Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments
Nuclear energy provides more than 10% of electrical power internationally and the increasing engagement of nuclear energy is essential to meet the rapid worldwide increase in energy demand. A paramount challenge in the development of advanced nuclear reactors is the discovery of advanced structural...
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| Veröffentlicht in: | Scientific reports 2015-01, Vol.5 (1), p.7801-7801, Article 7801 |
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| creator | Sun, C. Zheng, S. Wei, C. C. Wu, Y. Shao, L. Yang, Y. Hartwig, K. T. Maloy, S. A. Zinkle, S. J. Allen, T. R. Wang, H. Zhang, X. |
| description | Nuclear energy provides more than 10% of electrical power internationally and the increasing engagement of nuclear energy is essential to meet the rapid worldwide increase in energy demand. A paramount challenge in the development of advanced nuclear reactors is the discovery of advanced structural materials that can endure extreme environments, such as severe neutron irradiation damage at high temperatures. It has been known for decades that high dose radiation can introduce significant void swelling accompanied by precipitation in austenitic stainless steel (SS). Here we report, however, that through nanoengineering, ultra-fine grained (UFG) 304L SS with an average grain size of ~100 nm, can withstand Fe ion irradiation at 500°C to 80 displacements-per-atom (dpa) with moderate grain coarsening. Compared to coarse grained (CG) counterparts, swelling resistance of UFG SS is improved by nearly an order of magnitude and swelling rate is reduced by a factor of 5. M
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precipitates, abundant in irradiated CG SS, are largely absent in UFG SS. This study provides a nanoengineering approach to design and discover radiation tolerant metallic materials for applications in extreme radiation environments. |
| doi_str_mv | 10.1038/srep07801 |
| format | Article |
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precipitates, abundant in irradiated CG SS, are largely absent in UFG SS. This study provides a nanoengineering approach to design and discover radiation tolerant metallic materials for applications in extreme radiation environments.</description><identifier>ISSN: 2045-2322</identifier><identifier>EISSN: 2045-2322</identifier><identifier>DOI: 10.1038/srep07801</identifier><identifier>PMID: 25588326</identifier><language>eng</language><publisher>London: Nature Publishing Group UK</publisher><subject>147/143 ; 147/28 ; 639/166 ; 639/301 ; Alloys ; Electric power ; Energy demand ; High temperature ; Humanities and Social Sciences ; Irradiation ; multidisciplinary ; Nuclear energy ; Nuclear reactors ; Science ; Stainless steel</subject><ispartof>Scientific reports, 2015-01, Vol.5 (1), p.7801-7801, Article 7801</ispartof><rights>The Author(s) 2015</rights><rights>Copyright Nature Publishing Group Jan 2015</rights><rights>Copyright © 2015, Macmillan Publishers Limited. All rights reserved 2015 Macmillan Publishers Limited. All rights reserved</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c504t-c53bf4438252cee9ccb0e7131662de9eb6187d174fea62c2f8db27b22fcabfad3</citedby><cites>FETCH-LOGICAL-c504t-c53bf4438252cee9ccb0e7131662de9eb6187d174fea62c2f8db27b22fcabfad3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.ncbi.nlm.nih.gov/pmc/articles/PMC4295098/pdf/$$EPDF$$P50$$Gpubmedcentral$$Hfree_for_read</linktopdf><linktohtml>$$Uhttps://www.ncbi.nlm.nih.gov/pmc/articles/PMC4295098/$$EHTML$$P50$$Gpubmedcentral$$Hfree_for_read</linktohtml><link.rule.ids>230,315,729,782,786,866,887,27931,27932,41127,42196,51583,53798,53800</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/25588326$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Sun, C.</creatorcontrib><creatorcontrib>Zheng, S.</creatorcontrib><creatorcontrib>Wei, C. C.</creatorcontrib><creatorcontrib>Wu, Y.</creatorcontrib><creatorcontrib>Shao, L.</creatorcontrib><creatorcontrib>Yang, Y.</creatorcontrib><creatorcontrib>Hartwig, K. T.</creatorcontrib><creatorcontrib>Maloy, S. A.</creatorcontrib><creatorcontrib>Zinkle, S. J.</creatorcontrib><creatorcontrib>Allen, T. R.</creatorcontrib><creatorcontrib>Wang, H.</creatorcontrib><creatorcontrib>Zhang, X.</creatorcontrib><title>Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments</title><title>Scientific reports</title><addtitle>Sci Rep</addtitle><addtitle>Sci Rep</addtitle><description>Nuclear energy provides more than 10% of electrical power internationally and the increasing engagement of nuclear energy is essential to meet the rapid worldwide increase in energy demand. A paramount challenge in the development of advanced nuclear reactors is the discovery of advanced structural materials that can endure extreme environments, such as severe neutron irradiation damage at high temperatures. It has been known for decades that high dose radiation can introduce significant void swelling accompanied by precipitation in austenitic stainless steel (SS). Here we report, however, that through nanoengineering, ultra-fine grained (UFG) 304L SS with an average grain size of ~100 nm, can withstand Fe ion irradiation at 500°C to 80 displacements-per-atom (dpa) with moderate grain coarsening. Compared to coarse grained (CG) counterparts, swelling resistance of UFG SS is improved by nearly an order of magnitude and swelling rate is reduced by a factor of 5. M
