Corrosion of ferritic–martensitic steel HT9 in supercritical water
The oxidation of a 12% Cr ferritic–martensitic steel, HT9 has been examined after exposure to supercritical water (SCW) at 500 °C with two different dissolved oxygen contents, 25 wppb and 2 wppm, for exposure periods of up to 505 h. Samples exposed to the higher oxygen content SCW showed Cr-rich bla...
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| Veröffentlicht in: | Journal of nuclear materials 2006-11, Vol.358 (2), p.227-234 |
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| container_title | Journal of nuclear materials |
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| creator | Ren, X. Sridharan, K. Allen, T.R. |
| description | The oxidation of a 12% Cr ferritic–martensitic steel, HT9 has been examined after exposure to supercritical water (SCW) at 500
°C with two different dissolved oxygen contents, 25
wppb and 2
wppm, for exposure periods of up to 505
h. Samples exposed to the higher oxygen content SCW showed Cr-rich blades and generally a much finer oxide grain structure than samples exposed to the lower oxygen content SCW which have a porous surface oxide structure. A double-layer oxide structure developed on all samples exposed in 25
wppb oxygen content SCW, consisting specifically of an Fe-rich outer magnetite layer and a Cr-rich inner oxide layer composed of spinel and ferrite. An outer hematite layer was also found for samples exposed to 2
wppm oxygen content SCW. Samples whose surface was pre-implanted with oxygen and then exposed to SCW with 25
wppb oxygen content for 505
h showed a slightly lower weight gain compared to the untreated samples. This difference in weight gain appears to be associated with a preferred orientation in the outer oxide layer. |
| doi_str_mv | 10.1016/j.jnucmat.2006.07.010 |
| format | Article |
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°C with two different dissolved oxygen contents, 25
wppb and 2
wppm, for exposure periods of up to 505
h. Samples exposed to the higher oxygen content SCW showed Cr-rich blades and generally a much finer oxide grain structure than samples exposed to the lower oxygen content SCW which have a porous surface oxide structure. A double-layer oxide structure developed on all samples exposed in 25
wppb oxygen content SCW, consisting specifically of an Fe-rich outer magnetite layer and a Cr-rich inner oxide layer composed of spinel and ferrite. An outer hematite layer was also found for samples exposed to 2
wppm oxygen content SCW. Samples whose surface was pre-implanted with oxygen and then exposed to SCW with 25
wppb oxygen content for 505
h showed a slightly lower weight gain compared to the untreated samples. This difference in weight gain appears to be associated with a preferred orientation in the outer oxide layer.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2006.07.010</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Installations for energy generation and conversion: thermal and electrical energy</subject><ispartof>Journal of nuclear materials, 2006-11, Vol.358 (2), p.227-234</ispartof><rights>2006 Elsevier B.V.</rights><rights>2007 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c467t-80ff31da0b030a1248a09cebe2faf16ee7f2beb5ef1b72f3bb65866483602be23</citedby><cites>FETCH-LOGICAL-c467t-80ff31da0b030a1248a09cebe2faf16ee7f2beb5ef1b72f3bb65866483602be23</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311506004077$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27901,27902,65306</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=18236662$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Ren, X.</creatorcontrib><creatorcontrib>Sridharan, K.</creatorcontrib><creatorcontrib>Allen, T.R.</creatorcontrib><title>Corrosion of ferritic–martensitic steel HT9 in supercritical water</title><title>Journal of nuclear materials</title><description>The oxidation of a 12% Cr ferritic–martensitic steel, HT9 has been examined after exposure to supercritical water (SCW) at 500
°C with two different dissolved oxygen contents, 25
wppb and 2
wppm, for exposure periods of up to 505
h. Samples exposed to the higher oxygen content SCW showed Cr-rich blades and generally a much finer oxide grain structure than samples exposed to the lower oxygen content SCW which have a porous surface oxide structure. A double-layer oxide structure developed on all samples exposed in 25
