Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR
An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5 × 10 22 and 5.2 × 10 22 m −3, and a bl...
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Veröffentlicht in: | Journal of nuclear materials 1999-06, Vol.273 (1), p.95-101 |
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creator | Hashimoto, N Wakai, E Robertson, J.P |
description | An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5
×
10
22 and 5.2
×
10
22 m
−3, and a black dot density of 2.2
×
10
23 and 1.1
×
10
23 m
−3, respectively, in the steel. A low density ( |
doi_str_mv | 10.1016/S0022-3115(99)00009-4 |
format | Article |
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×
10
22 and 5.2
×
10
22 m
−3, and a black dot density of 2.2
×
10
23 and 1.1
×
10
23 m
−3, respectively, in the steel. A low density (<1
×
10
19 m
−3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/S0022-3115(99)00009-4</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Installations for energy generation and conversion: thermal and electrical energy</subject><ispartof>Journal of nuclear materials, 1999-06, Vol.273 (1), p.95-101</ispartof><rights>1999 Elsevier Science B.V.</rights><rights>1999 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c433t-87b397a833cb9f6fb965a6496780a00aa59a740a6dd9b39cbbd0cd0414ff74fe3</citedby><cites>FETCH-LOGICAL-c433t-87b397a833cb9f6fb965a6496780a00aa59a740a6dd9b39cbbd0cd0414ff74fe3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/S0022-3115(99)00009-4$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=1791719$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Hashimoto, N</creatorcontrib><creatorcontrib>Wakai, E</creatorcontrib><creatorcontrib>Robertson, J.P</creatorcontrib><title>Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR</title><title>Journal of nuclear materials</title><description>An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5
×
10
22 and 5.2
×
10
22 m
−3, and a black dot density of 2.2
×
10
23 and 1.1
×
10
23 m
−3, respectively, in the steel. A low density (<1
×
10
19 m
−3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</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>1999</creationdate><recordtype>article</recordtype><recordid>eNqFkEFP3DAQha0KpC7Qn1DJhwrRQ6gdO3F8qhCCgrQqErRna2JPWFdZZ7EdUI_95_WytByZy4xG37yneYR85OyUM95-uWOsrivBeXOi9WdWSlfyHVnwTolKdjXbI4v_yHtykNKvwjSaNQvy5xZHyH4KaeU3tMf8hBjoCqLD4MM9heCogzXcI005zjbPEakPFOaUC5G9LXvwYcSUyoQ4UsHb5XfqYwTnIaOjkOk4PdGM6w1G-KeQV0ivLq9vj8j-AGPCDy_9kPy8vPhxflUtb75dn58tKyuFyFWneqEVdELYXg_t0Ou2gVbqVnUMGANoNCjJoHVOF9L2vWPWMcnlMCg5oDgkxzvdTZweZkzZrH2yOI4QcJqTqRVnNVO6gM0OtHFKKeJgNtGvIf42nJlt4OY5cLNN02htngM3stx9ejGAZGEcIgTr0-ux0lzxrfzXHYbl2UeP0STrMVh0PqLNxk3-DaO_UWuWXQ</recordid><startdate>19990601</startdate><enddate>19990601</enddate><creator>Hashimoto, N</creator><creator>Wakai, E</creator><creator>Robertson, J.P</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>8BQ</scope><scope>8FD</scope><scope>JG9</scope></search><sort><creationdate>19990601</creationdate><title>Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR</title><author>Hashimoto, N ; Wakai, E ; Robertson, J.P</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c433t-87b397a833cb9f6fb965a6496780a00aa59a740a6dd9b39cbbd0cd0414ff74fe3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1999</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Hashimoto, N</creatorcontrib><creatorcontrib>Wakai, E</creatorcontrib><creatorcontrib>Robertson, J.P</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>METADEX</collection><collection>Technology 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>Hashimoto, N</au><au>Wakai, E</au><au>Robertson, J.P</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR</atitle><jtitle>Journal of nuclear materials</jtitle><date>1999-06-01</date><risdate>1999</risdate><volume>273</volume><issue>1</issue><spage>95</spage><epage>101</epage><pages>95-101</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90°C and 250°C has been examined by transmission electron microscopy. The irradiation at 90°C and 250°C induced a dislocation loop density of 3.5
×
10
22 and 5.2
×
10
22 m
−3, and a black dot density of 2.2
×
10
23 and 1.1
×
10
23 m
−3, respectively, in the steel. A low density (<1
×
10
19 m
−3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/S0022-3115(99)00009-4</doi><tpages>7</tpages></addata></record> |
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source | Access via ScienceDirect (Elsevier) |
subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy |
title | Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR |
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