In-situ Fe + Ion Irradiation of an Oxide Dispersion Strengthened Steel
Oxide Dispersion Strengthened (ODS) reduced activation ferritic steels are promising candidate materials for structural components of both nuclear fission and fusion reactors. However, when irradiated with energetic particles, they may suffer changes on their microstructures that degrade their mecha...
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Veröffentlicht in: | Journal of physics. Conference series 2014-06, Vol.522 (1), p.12032 |
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creator | de Castro, V Briceno, M Jenkins, M L Kirk, M Lozano-Perez, S Roberts, S G |
description | Oxide Dispersion Strengthened (ODS) reduced activation ferritic steels are promising candidate materials for structural components of both nuclear fission and fusion reactors. However, when irradiated with energetic particles, they may suffer changes on their microstructures that degrade their mechanical performance. In-situ transmission electron microscopy studies on ion-irradiated ODS steels can give remarkable insights into fundamental aspects of radiation damage allowing dynamic observations of defect formation, mobilities, and interactions during irradiation. In this investigation, a commercially available PM2000 ODS steel was in-situ irradiated with 150 KeV Fe+ at room temperature and 700°C. These experiments showed that the oxide nanoparticles in these steels remain stable up to the higher irradiation dose (~ 1.5 dpa), and that these particles seem to be effective sinks for irradiation induced defects. |
doi_str_mv | 10.1088/1742-6596/522/1/012032 |
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However, when irradiated with energetic particles, they may suffer changes on their microstructures that degrade their mechanical performance. In-situ transmission electron microscopy studies on ion-irradiated ODS steels can give remarkable insights into fundamental aspects of radiation damage allowing dynamic observations of defect formation, mobilities, and interactions during irradiation. In this investigation, a commercially available PM2000 ODS steel was in-situ irradiated with 150 KeV Fe+ at room temperature and 700°C. These experiments showed that the oxide nanoparticles in these steels remain stable up to the higher irradiation dose (~ 1.5 dpa), and that these particles seem to be effective sinks for irradiation induced defects.</description><identifier>ISSN: 1742-6588</identifier><identifier>EISSN: 1742-6596</identifier><identifier>DOI: 10.1088/1742-6596/522/1/012032</identifier><language>eng</language><publisher>Bristol: IOP Publishing</publisher><subject>Dispersion hardening steels ; Energetic particles ; Ferritic stainless steels ; Fusion reactors ; Ion irradiation ; Materials selection ; Mechanical properties ; Nanoparticles ; Nuclear fission ; Nuclear fusion ; Nuclear reactor components ; Nuclear reactors ; Oxide dispersion strengthening ; Physics ; Radiation damage ; Radiation dosage ; Room temperature</subject><ispartof>Journal of physics. Conference series, 2014-06, Vol.522 (1), p.12032</ispartof><rights>2014. 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These experiments showed that the oxide nanoparticles in these steels remain stable up to the higher irradiation dose (~ 1.5 dpa), and that these particles seem to be effective sinks for irradiation induced defects.</description><subject>Dispersion hardening steels</subject><subject>Energetic particles</subject><subject>Ferritic stainless steels</subject><subject>Fusion reactors</subject><subject>Ion irradiation</subject><subject>Materials selection</subject><subject>Mechanical properties</subject><subject>Nanoparticles</subject><subject>Nuclear fission</subject><subject>Nuclear fusion</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Oxide dispersion strengthening</subject><subject>Physics</subject><subject>Radiation damage</subject><subject>Radiation dosage</subject><subject>Room temperature</subject><issn>1742-6588</issn><issn>1742-6596</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><recordid>eNo9kE9LAzEQxYMoWKtfQQIeZd1Msvl3lGp1odCDeg7ZbKJb6m5NtqDfvlkqncu8mfeYgR9Ct0AegChVgqxoIbgWJae0hJIAJYyeodnJOD9ppS7RVUobQlguOUPLui9SN-7x0uN7XA89rmO0bWfHLushYNvj9W_XevzUpZ2PaVq_jdH3n-OX732bB--31-gi2G3yN_99jj6Wz--L12K1fqkXj6vCMS3HwjoOQANrqyBk45vgGk2q1ipRCS4l4Y0WlQLXBgpMcwmu4VBpAsKR7AKbo7vj3V0cfvY-jWYz7GOfXxrKpRCKac1zShxTLg4pRR_MLnbfNv4ZIGZiZiYcZkJjMjMD5siMHQAo8lzF</recordid><startdate>20140611</startdate><enddate>20140611</enddate><creator>de