Loading…
Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel
A U-7Mo alloy/6061 Al alloy matrix mini-dispersion fuel plate was irradiated in the Advanced Test Reactor and then examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructure of the as-fabricated disp...
Saved in:
| Published in: | Journal of nuclear materials 2009-09, Vol.393 (2), p.311-320 |
|---|---|
| Main Authors: | , , , , , |
| Format: | Article |
| Language: | English |
| Subjects: | |
| Citations: | Items that this one cites Items that cite this one |
| Online Access: | Get full text |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| cited_by | cdi_FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33 |
|---|---|
| cites | cdi_FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33 |
| container_end_page | 320 |
| container_issue | 2 |
| container_start_page | 311 |
| container_title | Journal of nuclear materials |
| container_volume | 393 |
| creator | Keiser, Dennis D. Robinson, Adam B. Jue, Jan-Fong Medvedev, Pavel Wachs, Daniel M. Finlay, M. Ross |
| description | A U-7Mo alloy/6061 Al alloy matrix mini-dispersion fuel plate was irradiated in the Advanced Test Reactor and then examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructure of the as-fabricated dispersion fuel to identify changes that occurred during irradiation. The layer that formed on the surface of the fuel U-7Mo particles during fuel plate fabrication exhibits stable irradiation performance as a result of the ∼0.88
wt% Si present in the fuel meat matrix. During irradiation, the pre-formed interaction layer changed very little in thickness and composition. The overall irradiation performance of the fuel plate to moderate power and burnup was considered excellent. |
| doi_str_mv | 10.1016/j.jnucmat.2009.06.018 |
| format | article |
| fullrecord | <record><control><sourceid>proquest_osti_</sourceid><recordid>TN_cdi_osti_scitechconnect_968549</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0022311509006801</els_id><sourcerecordid>20799223</sourcerecordid><originalsourceid>FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33</originalsourceid><addsrcrecordid>eNqFkU9r3DAUxEVpIds0HyGgHtqbnSdZf6xTCSFtAwm5JGehlZ-pFq21leTQfPvY7NJrTu_ymzfMDCGXDFoGTF3t2t00-72rLQcwLagWWP-BbFivu0b0HD6SDQDnTceYPCOfS9kBgDQgN-TpIficSs2zr3N2kQ74gjEd9jhVGiYacnZDcBUH-tzoh3SlQDF6HamLMb3SxTSHf3QI5YC5hDTRccb4hXwaXSx4cbrn5Pnn7dPN7-b-8dfdzfV94wXXtWFcq62DvkcjuGIjH72RILZMKo1Gmc5o7ZwY-60zg0anmZHYSQXay2H0XXdOvh7_LgGCLT5U9H98mib01RrVS2EW5vuROeT0d8ZS7T4UjzG6CdNcbCe0ZkrJd0EO2hjOV1d5BNfiSsbRHnLYu_xqGdh1ELuzp0HsOogFZZdBFt23k4Er3sUxu8mH8l_MmQEhOr5wP44cLtW9BMxrMpw8DiGvwYYU3nF6A2GmopQ</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>20799223</pqid></control><display><type>article</type><title>Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel</title><source>ScienceDirect Freedom Collection</source><creator>Keiser, Dennis D. ; Robinson, Adam B. ; Jue, Jan-Fong ; Medvedev, Pavel ; Wachs, Daniel M. ; Finlay, M. Ross</creator><creatorcontrib>Keiser, Dennis D. ; Robinson, Adam B. ; Jue, Jan-Fong ; Medvedev, Pavel ; Wachs, Daniel M. ; Finlay, M. Ross ; Idaho National Laboratory (INL)</creatorcontrib><description>A U-7Mo alloy/6061 Al alloy matrix mini-dispersion fuel plate was irradiated in the Advanced Test Reactor and then examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructure of the as-fabricated dispersion fuel to identify changes that occurred during irradiation. The layer that formed on the surface of the fuel U-7Mo particles during fuel plate fabrication exhibits stable irradiation performance as a result of the ∼0.88
