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Ag transport in high temperature neutron irradiated 3C–SiC
The effect of high temperature neutron irradiation on the ability of a Pd–Ag mixture to penetrate 3C–SiC has been investigated. Previous work has revealed enhanced Ag transport in SiC in the presence of the fission product Pd. In this work it has been shown that high temperature neutron irradiation...
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Published in: | Journal of nuclear materials 2014-02, Vol.445 (1-3), p.20-25 |
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container_title | Journal of nuclear materials |
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creator | O’Connell, J.H. Neethling, J.H. |
description | The effect of high temperature neutron irradiation on the ability of a Pd–Ag mixture to penetrate 3C–SiC has been investigated. Previous work has revealed enhanced Ag transport in SiC in the presence of the fission product Pd. In this work it has been shown that high temperature neutron irradiation leads to enhanced transport of this Pd–Ag mixture as compared to unirradiated material and that both high irradiation temperature and high neutron fluence is required for significant transport enhancement. The results suggest that grain boundary type and misorientation is not significantly altered by high temperature neutron irradiation, suggesting that these characteristics play only a secondary role in Pd–Ag transport. |
doi_str_mv | 10.1016/j.jnucmat.2013.10.050 |
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Previous work has revealed enhanced Ag transport in SiC in the presence of the fission product Pd. In this work it has been shown that high temperature neutron irradiation leads to enhanced transport of this Pd–Ag mixture as compared to unirradiated material and that both high irradiation temperature and high neutron fluence is required for significant transport enhancement. The results suggest that grain boundary type and misorientation is not significantly altered by high temperature neutron irradiation, suggesting that these characteristics play only a secondary role in Pd–Ag transport.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2013.10.050</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Energy ; Energy. 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Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fluence</subject><subject>Grain boundaries</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Irradiation</subject><subject>Neutron irradiation</subject><subject>Nuclear engineering</subject><subject>Palladium</subject><subject>Silicon carbide</subject><subject>Silver</subject><subject>Transport</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><recordid>eNqFkc9KAzEQxoMoWKuPIOxF8LI1k2ySDQgixX8geFDPIc3Oakq7W5Os4M138A19ElNavPY0zPCb7xvmI-QU6AQoyIv5ZN4NbmnThFHgeTahgu6REdSKl1XN6D4ZUcpYyQHEITmKcU4pFZqKEbm8fitSsF1c9SEVvive_dt7kXC5wmDTELDocEih7wofgm28TdgUfPr7_fPsp8fkoLWLiCfbOiavtzcv0_vy8enuYXr9WLqK16kU0ragubaWQ80c10zpfE8LnDVu5qhDNWNSi5YrOaNcae5mqhW5k1XTOORjcr7RXYX-Y8CYzNJHh4uF7bAfooEaJAUmmdqNKl1VWoi63o0KqQBUFs2o2KAu9DEGbM0q-KUNXwaoWWdg5mabgVlnsB7nDPLe2dbCRmcXbX608_F_mdUgVCVF5q42HOYvfnoMJjqPncPGB3TJNL3f4fQHWfCd4A</recordid><startdate>20140201</startdate><enddate>20140201</enddate><creator>O’Connell, J.H.</creator><creator>Neethling, J.H.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>JG9</scope><scope>L7M</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7QQ</scope></search><sort><creationdate>20140201</creationdate><title>Ag transport in high temperature neutron irradiated 3C–SiC</title><author>O’Connell, J.H. ; Neethling, J.H.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c438t-56af1939aa3182c39279002f132dcbc0ce7b2695f376b03793cb7f537664ddce3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Applied sciences</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fluence</topic><topic>Grain boundaries</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Irradiation</topic><topic>Neutron irradiation</topic><topic>Nuclear engineering</topic><topic>Palladium</topic><topic>Silicon carbide</topic><topic>Silver</topic><topic>Transport</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>O’Connell, J.H.</creatorcontrib><creatorcontrib>Neethling, J.H.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Ceramic Abstracts</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>O’Connell, J.H.</au><au>Neethling, J.H.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Ag transport in high temperature neutron irradiated 3C–SiC</atitle><jtitle>Journal of nuclear materials</jtitle><date>2014-02-01</date><risdate>2014</risdate><volume>445</volume><issue>1-3</issue><spage>20</spage><epage>25</epage><pages>20-25</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>The effect of high temperature neutron irradiation on the ability of a Pd–Ag mixture to penetrate 3C–SiC has been investigated. 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subjects | Applied sciences Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fluence Grain boundaries Installations for energy generation and conversion: thermal and electrical energy Irradiation Neutron irradiation Nuclear engineering Palladium Silicon carbide Silver Transport |
title | Ag transport in high temperature neutron irradiated 3C–SiC |
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