Castro, V</creator><creator>Briceno, M</creator><creator>Jenkins, M L</creator><creator>Kirk, M</creator><creator>Lozano-Perez, S</creator><creator>Roberts, S G</creator><general>IOP Publishing</general><scope>AAYXX</scope><scope>CITATION</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>ARAPS</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>H8D</scope><scope>HCIFZ</scope><scope>L7M</scope><scope>P5Z</scope><scope>P62</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PRINS</scope></search><sort><creationdate>20140611</creationdate><title>In-situ Fe + Ion Irradiation of an Oxide Dispersion Strengthened Steel</title><author>de Castro, V ; Briceno, M ; Jenkins, M L ; Kirk, M ; Lozano-Perez, S ; Roberts, S G</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c397t-ac5112f3d4f67bebfcb904da864657705b96481cdf2139571cb5149016c070513</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Dispersion hardening steels</topic><topic>Energetic particles</topic><topic>Ferritic stainless steels</topic><topic>Fusion reactors</topic><topic>Ion irradiation</topic><topic>Materials selection</topic><topic>Mechanical properties</topic><topic>Nanoparticles</topic><topic>Nuclear fission</topic><topic>Nuclear fusion</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Oxide dispersion strengthening</topic><topic>Physics</topic><topic>Radiation damage</topic><topic>Radiation dosage</topic><topic>Room temperature</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>de Castro, V</creatorcontrib><creatorcontrib>Briceno, M</creatorcontrib><creatorcontrib>Jenkins, M L</creatorcontrib><creatorcontrib>Kirk, M</creatorcontrib><creatorcontrib>Lozano-Perez, S</creatorcontrib><creatorcontrib>Roberts, S G</creatorcontrib><collection>CrossRef</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>ProQuest Central (Alumni Edition)</collection><collection>ProQuest Central UK/Ireland</collection><collection>Advanced Technologies & Aerospace Collection</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>Aerospace Database</collection><collection>SciTech Premium Collection</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Advanced Technologies & Aerospace Database</collection><collection>ProQuest Advanced Technologies & Aerospace Collection</collection><collection>Access via ProQuest (Open Access)</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>Journal of physics. Conference series</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>de Castro, V</au><au>Briceno, M</au><au>Jenkins, M L</au><au>Kirk, M</au><au>Lozano-Perez, S</au><au>Roberts, S G</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>In-situ Fe + Ion Irradiation of an Oxide Dispersion Strengthened Steel</atitle><jtitle>Journal of physics. Conference series</jtitle><date>2014-06-11</date><risdate>2014</risdate><volume>522</volume><issue>1</issue><spage>12032</spage><pages>12032-</pages><issn>1742-6588</issn><eissn>1742-6596</eissn><abstract>Oxide Dispersion Strengthened (ODS) reduced activation ferritic steels are promising candidate materials for structural components of both nuclear fission and fusion reactors. However, when irradiated with energetic particles, they may suffer changes on their microstructures that degrade their mechanical performance. In-situ transmission electron microscopy studies on ion-irradiated ODS steels can give remarkable insights into fundamental aspects of radiation damage allowing dynamic observations of defect formation, mobilities, and interactions during irradiation. In this investigation, a commercially available PM2000 ODS steel was in-situ irradiated with 150 KeV Fe+ at room temperature and 700°C. These experiments showed that the oxide nanoparticles in these steels remain stable up to the higher irradiation dose (~ 1.5 dpa), and that these particles seem to be effective sinks for irradiation induced defects.</abstract><cop>Bristol</cop><pub>IOP Publishing</pub><doi>10.1088/1742-6596/522/1/012032</doi><oa>free_for_read</oa></addata></record> |
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subjects | Dispersion hardening steels Energetic particles Ferritic stainless steels Fusion reactors Ion irradiation Materials selection Mechanical properties Nanoparticles Nuclear fission Nuclear fusion Nuclear reactor components Nuclear reactors Oxide dispersion strengthening Physics Radiation damage Radiation dosage Room temperature |
title | In-situ Fe + Ion Irradiation of an Oxide Dispersion Strengthened Steel |
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