Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets
UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a...
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Veröffentlicht in: | Journal of nuclear materials 2006-06, Vol.352 (1-3), p.151-156 |
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container_title | Journal of nuclear materials |
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creator | Kim, Si-Hyung Joung, Chang-Young Kim, Han-Soo Lee, Young-Woo Ryu, Ho-Jin Sohn, Dong-Seong Kim, Dong-Joo |
description | UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ=(A+BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2. |
doi_str_mv | 10.1016/j.jnucmat.2006.02.049 |
format | Article |
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The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ=(A+BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2006.02.049</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Energy ; Exact sciences and technology ; Fuels ; Nuclear fuels ; Preparation and processing of nuclear fuels</subject><ispartof>Journal of nuclear materials, 2006-06, Vol.352 (1-3), p.151-156</ispartof><rights>2006 Elsevier B.V.</rights><rights>2006 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c370t-bc4ee533e8bbfa7829a2a4681c2dd6ac12d81a75ff4255951149d465369f238d3</citedby><cites>FETCH-LOGICAL-c370t-bc4ee533e8bbfa7829a2a4681c2dd6ac12d81a75ff4255951149d465369f238d3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311506001188$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,23909,23910,25118,27901,27902,65534</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=17919212$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Kim, Si-Hyung</creatorcontrib><creatorcontrib>Joung, Chang-Young</creatorcontrib><creatorcontrib>Kim, Han-Soo</creatorcontrib><creatorcontrib>Lee, Young-Woo</creatorcontrib><creatorcontrib>Ryu, Ho-Jin</creatorcontrib><creatorcontrib>Sohn, Dong-Seong</creatorcontrib><creatorcontrib>Kim, Dong-Joo</creatorcontrib><title>Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets</title><title>Journal of nuclear materials</title><description>UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ=(A+BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2.</description><subject>Applied sciences</subject><subject>Energy</subject><subject>Exact sciences and technology</subject><subject>Fuels</subject><subject>Nuclear fuels</subject><subject>Preparation and processing of nuclear fuels</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2006</creationdate><recordtype>article</recordtype><recordid>eNqFkE1r3DAQhkVpoNukP6GgS3uzow_Ltk6lhCYtBHJpz2IsjYkWS3IlOXT_fR12ocee5vK88848hHzkrOWM97fH9hg3G6C2grG-ZaJlnX5DDnwcZNONgr0lB8aEaCTn6h15X8qRMaY0Uwfi72HK3kL1KdKA9Tk5CtHR-ow5wEJtim6z1b_4eqJQCpYSMFaaZhrScpocxi00a0brV1-hoqNbhui3QJ1Pf7xDuuKyYC035GqGpeCHy7wmv-6__bz73jw-Pfy4-_rYWDmw2ky2Q1RS4jhNMwyj0CCg60duhXM9WC7cyGFQ89wJpbTivNOu65Xs9Szk6OQ1-Xzeu-b0e8NSTfDF7jdAxLQVI7Tse9mNO6jOoM2plIyzWbMPkE-GM_Mq1hzNRax5FWuYMLvYPffpUgDFwjLv71pf_oUHzbXgYue-nDncv33xmE2xHqNF53dd1bjk_9P0FxRVlBk</recordid><startdate>20060630</startdate><enddate>20060630</enddate><creator>Kim, Si-Hyung</creator><creator>Joung, Chang-Young</creator><creator>Kim, Han-Soo</creator><creator>Lee, Young-Woo</creator><creator>Ryu, Ho-Jin</creator><creator>Sohn, Dong-Seong</creator><creator>Kim, Dong-Joo</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</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></search><sort><creationdate>20060630</creationdate><title>Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets</title><author>Kim, Si-Hyung ; Joung, Chang-Young ; Kim, Han-Soo ; Lee, Young-Woo ; Ryu, Ho-Jin ; Sohn, Dong-Seong ; Kim, Dong-Joo</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c370t-bc4ee533e8bbfa7829a2a4681c2dd6ac12d81a75ff4255951149d465369f238d3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2006</creationdate><topic>Applied sciences</topic><topic>Energy</topic><topic>Exact sciences and technology</topic><topic>Fuels</topic><topic>Nuclear fuels</topic><topic>Preparation and processing of nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kim, Si-Hyung</creatorcontrib><creatorcontrib>Joung, Chang-Young</creatorcontrib><creatorcontrib>Kim, Han-Soo</creatorcontrib><creatorcontrib>Lee, Young-Woo</creatorcontrib><creatorcontrib>Ryu, Ho-Jin</creatorcontrib><creatorcontrib>Sohn, Dong-Seong</creatorcontrib><creatorcontrib>Kim, Dong-Joo</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</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><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kim, Si-Hyung</au><au>Joung, Chang-Young</au><au>Kim, Han-Soo</au><au>Lee, Young-Woo</au><au>Ryu, Ho-Jin</au><au>Sohn, Dong-Seong</au><au>Kim, Dong-Joo</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets</atitle><jtitle>Journal of nuclear materials</jtitle><date>2006-06-30</date><risdate>2006</risdate><volume>352</volume><issue>1-3</issue><spage>151</spage><epage>156</epage><pages>151-156</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ=(A+BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2006.02.049</doi><tpages>6</tpages></addata></record> |
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subjects | Applied sciences Energy Exact sciences and technology Fuels Nuclear fuels Preparation and processing of nuclear fuels |
title | Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets |
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