TEM examination of phases formed between U–Pu–Zr fuel and Fe
Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring...
Gespeichert in:
| Veröffentlicht in: | Journal of nuclear materials 2015-12, Vol.467 (Part 2), p.717-723 |
|---|---|
| Hauptverfasser: | , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 723 |
|---|---|
| container_issue | Part 2 |
| container_start_page | 717 |
| container_title | Journal of nuclear materials |
| container_volume | 467 |
| creator | Aitkaliyeva, Assel Madden, James W. Miller, Brandon D. Papesch, Cynthia A. Cole, James I. |
| description | Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U–22Pu–4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), β-Zr (Im-3m), and ZrO2 (Fm-3m). |
| doi_str_mv | 10.1016/j.jnucmat.2015.10.043 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_osti_</sourceid><recordid>TN_cdi_osti_scitechconnect_1252516</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0022311515302890</els_id><sourcerecordid>1808699266</sourcerecordid><originalsourceid>FETCH-LOGICAL-c449t-c47aeca81fec2944d6d49f07b0cbeb49e4cadc4c9575aba41277ec9586ce3b483</originalsourceid><addsrcrecordid>eNqNUctOwzAQtBBIlMInIFmcuDTYjp3HCVDVAlIRHNoLF8txNqqjxi52wuPGP_CHfAmJ2jtcdrWjmdFoB6FzSiJKaHJVR7XtdKPaiBEqeiwiPD5AI5ql8YRnjByiESGMTWJKxTE6CaEmhIiciBG6Wc4eMXyoxljVGmexq_B2rQIEXDnfQIkLaN8BLF79fH0_d_148bjqYIOVLfEcTtFRpTYBzvZ7jFbz2XJ6P1k83T1MbxcTzXne9jNVoFVGK9As57xMSp5XJC2ILqDgOXCtSs11LlKhCsUpS1PoryzREBc8i8foYufrQmtk0KYFvdbOWtCtpEwwQZOedLkjbb177SC0sjFBw2ajLLguSJoxwZOUsuwfVJIlec6SwVXsqNq7EDxUcutNo_ynpEQODcha7huQQwMD3DfQ6653Ouj_8mbAD7HBaiiNH1KXzvzh8AvNm5JE</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1808699266</pqid></control><display><type>article</type><title>TEM examination of phases formed between U–Pu–Zr fuel and Fe</title><source>Access via ScienceDirect (Elsevier)</source><creator>Aitkaliyeva, Assel ; Madden, James W. ; Miller, Brandon D. ; Papesch, Cynthia A. ; Cole, James I.</creator><creatorcontrib>Aitkaliyeva, Assel ; Madden, James W. ; Miller, Brandon D. ; Papesch, Cynthia A. ; Cole, James I.</creatorcontrib><description>Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U–22Pu–4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), β-Zr (Im-3m), and ZrO2 (Fm-3m).</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2015.10.043</identifier><language>eng</language><publisher>Netherlands: Elsevier B.V</publisher><subject>Brittleness ; Cladding ; Diffusion ; Electron microscopes ; Fuel-cladding chemical interaction (FCCI) ; Fuels ; Metal fuel ; Nuclear engineering ; Phases ; Transmission electron microscopy ; U–Pu–Zr</subject><ispartof>Journal of nuclear materials, 2015-12, Vol.467 (Part 2), p.717-723</ispartof><rights>2015</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c449t-c47aeca81fec2944d6d49f07b0cbeb49e4cadc4c9575aba41277ec9586ce3b483</citedby><cites>FETCH-LOGICAL-c449t-c47aeca81fec2944d6d49f07b0cbeb49e4cadc4c9575aba41277ec9586ce3b483</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.2015.10.043$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,315,781,785,886,3551,27929,27930,46000</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/1252516$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Aitkaliyeva, Assel</creatorcontrib><creatorcontrib>Madden, James W.</creatorcontrib><creatorcontrib>Miller, Brandon D.</creatorcontrib><creatorcontrib>Papesch, Cynthia A.</creatorcontrib><creatorcontrib>Cole, James I.</creatorcontrib><title>TEM examination of phases formed between U–Pu–Zr fuel and Fe</title><title>Journal of nuclear materials</title><description>Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U–22Pu–4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), β-Zr (Im-3m), and ZrO2 (Fm-3m).