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precipitates, abundant in irradiated CG SS, are largely absent in UFG SS. This study provides a nanoengineering approach to design and discover radiation tolerant metallic materials for applications in extreme radiation environments.</description><subject>147/143</subject><subject>147/28</subject><subject>639/166</subject><subject>639/301</subject><subject>Alloys</subject><subject>Electric power</subject><subject>Energy demand</subject><subject>High temperature</subject><subject>Humanities and Social Sciences</subject><subject>Irradiation</subject><subject>multidisciplinary</subject><subject>Nuclear energy</subject><subject>Nuclear reactors</subject><subject>Science</subject><subject>Stainless steel</subject><issn>2045-2322</issn><issn>2045-2322</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2015</creationdate><recordtype>article</recordtype><sourceid>C6C</sourceid><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GNUQQ</sourceid><recordid>eNplkU1LHTEUhoO0qFgX_gEJdFMLtyYn85HZCCJaCxe6qK5DJnPmNjKTjElGdNPfbuy119s2i-TAeXjOCS8hR5x94UzI0xhwYrVkfIfsAyvKBQiAd1v1HjmM8Y7lU0JT8GaX7EFZSimg2ie_fswTBusDDbqzOlnvFgGjjUm7RJ12Ht3KOsSAHdVzTOhssoYKVixphqwbMMZcIQ60zxo9TYM1v0WRWkfxMQUc8U1P0T3Y4N2ILsUP5H2vh4iHr-8Bub26vLm4Xiy_f_12cb5cmJIVKd-i7YtCSCjBIDbGtAxrLnhVQYcNthWXdcfrokddgYFedi3ULUBvdNvrThyQs7V3mtsRO5NnBz2oKdhRhyfltVV_d5z9qVb-QRXQlKyRWfDpVRD8_YwxqdFGg8OgHfo5Kl6VIHIKIDL68R_0zs_B5e8pLhvJWZO3ztTJmjLBx5xhv1mGM_USrNoEm9nj7e035J8YM_B5DcTccisMWyP_sz0DXtqxbA</recordid><startdate>20150115</startdate><enddate>20150115</enddate><creator>Sun, C.</creator><creator>Zheng, S.</creator><creator>Wei, C. 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C. ; Wu, Y. ; Shao, L. ; Yang, Y. ; Hartwig, K. T. ; Maloy, S. A. ; Zinkle, S. J. ; Allen, T. R. ; Wang, H. ; Zhang, X.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c504t-c53bf4438252cee9ccb0e7131662de9eb6187d174fea62c2f8db27b22fcabfad3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2015</creationdate><topic>147/143</topic><topic>147/28</topic><topic>639/166</topic><topic>639/301</topic><topic>Alloys</topic><topic>Electric power</topic><topic>Energy demand</topic><topic>High temperature</topic><topic>Humanities and Social Sciences</topic><topic>Irradiation</topic><topic>multidisciplinary</topic><topic>Nuclear energy</topic><topic>Nuclear reactors</topic><topic>Science</topic><topic>Stainless steel</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Sun, C.</creatorcontrib><creatorcontrib>Zheng, S.</creatorcontrib><creatorcontrib>Wei, C. 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C.</au><au>Wu, Y.</au><au>Shao, L.</au><au>Yang, Y.</au><au>Hartwig, K. T.</au><au>Maloy, S. A.</au><au>Zinkle, S. J.</au><au>Allen, T. R.</au><au>Wang, H.</au><au>Zhang, X.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments</atitle><jtitle>Scientific reports</jtitle><stitle>Sci Rep</stitle><addtitle>Sci Rep</addtitle><date>2015-01-15</date><risdate>2015</risdate><volume>5</volume><issue>1</issue><spage>7801</spage><epage>7801</epage><pages>7801-7801</pages><artnum>7801</artnum><issn>2045-2322</issn><eissn>2045-2322</eissn><abstract>Nuclear energy provides more than 10% of electrical power internationally and the increasing engagement of nuclear energy is essential to meet the rapid worldwide increase in energy demand. A paramount challenge in the development of advanced nuclear reactors is the discovery of advanced structural materials that can endure extreme environments, such as severe neutron irradiation damage at high temperatures. It has been known for decades that high dose radiation can introduce significant void swelling accompanied by precipitation in austenitic stainless steel (SS). Here we report, however, that through nanoengineering, ultra-fine grained (UFG) 304L SS with an average grain size of ~100 nm, can withstand Fe ion irradiation at 500°C to 80 displacements-per-atom (dpa) with moderate grain coarsening. Compared to coarse grained (CG) counterparts, swelling resistance of UFG SS is improved by nearly an order of magnitude and swelling rate is reduced by a factor of 5. M
23
C
6
precipitates, abundant in irradiated CG SS, are largely absent in UFG SS. This study provides a nanoengineering approach to design and discover radiation tolerant metallic materials for applications in extreme radiation environments.</abstract><cop>London</cop><pub>Nature Publishing Group UK</pub><pmid>25588326</pmid><doi>10.1038/srep07801</doi><tpages>1</tpages><oa>free_for_read</oa></addata></record> |
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| subjects | 147/143 147/28 639/166 639/301 Alloys Electric power Energy demand High temperature Humanities and Social Sciences Irradiation multidisciplinary Nuclear energy Nuclear reactors Science Stainless steel |
| title | Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments |
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