wppb oxygen content SCW, consisting specifically of an Fe-rich outer magnetite layer and a Cr-rich inner oxide layer composed of spinel and ferrite. An outer hematite layer was also found for samples exposed to 2
wppm oxygen content SCW. Samples whose surface was pre-implanted with oxygen and then exposed to SCW with 25
wppb oxygen content for 505
h showed a slightly lower weight gain compared to the untreated samples. This difference in weight gain appears to be associated with a preferred orientation in the outer oxide layer.</description><subject>Applied sciences</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2006</creationdate><recordtype>article</recordtype><recordid>eNqFkE1OwzAQRi0EEqVwBKRsYJcwtmMnWSFUfopUiU1ZW447lhylSbFdEDvuwA05CUlbiSUra-Q38808Qi4pZBSovGmyptuatY4ZA5AZFBlQOCITWhY8zUsGx2QCwFjKKRWn5CyEBgBEBWJC7me9931wfZf0NrHovYvO_Hx9r7WP2IWxSkJEbJP5skpcl4TtBr3ZYbpNPnREf05OrG4DXhzeKXl9fFjO5uni5el5drdITS6LmJZgLacrDTVw0JTlpYbKYI3MakslYmFZjbVAS-uCWV7XUpRS5iWXMHwwPiXX-7kb379tMUS1dsFg2-oO-21QrBJQFRT-BwcbFRcjKPagGSQEj1ZtvBtO_1QU1ChXNeogV41yFRQKdgFXhwAdBg3W68648NdcMi6lHDe-3XM4aHl36FUwDjuDK-fRRLXq3T9Jv57Ak_E</recordid><startdate>20061130</startdate><enddate>20061130</enddate><creator>Ren, X.</creator><creator>Sridharan, K.</creator><creator>Allen, T.R.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7SE</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope></search><sort><creationdate>20061130</creationdate><title>Corrosion of ferritic–martensitic steel HT9 in supercritical water</title><author>Ren, X. ; Sridharan, K. ; Allen, T.R.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c467t-80ff31da0b030a1248a09cebe2faf16ee7f2beb5ef1b72f3bb65866483602be23</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2006</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>Installations for energy generation and conversion: thermal and electrical energy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Ren, X.</creatorcontrib><creatorcontrib>Sridharan, K.</creatorcontrib><creatorcontrib>Allen, T.R.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Corrosion Abstracts</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>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Ren, X.</au><au>Sridharan, K.</au><au>Allen, T.R.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Corrosion of ferritic–martensitic steel HT9 in supercritical water</atitle><jtitle>Journal of nuclear materials</jtitle><date>2006-11-30</date><risdate>2006</risdate><volume>358</volume><issue>2</issue><spage>227</spage><epage>234</epage><pages>227-234</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>The oxidation of a 12% Cr ferritic–martensitic steel, HT9 has been examined after exposure to supercritical water (SCW) at 500
°C with two different dissolved oxygen contents, 25
wppb and 2
wppm, for exposure periods of up to 505
h. Samples exposed to the higher oxygen content SCW showed Cr-rich blades and generally a much finer oxide grain structure than samples exposed to the lower oxygen content SCW which have a porous surface oxide structure. A double-layer oxide structure developed on all samples exposed in 25
wppb oxygen content SCW, consisting specifically of an Fe-rich outer magnetite layer and a Cr-rich inner oxide layer composed of spinel and ferrite. An outer hematite layer was also found for samples exposed to 2
wppm oxygen content SCW. Samples whose surface was pre-implanted with oxygen and then exposed to SCW with 25
wppb oxygen content for 505
h showed a slightly lower weight gain compared to the untreated samples. This difference in weight gain appears to be associated with a preferred orientation in the outer oxide layer.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2006.07.010</doi><tpages>8</tpages></addata></record> |
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| ispartof | Journal of nuclear materials, 2006-11, Vol.358 (2), p.227-234 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Applied sciences Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy |
| title | Corrosion of ferritic–martensitic steel HT9 in supercritical water |
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