wt% Si present in the fuel meat matrix. During irradiation, the pre-formed interaction layer changed very little in thickness and composition. The overall irradiation performance of the fuel plate to moderate power and burnup was considered excellent.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2009.06.018</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>ALLOYS ; Applied sciences ; BURNUP ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; FABRICATION ; Fission nuclear power plants ; FUEL PLATES ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; irradiated U-7Mo/6061 Al alloy matrix dispersion f ; IRRADIATION ; low enriched uranium ; MEAT ; METALLOGRAPHY ; microstructural development ; MICROSTRUCTURE ; NUCLEAR FUEL CYCLE AND FUEL MATERIALS ; Nuclear fuels ; Reduced Enrichment for Research and Test Reactors ; SCANNING ELECTRON MICROSCOPY ; TEST REACTORS ; THICKNESS</subject><ispartof>Journal of nuclear materials, 2009-09, Vol.393 (2), p.311-320</ispartof><rights>2009</rights><rights>2009 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33</citedby><cites>FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>230,314,780,784,885,27924,27925</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=21904432$$DView record in Pascal Francis$$Hfree_for_read</backlink><backlink>$$Uhttps://www.osti.gov/biblio/968549$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Keiser, Dennis D.</creatorcontrib><creatorcontrib>Robinson, Adam B.</creatorcontrib><creatorcontrib>Jue, Jan-Fong</creatorcontrib><creatorcontrib>Medvedev, Pavel</creatorcontrib><creatorcontrib>Wachs, Daniel M.</creatorcontrib><creatorcontrib>Finlay, M. Ross</creatorcontrib><creatorcontrib>Idaho National Laboratory (INL)</creatorcontrib><title>Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel</title><title>Journal of nuclear materials</title><description>A U-7Mo alloy/6061 Al alloy matrix mini-dispersion fuel plate was irradiated in the Advanced Test Reactor and then examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructure of the as-fabricated dispersion fuel to identify changes that occurred during irradiation. The layer that formed on the surface of the fuel U-7Mo particles during fuel plate fabrication exhibits stable irradiation performance as a result of the ∼0.88
wt% Si present in the fuel meat matrix. During irradiation, the pre-formed interaction layer changed very little in thickness and composition. The overall irradiation performance of the fuel plate to moderate power and burnup was considered excellent.</description><subject>ALLOYS</subject><subject>Applied sciences</subject><subject>BURNUP</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>FABRICATION</subject><subject>Fission nuclear power plants</subject><subject>FUEL PLATES</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>irradiated U-7Mo/6061 Al alloy matrix dispersion f</subject><subject>IRRADIATION</subject><subject>low enriched uranium</subject><subject>MEAT</subject><subject>METALLOGRAPHY</subject><subject>microstructural development</subject><subject>MICROSTRUCTURE</subject><subject>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</subject><subject>Nuclear fuels</subject><subject>Reduced Enrichment for Research and Test Reactors</subject><subject>SCANNING ELECTRON MICROSCOPY</subject><subject>TEST REACTORS</subject><subject>THICKNESS</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2009</creationdate><recordtype>article</recordtype><recordid>eNqFkU9r3DAUxEVpIds0HyGgHtqbnSdZf6xTCSFtAwm5JGehlZ-pFq21leTQfPvY7NJrTu_ymzfMDCGXDFoGTF3t2t00-72rLQcwLagWWP-BbFivu0b0HD6SDQDnTceYPCOfS9kBgDQgN-TpIficSs2zr3N2kQ74gjEd9jhVGiYacnZDcBUH-tzoh3SlQDF6HamLMb3SxTSHf3QI5YC5hDTRccb4hXwaXSx4cbrn5Pnn7dPN7-b-8dfdzfV94wXXtWFcq62DvkcjuGIjH72RILZMKo1Gmc5o7ZwY-60zg0anmZHYSQXay2H0XXdOvh7_LgGCLT5U9H98mib01RrVS2EW5vuROeT0d8ZS7T4UjzG6CdNcbCe0ZkrJd0EO2hjOV1d5BNfiSsbRHnLYu_xqGdh1ELuzp0HsOogFZZdBFt23k4Er3sUxu8mH8l_MmQEhOr5wP44cLtW9BMxrMpw8DiGvwYYU3nF6A2GmopQ</recordid><startdate>20090901</startdate><enddate>20090901</enddate><creator>Keiser, Dennis D.</creator><creator>Robinson, Adam B.</creator><creator>Jue, Jan-Fong</creator><creator>Medvedev, Pavel</creator><creator>Wachs, Daniel M.