DWQXO</scope><scope>HCIFZ</scope><scope>KB.</scope><scope>PDBOC</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope></search><sort><creationdate>2017</creationdate><title>Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions</title><author>Zheng, Zhong-Cheng ; Yu, Yan-Xia ; Zhang, Wei-Ping ; Shen, Zhen-Yu ; Luo, Feng-Feng ; Guo, Li-Ping ; Ren, Yao-Yao ; Tang, Rui</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c386t-4837d2710ca56a6e5e06dc72b7929397fdd2d7f4bbc887a4705802f5231584583</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2017</creationdate><topic>Austenitic stainless steels</topic><topic>Burgers vector</topic><topic>Characterization and Evaluation of Materials</topic><topic>Chemistry and Materials Science</topic><topic>Corrosion and Coatings</topic><topic>Corrosion resistance</topic><topic>Dislocation loops</topic><topic>Evolution</topic><topic>High temperature</topic><topic>Hydrogen</topic><topic>Hydrogen ions</topic><topic>Investigations</topic><topic>Materials Science</topic><topic>Metallic Materials</topic><topic>Microstructure</topic><topic>Nanotechnology</topic><topic>Nucleation</topic><topic>Organometallic Chemistry</topic><topic>Point defects</topic><topic>Radiation</topic><topic>Radiation effects</topic><topic>Spectroscopy/Spectrometry</topic><topic>Stainless steel</topic><topic>Tribology</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Zheng, Zhong-Cheng</creatorcontrib><creatorcontrib>Yu, Yan-Xia</creatorcontrib><creatorcontrib>Zhang, Wei-Ping</creatorcontrib><creatorcontrib>Shen, Zhen-Yu</creatorcontrib><creatorcontrib>Luo, Feng-Feng</creatorcontrib><creatorcontrib>Guo, Li-Ping</creatorcontrib><creatorcontrib>Ren, Yao-Yao</creatorcontrib><creatorcontrib>Tang, Rui</creatorcontrib><collection>中文科技期刊数据库</collection><collection>中文科技期刊数据库-CALIS站点</collection><collection>中文科技期刊数据库-7.0平台</collection><collection>中文科技期刊数据库-工程技术</collection><collection>中文科技期刊数据库- 镜像站点</collection><collection>CrossRef</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central UK/Ireland</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 Science Database</collection><collection>Materials Science Collection</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><jtitle>Acta metallurgica sinica : English letters</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Zheng, Zhong-Cheng</au><au>Yu, Yan-Xia</au><au>Zhang, Wei-Ping</au><au>Shen, Zhen-Yu</au><au>Luo, Feng-Feng</au><au>Guo, Li-Ping</au><au>Ren, Yao-Yao</au><au>Tang, Rui</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions</atitle><jtitle>Acta metallurgica sinica : English letters</jtitle><stitle>Acta Metall. Sin. (Engl. Lett.)</stitle><addtitle>Acta Metallurgica Sinica（English Letters）</addtitle><date>2017</date><risdate>2017</risdate><volume>30</volume><issue>1</issue><spage>89</spage><epage>96</epage><pages>89-96</pages><issn>1006-7191</issn><eissn>2194-1289</eissn><abstract>AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2＋ ions at 290 and 380 ℃. Microstructures were characterized by transmission electron microscopy （TEM）. Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 〈111〉 type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 ℃. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. 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| subjects | Austenitic stainless steels Burgers vector Characterization and Evaluation of Materials Chemistry and Materials Science Corrosion and Coatings Corrosion resistance Dislocation loops Evolution High temperature Hydrogen Hydrogen ions Investigations Materials Science Metallic Materials Microstructure Nanotechnology Nucleation Organometallic Chemistry Point defects Radiation Radiation effects Spectroscopy/Spectrometry Stainless steel Tribology |
| title | Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions |
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