Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II
Three 37-pin MOX-fueled experimental subassemblies were irradiated in EBR-II with fuel pin cladding constructed from annealed AISI 304 stainless steel. Analysis of the swelling and irradiation creep of the cladding showed that the terminal swelling rate of AISI 304 stainless steel appears to be ∼1%/...
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| Veröffentlicht in: | Journal of nuclear materials 2011-06, Vol.413 (1), p.53-61 |
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| creator | Garner, F.A. Makenas, B.J. Chastain, S.A. |
| description | Three 37-pin MOX-fueled experimental subassemblies were irradiated in EBR-II with fuel pin cladding constructed from annealed AISI 304 stainless steel. Analysis of the swelling and irradiation creep of the cladding showed that the terminal swelling rate of AISI 304 stainless steel appears to be ∼1%/dpa and that swelling is very reproducible for identical irradiation conditions. The swelling at a given neutron fluence is rather sensitive to both irradiation temperature and especially to the neutron flux, however, with the primary influence residing in the transient regime. As the neutron flux increases the duration of the transient regime is increased in agreement with other recent studies. The duration of the transient regime is also decreased by increasing irradiation temperature.
In these assemblies swelling reached high levels rather quickly, reducing the opportunity for fuel pin cladding interaction and thereby reducing the contribution of irradiation creep to the total deformation. It also appears that in this swelling-before-creep scenario that the well-known “creep disappearance” phenomenon was operating strongly. |
| doi_str_mv | 10.1016/j.jnucmat.2011.03.055 |
| format | Article |
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In these assemblies swelling reached high levels rather quickly, reducing the opportunity for fuel pin cladding interaction and thereby reducing the contribution of irradiation creep to the total deformation. It also appears that in this swelling-before-creep scenario that the well-known “creep disappearance” phenomenon was operating strongly.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2011.03.055</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 ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear fuels</subject><ispartof>Journal of nuclear materials, 2011-06, Vol.413 (1), p.53-61</ispartof><rights>2011 Elsevier B.V.</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c437t-f4e58194534164dc6c012f79a34113d5e89dc5990ee6b793151fcbe87f039eb3</citedby><cites>FETCH-LOGICAL-c437t-f4e58194534164dc6c012f79a34113d5e89dc5990ee6b793151fcbe87f039eb3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.jnucmat.2011.03.055$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3549,27923,27924,45994</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=24212216$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Garner, F.A.</creatorcontrib><creatorcontrib>Makenas, B.J.</creatorcontrib><creatorcontrib>Chastain, S.A.</creatorcontrib><title>Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II</title><title>Journal of nuclear materials</title><description>Three 37-pin MOX-fueled experimental subassemblies were irradiated in EBR-II with fuel pin cladding constructed from annealed AISI 304 stainless steel. Analysis of the swelling and irradiation creep of the cladding showed that the terminal swelling rate of AISI 304 stainless steel appears to be ∼1%/dpa and that swelling is very reproducible for identical irradiation conditions. The swelling at a given neutron fluence is rather sensitive to both irradiation temperature and especially to the neutron flux, however, with the primary influence residing in the transient regime. As the neutron flux increases the duration of the transient regime is increased in agreement with other recent studies. The duration of the transient regime is also decreased by increasing irradiation temperature.
In these assemblies swelling reached high levels rather quickly, reducing the opportunity for fuel pin cladding interaction and thereby reducing the contribution of irradiation creep to the total deformation. It also appears that in this swelling-before-creep scenario that the well-known “creep disappearance” phenomenon was operating strongly.</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>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkM1v1DAQxS0EEkvhT0DyBXFKGH8l8QmVqkCkokq0B26WY4_Bq3wsdrao_z1eZdVrT6MZ_d4bvUfIewY1A9Z82tf7-egmu9YcGKtB1KDUC7JjXSsq2XF4SXYAnFeCMfWavMl5DwBKg9qR6e4fjmOcf1M7e-oS4oEuQ8b0gJ7GmV72dz0VIGk44kgP5eJG6_1JENIy0fVPkdAft782wOaM0zBGzDSmZH206-Zz_eVn1fdvyatgx4zvzvOC3H-9vr_6Xt3cfuuvLm8qJ0W7VkGi6piWSkjWSO8aB4yHVtuyM-EVdto7pTUgNkOrBVMsuAG7NoDQOIgL8nGzPaTl7xHzaqaYXclpZ1yO2XSdloK3IAupNtKlJeeEwRxSnGx6NAzMqVyzN-dyzalcA8KUcovuw_mDzc6OIdnZxfwk5pIzzllTuM8bhyXtQ8Rksos4O_QxoVuNX-Izn_4DHbqQvw</recordid><startdate>20110601</startdate><enddate>20110601</enddate><creator>Garner, F.A.</creator><creator>Makenas, B.J.</creator><creator>Chastain, S.A.</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></search><sort><creationdate>20110601</creationdate><title>Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II</title><author>Garner, F.A. ; Makenas, B.J. ; Chastain, S.A.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c437t-f4e58194534164dc6c012f79a34113d5e89dc5990ee6b793151fcbe87f039eb3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</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>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Garner, F.A.</creatorcontrib><creatorcontrib>Makenas, B.J.</creatorcontrib><creatorcontrib>Chastain, S.A.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Garner, F.A.</au><au>Makenas, B.J.</au><au>Chastain, S.A.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II</atitle><jtitle>Journal of nuclear materials</jtitle><date>2011-06-01</date><risdate>2011</risdate><volume>413</volume><issue>1</issue><spage>53</spage><epage>61</epage><pages>53-61</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>Three 37-pin MOX-fueled experimental subassemblies were irradiated in EBR-II with fuel pin cladding constructed from annealed AISI 304 stainless steel. Analysis of the swelling and irradiation creep of the cladding showed that the terminal swelling rate of AISI 304 stainless steel appears to be ∼1%/dpa and that swelling is very reproducible for identical irradiation conditions. The swelling at a given neutron fluence is rather sensitive to both irradiation temperature and especially to the neutron flux, however, with the primary influence residing in the transient regime. As the neutron flux increases the duration of the transient regime is increased in agreement with other recent studies. The duration of the transient regime is also decreased by increasing irradiation temperature.
In these assemblies swelling reached high levels rather quickly, reducing the opportunity for fuel pin cladding interaction and thereby reducing the contribution of irradiation creep to the total deformation. It also appears that in this swelling-before-creep scenario that the well-known “creep disappearance” phenomenon was operating strongly.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2011.03.055</doi><tpages>9</tpages></addata></record> |
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| ispartof | Journal of nuclear materials, 2011-06, Vol.413 (1), p.53-61 |
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| language | eng |
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| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Applied sciences 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 Nuclear fuels |
| title | Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II |
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