Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide
Fission products, such as krypton (Kr), are known to be insoluble within UO 2 , segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identified that differences in grain boundary structure have a signifi...
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| Veröffentlicht in: | JOM 2014-12, Vol.66 (12), p.2562-2568 |
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| creator | Valderrama, Billy He, Lingfeng Henderson, Hunter B. Pakarinen, Janne Jaques, Brian Gan, Jian Butt, Darryl P. Allen, Todd R. Manuel, Michele V. |
| description | Fission products, such as krypton (Kr), are known to be insoluble within UO
2
, segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identified that differences in grain boundary structure have a significant effect on the segregation behavior of fission products. However, experimental work supporting these simulations is lacking. Atom probe tomography was used to measure the Kr distribution across grain boundaries in UO
2
. Polycrystalline depleted UO
2
samples were irradiated with 0.7 MeV and 1.8 MeV Kr-ions and annealed to 1000°C, 1300°C, and 1600°C for 1 h to produce a Kr-bubble dominated microstructure. The results of this work indicate a strong dependence of Kr concentration as a function of grain boundary structure. Temperature also influences grain boundary chemistry with greater Kr concentration evident at higher temperatures, resulting in a reduced Kr concentration in the bulk. Although Kr segregation takes place at elevated temperatures, no change in grain size or texture was observed in the irradiated UO
2
samples. |
| doi_str_mv | 10.1007/s11837-014-1182-x |
| format | Article |
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2
, segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identified that differences in grain boundary structure have a significant effect on the segregation behavior of fission products. However, experimental work supporting these simulations is lacking. Atom probe tomography was used to measure the Kr distribution across grain boundaries in UO
2
. Polycrystalline depleted UO
2
samples were irradiated with 0.7 MeV and 1.8 MeV Kr-ions and annealed to 1000°C, 1300°C, and 1600°C for 1 h to produce a Kr-bubble dominated microstructure. The results of this work indicate a strong dependence of Kr concentration as a function of grain boundary structure. Temperature also influences grain boundary chemistry with greater Kr concentration evident at higher temperatures, resulting in a reduced Kr concentration in the bulk. Although Kr segregation takes place at elevated temperatures, no change in grain size or texture was observed in the irradiated UO
2
samples.</description><identifier>ISSN: 1047-4838</identifier><identifier>EISSN: 1543-1851</identifier><identifier>DOI: 10.1007/s11837-014-1182-x</identifier><identifier>CODEN: JOMMER</identifier><language>eng</language><publisher>Boston: Springer US</publisher><subject>Annealing ; Chemistry/Food Science ; Computer simulation ; Earth Sciences ; Electrons ; Engineering ; Environment ; Fission products ; Fuels ; Grain boundaries ; Grain size ; Heat conductivity ; Krypton ; Microscopy ; Nuclear fission ; phonons, thermal conductivity, nuclear (including radiation effects), defects, materials and chemistry by design ; Physics ; Raw materials ; Segregations ; Studies ; Swelling ; Temperature ; Thermal conductivity ; Tomography ; Uranium ; Variance analysis</subject><ispartof>JOM, 2014-12, Vol.66 (12), p.2562-2568</ispartof><rights>The Minerals, Metals & Materials Society 2014</rights><rights>Copyright Springer Science & Business Media Dec 2014</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c446t-c772ef7b49ae15faf20ed24b7d83b539ddf8739701d5b8356a612d8b1d5518493</citedby><cites>FETCH-LOGICAL-c446t-c772ef7b49ae15faf20ed24b7d83b539ddf8739701d5b8356a612d8b1d5518493</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s11837-014-1182-x$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1007/s11837-014-1182-x$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,780,784,885,27924,27925,41488,42557,51319</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/1168339$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Valderrama, Billy</creatorcontrib><creatorcontrib>He, Lingfeng</creatorcontrib><creatorcontrib>Henderson, Hunter B.</creatorcontrib><creatorcontrib>Pakarinen, Janne</creatorcontrib><creatorcontrib>Jaques, Brian</creatorcontrib><creatorcontrib>Gan, Jian</creatorcontrib><creatorcontrib>Butt, Darryl P.</creatorcontrib><creatorcontrib>Allen, Todd R.</creatorcontrib><creatorcontrib>Manuel, Michele V.</creatorcontrib><creatorcontrib>Center for Materials Science of Nuclear Fuel (CMSNF)</creatorcontrib><creatorcontrib>Energy Frontier Research Centers (EFRC)</creatorcontrib><title>Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide</title><title>JOM</title><addtitle>JOM</addtitle><description>Fission products, such as krypton (Kr), are known to be insoluble within UO
2
, segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identified that differences in grain boundary structure have a significant effect on the segregation behavior of fission products. However, experimental work supporting these simulations is lacking. Atom probe tomography was used to measure the Kr distribution across grain boundaries in UO
2
. Polycrystalline depleted UO
2