</description><subject>Brittleness</subject><subject>Cladding</subject><subject>Diffusion</subject><subject>Electron microscopes</subject><subject>Fuel-cladding chemical interaction (FCCI)</subject><subject>Fuels</subject><subject>Metal fuel</subject><subject>Nuclear engineering</subject><subject>Phases</subject><subject>Transmission electron microscopy</subject><subject>U–Pu–Zr</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2015</creationdate><recordtype>article</recordtype><recordid>eNqNUctOwzAQtBBIlMInIFmcuDTYjp3HCVDVAlIRHNoLF8txNqqjxi52wuPGP_CHfAmJ2jtcdrWjmdFoB6FzSiJKaHJVR7XtdKPaiBEqeiwiPD5AI5ql8YRnjByiESGMTWJKxTE6CaEmhIiciBG6Wc4eMXyoxljVGmexq_B2rQIEXDnfQIkLaN8BLF79fH0_d_148bjqYIOVLfEcTtFRpTYBzvZ7jFbz2XJ6P1k83T1MbxcTzXne9jNVoFVGK9As57xMSp5XJC2ILqDgOXCtSs11LlKhCsUpS1PoryzREBc8i8foYufrQmtk0KYFvdbOWtCtpEwwQZOedLkjbb177SC0sjFBw2ajLLguSJoxwZOUsuwfVJIlec6SwVXsqNq7EDxUcutNo_ynpEQODcha7huQQwMD3DfQ6653Ouj_8mbAD7HBaiiNH1KXzvzh8AvNm5JE</recordid><startdate>201512</startdate><enddate>201512</enddate><creator>Aitkaliyeva, Assel</creator><creator>Madden, James W.</creator><creator>Miller, Brandon D.</creator><creator>Papesch, Cynthia A.</creator><creator>Cole, James I.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7QQ</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>JG9</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>201512</creationdate><title>TEM examination of phases formed between U–Pu–Zr fuel and Fe</title><author>Aitkaliyeva, Assel ; Madden, James W. ; Miller, Brandon D. ; Papesch, Cynthia A. ; Cole, James I.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c449t-c47aeca81fec2944d6d49f07b0cbeb49e4cadc4c9575aba41277ec9586ce3b483</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2015</creationdate><topic>Brittleness</topic><topic>Cladding</topic><topic>Diffusion</topic><topic>Electron microscopes</topic><topic>Fuel-cladding chemical interaction (FCCI)</topic><topic>Fuels</topic><topic>Metal fuel</topic><topic>Nuclear engineering</topic><topic>Phases</topic><topic>Transmission electron microscopy</topic><topic>U–Pu–Zr</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Aitkaliyeva, Assel</creatorcontrib><creatorcontrib>Madden, James W.</creatorcontrib><creatorcontrib>Miller, Brandon D.</creatorcontrib><creatorcontrib>Papesch, Cynthia A.</creatorcontrib><creatorcontrib>Cole, James I.</creatorcontrib><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Ceramic 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>Aerospace Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Aitkaliyeva, Assel</au><au>Madden, James W.</au><au>Miller, Brandon D.</au><au>Papesch, Cynthia A.</au><au>Cole, James I.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>TEM examination of phases formed between U–Pu–Zr fuel and Fe</atitle><jtitle>Journal of nuclear materials</jtitle><date>2015-12</date><risdate>2015</risdate><volume>467</volume><issue>Part 2</issue><spage>717</spage><epage>723</epage><pages>717-723</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U–22Pu–4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), β-Zr (Im-3m), and ZrO2 (Fm-3m).</abstract><cop>Netherlands</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2015.10.043</doi><tpages>7</tpages><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0022-3115 |
| ispartof | Journal of nuclear materials, 2015-12, Vol.467 (Part 2), p.717-723 |
| issn | 0022-3115 1873-4820 |
| language | eng |
| recordid | cdi_osti_scitechconnect_1252516 |
| source | Access via ScienceDirect (Elsevier) |
| subjects | Brittleness Cladding Diffusion Electron microscopes Fuel-cladding chemical interaction (FCCI) Fuels Metal fuel Nuclear engineering Phases Transmission electron microscopy U–Pu–Zr |
| title | TEM examination of phases formed between U–Pu–Zr fuel and Fe |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-15T22%3A42%3A56IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_osti_&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=TEM%20examination%20of%20phases%20formed%20between%20U%E2%80%93Pu%E2%80%93Zr%20fuel%20and%20Fe&rft.jtitle=Journal%20of%20nuclear%20materials&rft.au=Aitkaliyeva,%20Assel&rft.date=2015-12&rft.volume=467&rft.issue=Part%202&rft.spage=717&rft.epage=723&rft.pages=717-723&rft.issn=0022-3115&rft.eissn=1873-4820&rft_id=info:doi/10.1016/j.jnucmat.2015.10.043&rft_dat=%3Cproquest_osti_%3E1808699266%3C/proquest_osti_%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=1808699266&rft_id=info:pmid/&rft_els_id=S0022311515302890&rfr_iscdi=true |