Corrosion behaviour of aluminized martensitic and austenitic steels in liquid Pb–Bi
The Pb–Bi liquid alloy is under consideration as a spallation target material in the hybrid systems due to its suitable nuclear and physical properties. In order to limit the risks of corrosion of the structural elements in contact with the liquid Pb–Bi, protection by means of aluminized coatings wa...
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| Veröffentlicht in: | Journal of nuclear materials 2004-11, Vol.335 (2), p.180-184 |
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| container_title | Journal of nuclear materials |
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| creator | Deloffre, Ph Balbaud-Célérier, F. Terlain, A. |
| description | The Pb–Bi liquid alloy is under consideration as a spallation target material in the hybrid systems due to its suitable nuclear and physical properties. In order to limit the risks of corrosion of the structural elements in contact with the liquid Pb–Bi, protection by means of aluminized coatings was investigated for 316L austenitic steel and T91 martensitic steel. For both steels, no damages were observed after immersions in static Pb–Bi up to 500 °C for low oxygen concentrations and long durations. However, at 600 °C in the same conditions, a non-uniform degradation of the coatings was observed. Only coated 316L was tested in dynamic conditions. The results were generally satisfying for temperatures from 350 to 600 °C and for fluid velocities up to 2.3 m
s
−1. However, in both the IPPE loops and the CICLAD device, some localized damage of the coatings, attributed to erosion, was observed. |
| doi_str_mv | 10.1016/j.jnucmat.2004.07.014 |
| format | Article |
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s
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s
−1. However, in both the IPPE loops and the CICLAD device, some localized damage of the coatings, attributed to erosion, was observed.</description><subject>Applied sciences</subject><subject>C0700</subject><subject>C0900</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>L0300</subject><subject>Nuclear fuels</subject><subject>S0600</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2004</creationdate><recordtype>article</recordtype><recordid>eNqFkM1KxDAUhYMoOP48gpCN7lqTtGmalejgHwi6GNchzQ_eoZNq0gq68h18Q5_E6Ay4dHXvgXPu5XwIHVFSUkKb02W5DJNZ6bFkhNQlESWh9Raa0VZURd0yso1mhDBWVJTyXbSX0pIQwiXhM_Q4H2IcEgwBd-5Jv8IwRTx4rPtpBQHencUrHUcXEoxgsA4W6yll_Svz4vqEIeAeXiaw-KH7-vi8gAO043Wf3OFm7qPF1eViflPc3V_fzs_vClM17VjYRtTWV77qtPSG085y30phvKyN5VZSoUVnmkYK1jDGubd1W3WyptIQ0_FqH52szz7H4WVyaVQrSMb1vQ5umJJiLaWyYW028rXR5K4pOq-eI-Reb4oS9cNQLdWGofphqIhQmWHOHW8e6GR076MOBtJfuGE151Jk39nal2m4V3BRJQMuGGchOjMqO8A_n74BsNmMkw</recordid><startdate>20041101</startdate><enddate>20041101</enddate><creator>Deloffre, Ph</creator><creator>Balbaud-Célérier, F.</creator><creator>Terlain, A.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7QF</scope><scope>7SE</scope><scope>7TB</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope></search><sort><creationdate>20041101</creationdate><title>Corrosion behaviour of aluminized martensitic and austenitic steels in liquid Pb–Bi</title><author>Deloffre, Ph ; Balbaud-Célérier, F. ; Terlain, A.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c368t-d674df3f3ba9fc51bd5f897cf94cd5d917a7bc6697262255fd483b9419c0cb53</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2004</creationdate><topic>Applied sciences</topic><topic>C0700</topic><topic>C0900</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>L0300</topic><topic>Nuclear fuels</topic><topic>S0600</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Deloffre, Ph</creatorcontrib><creatorcontrib>Balbaud-Célérier, F.</creatorcontrib><creatorcontrib>Terlain, A.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Aluminium Industry Abstracts</collection><collection>Corrosion Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Deloffre, Ph</au><au>Balbaud-Célérier, F.</au><au>Terlain, A.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Corrosion behaviour of aluminized martensitic and austenitic steels in liquid Pb–Bi</atitle><jtitle>Journal of nuclear materials</jtitle><date>2004-11-01</date><risdate>2004</risdate><volume>335</volume><issue>2</issue><spage>180</spage><epage>184</epage><pages>180-184</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>The Pb–Bi liquid alloy is under consideration as a spallation target material in the hybrid systems due to its suitable nuclear and physical properties. In order to limit the risks of corrosion of the structural elements in contact with the liquid Pb–Bi, protection by means of aluminized coatings was investigated for 316L austenitic steel and T91 martensitic steel. For both steels, no damages were observed after immersions in static Pb–Bi up to 500 °C for low oxygen concentrations and long durations. However, at 600 °C in the same conditions, a non-uniform degradation of the coatings was observed. Only coated 316L was tested in dynamic conditions. The results were generally satisfying for temperatures from 350 to 600 °C and for fluid velocities up to 2.3 m
s
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| ispartof | Journal of nuclear materials, 2004-11, Vol.335 (2), p.180-184 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Applied sciences C0700 C0900 Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy L0300 Nuclear fuels S0600 |
| title | Corrosion behaviour of aluminized martensitic and austenitic steels in liquid Pb–Bi |
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