samples were irradiated with 0.7 MeV and 1.8 MeV Kr-ions and annealed to 1000°C, 1300°C, and 1600°C for 1 h to produce a Kr-bubble dominated microstructure. The results of this work indicate a strong dependence of Kr concentration as a function of grain boundary structure. Temperature also influences grain boundary chemistry with greater Kr concentration evident at higher temperatures, resulting in a reduced Kr concentration in the bulk. Although Kr segregation takes place at elevated temperatures, no change in grain size or texture was observed in the irradiated UO
2
samples.</description><subject>Annealing</subject><subject>Chemistry/Food Science</subject><subject>Computer simulation</subject><subject>Earth Sciences</subject><subject>Electrons</subject><subject>Engineering</subject><subject>Environment</subject><subject>Fission products</subject><subject>Fuels</subject><subject>Grain boundaries</subject><subject>Grain size</subject><subject>Heat conductivity</subject><subject>Krypton</subject><subject>Microscopy</subject><subject>Nuclear fission</subject><subject>phonons, thermal conductivity, nuclear (including radiation effects), defects, materials and chemistry by design</subject><subject>Physics</subject><subject>Raw materials</subject><subject>Segregations</subject><subject>Studies</subject><subject>Swelling</subject><subject>Temperature</subject><subject>Thermal conductivity</subject><subject>Tomography</subject><subject>Uranium</subject><subject>Variance 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B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>3V.</scope><scope>4T-</scope><scope>4U-</scope><scope>7SR</scope><scope>7TA</scope><scope>7WY</scope><scope>7XB</scope><scope>883</scope><scope>88I</scope><scope>8BQ</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>8FK</scope><scope>8FL</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BEZIV</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>D1I</scope><scope>DWQXO</scope><scope>FRNLG</scope><scope>GNUQQ</scope><scope>HCIFZ</scope><scope>JG9</scope><scope>K60</scope><scope>K6~</scope><scope>KB.</scope><scope>L.-</scope><scope>M0F</scope><scope>M2P</scope><scope>PDBOC</scope><scope>PQBIZ</scope><scope>PQBZA</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>Q9U</scope><scope>S0X</scope><scope>OTOTI</scope></search><sort><creationdate>20141201</creationdate><title>Effect of Grain Boundaries on Krypton Segregation 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materials and chemistry by design</topic><topic>Physics</topic><topic>Raw materials</topic><topic>Segregations</topic><topic>Studies</topic><topic>Swelling</topic><topic>Temperature</topic><topic>Thermal conductivity</topic><topic>Tomography</topic><topic>Uranium</topic><topic>Variance analysis</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Valderrama, Billy</creatorcontrib><creatorcontrib>He, Lingfeng</creatorcontrib><creatorcontrib>Henderson, Hunter B.</creatorcontrib><creatorcontrib>Pakarinen, Janne</creatorcontrib><creatorcontrib>Jaques, Brian</creatorcontrib><creatorcontrib>Gan, Jian</creatorcontrib><creatorcontrib>Butt, Darryl P.</creatorcontrib><creatorcontrib>Allen, Todd R.</creatorcontrib><creatorcontrib>Manuel, Michele V.</creatorcontrib><creatorcontrib>Center for Materials Science of Nuclear Fuel (CMSNF)</creatorcontrib><creatorcontrib>Energy Frontier Research Centers 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(EFRC)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide</atitle><jtitle>JOM</jtitle><stitle>JOM</stitle><date>2014-12-01</date><risdate>2014</risdate><volume>66</volume><issue>12</issue><spage>2562</spage><epage>2568</epage><pages>2562-2568</pages><issn>1047-4838</issn><eissn>1543-1851</eissn><coden>JOMMER</coden><abstract>Fission products, such as krypton (Kr), are known to be insoluble within UO
2
, segregating toward grain boundaries and eventually leading to a lowering in thermal conductivity and fuel swelling. Recent computational studies have identified that differences in grain boundary structure have a significant effect on the segregation behavior of fission products. However, experimental work supporting these simulations is lacking. Atom probe tomography was used to measure the Kr distribution across grain boundaries in UO
2
. Polycrystalline depleted UO
2
samples were irradiated with 0.7 MeV and 1.8 MeV Kr-ions and annealed to 1000°C, 1300°C, and 1600°C for 1 h to produce a Kr-bubble dominated microstructure. The results of this work indicate a strong dependence of Kr concentration as a function of grain boundary structure. Temperature also influences grain boundary chemistry with greater Kr concentration evident at higher temperatures, resulting in a reduced Kr concentration in the bulk. Although Kr segregation takes place at elevated temperatures, no change in grain size or texture was observed in the irradiated UO
2
samples.</abstract><cop>Boston</cop><pub>Springer US</pub><doi>10.1007/s11837-014-1182-x</doi><tpages>7</tpages></addata></record> |
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| subjects | Annealing Chemistry/Food Science Computer simulation Earth Sciences Electrons Engineering Environment Fission products Fuels Grain boundaries Grain size Heat conductivity Krypton Microscopy Nuclear fission phonons, thermal conductivity, nuclear (including radiation effects), defects, materials and chemistry by design Physics Raw materials Segregations Studies Swelling Temperature Thermal conductivity Tomography Uranium Variance analysis |
| title | Effect of Grain Boundaries on Krypton Segregation Behavior in Irradiated Uranium Dioxide |
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