</creator><creator>Finlay, M. Ross</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><scope>7QF</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>20090901</creationdate><title>Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel</title><author>Keiser, Dennis D. ; Robinson, Adam B. ; Jue, Jan-Fong ; Medvedev, Pavel ; Wachs, Daniel M. ; Finlay, M. Ross</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2009</creationdate><topic>ALLOYS</topic><topic>Applied sciences</topic><topic>BURNUP</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>FABRICATION</topic><topic>Fission nuclear power plants</topic><topic>FUEL PLATES</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>irradiated U-7Mo/6061 Al alloy matrix dispersion f</topic><topic>IRRADIATION</topic><topic>low enriched uranium</topic><topic>MEAT</topic><topic>METALLOGRAPHY</topic><topic>microstructural development</topic><topic>MICROSTRUCTURE</topic><topic>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</topic><topic>Nuclear fuels</topic><topic>Reduced Enrichment for Research and Test Reactors</topic><topic>SCANNING ELECTRON MICROSCOPY</topic><topic>TEST REACTORS</topic><topic>THICKNESS</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Keiser, Dennis D.</creatorcontrib><creatorcontrib>Robinson, Adam B.</creatorcontrib><creatorcontrib>Jue, Jan-Fong</creatorcontrib><creatorcontrib>Medvedev, Pavel</creatorcontrib><creatorcontrib>Wachs, Daniel M.</creatorcontrib><creatorcontrib>Finlay, M. Ross</creatorcontrib><creatorcontrib>Idaho National Laboratory (INL)</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Aluminium Industry 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>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>Keiser, Dennis D.</au><au>Robinson, Adam B.</au><au>Jue, Jan-Fong</au><au>Medvedev, Pavel</au><au>Wachs, Daniel M.</au><au>Finlay, M. Ross</au><aucorp>Idaho National Laboratory (INL)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel</atitle><jtitle>Journal of nuclear materials</jtitle><date>2009-09-01</date><risdate>2009</risdate><volume>393</volume><issue>2</issue><spage>311</spage><epage>320</epage><pages>311-320</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>A U-7Mo alloy/6061 Al alloy matrix mini-dispersion fuel plate was irradiated in the Advanced Test Reactor and then examined using optical metallography and scanning electron microscopy to characterize the developed microstructure. Results were compared to the microstructure of the as-fabricated dispersion fuel to identify changes that occurred during irradiation. The layer that formed on the surface of the fuel U-7Mo particles during fuel plate fabrication exhibits stable irradiation performance as a result of the ∼0.88
wt% Si present in the fuel meat matrix. During irradiation, the pre-formed interaction layer changed very little in thickness and composition. The overall irradiation performance of the fuel plate to moderate power and burnup was considered excellent.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2009.06.018</doi><tpages>10</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0022-3115 |
| ispartof | Journal of nuclear materials, 2009-09, Vol.393 (2), p.311-320 |
| issn | 0022-3115 1873-4820 |
| language | eng |
| recordid | cdi_osti_scitechconnect_968549 |
| source | ScienceDirect Freedom Collection |
| subjects | ALLOYS Applied sciences BURNUP Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology FABRICATION Fission nuclear power plants FUEL PLATES Fuels Installations for energy generation and conversion: thermal and electrical energy irradiated U-7Mo/6061 Al alloy matrix dispersion f IRRADIATION low enriched uranium MEAT METALLOGRAPHY microstructural development MICROSTRUCTURE NUCLEAR FUEL CYCLE AND FUEL MATERIALS Nuclear fuels Reduced Enrichment for Research and Test Reactors SCANNING ELECTRON MICROSCOPY TEST REACTORS THICKNESS |
| title | Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel |
| url | http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-27T12%3A40%3A25IST&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=Microstructural%20development%20in%20irradiated%20U-7Mo/6061%20Al%20alloy%20matrix%20dispersion%20fuel&rft.jtitle=Journal%20of%20nuclear%20materials&rft.au=Keiser,%20Dennis%20D.&rft.aucorp=Idaho%20National%20Laboratory%20(INL)&rft.date=2009-09-01&rft.volume=393&rft.issue=2&rft.spage=311&rft.epage=320&rft.pages=311-320&rft.issn=0022-3115&rft.eissn=1873-4820&rft.coden=JNUMAM&rft_id=info:doi/10.1016/j.jnucmat.2009.06.018&rft_dat=%3Cproquest_osti_%3E20799223%3C/proquest_osti_%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-c427t-1276ba088e94261f2fc9504b1567e9693977aa4f8ba9d7ea7195e35607c5dfc33%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_pqid=20799223&rft_id=info:pmid/&rfr_iscdi=true |