Fission product release in thoria and urania defective fuel experiments FDO-680 and FDO-681
FDO-680 (thoria as ThO2-4%UO2) and FDO-681 (urania) were circa 1975 intentionally defected fuel experiments conducted in the National Research Experimental (NRX) reactor X-2 defect loop in Chalk River, Canada. The intent of these experiments was to determine the release rates of fission gases and ra...
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| Veröffentlicht in: | Journal of nuclear materials 2019-04, Vol.516, p.309-316 |
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| creator | Barry, Aaron Livingstone, Steve Floyd, Mark R. |
| description | FDO-680 (thoria as ThO2-4%UO2) and FDO-681 (urania) were circa 1975 intentionally defected fuel experiments conducted in the National Research Experimental (NRX) reactor X-2 defect loop in Chalk River, Canada. The intent of these experiments was to determine the release rates of fission gases and radioiodines from a defected ThO2-4%UO2 element and to determine the extent to which a moderately powered ThO2-4%UO2 element would deteriorate when defected. Detailed analysis of the FDO-680 and FDO-681 fission product release data has only recently been undertaken. The objective of analyzing this data is to address a gap in defected thoria fuel behaviour knowledge enroute to commercialisation of thoria fuels. The analysis suggests: 1) thoria fuel has superior stability when defected relative to urania, 2) thoria results in a lower fission product burden in the Primary Heat Transport System (PHTS) than urania under steady-state conditions, and 3) the fission product transport models developed for urania cannot be directly applied to thoria.
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| doi_str_mv | 10.1016/j.jnucmat.2019.01.044 |
| format | Article |
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[Display omitted]</description><subject>Commercialization</subject><subject>Data processing</subject><subject>Experiments</subject><subject>Fission products</subject><subject>Gases</subject><subject>Heat transport</subject><subject>Nuclear fuels</subject><subject>Rivers</subject><subject>Stability analysis</subject><subject>Thorium dioxide</subject><subject>Thorium oxides</subject><subject>Transport</subject><subject>Uranium dioxide</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNqFkEFL7TAQhYM8wfvUnyAEXLfOJG2arER8XhUEN7pyEWIyxZRre01aef57o9e9qzmLc87MfIydINQIqM6GehgX_-rmWgCaGrCGptljK9SdrBot4A9bAQhRScT2gP3NeQCA1kC7Yk_rmHOcRr5NU1j8zBNtyGXiceTzy5Si424MfEluLDJQT36O78T7hTac_m8pxVca58zX_-4rpeHbvdN4xPZ7t8l0_DMP2eP66uHyprq7v769vLirvDQwV8Zp51AqdEEpkE1QnQPXh05op6VQIUj1LA115KFYBWjTGa2ok50ADygP2emut_zwtlCe7TAtaSwrrUBjtGkRm-Jqdy6fppwT9XZbbnfpwyLYL452sD8c7RdHC2gLx5I73-WovPAeKdnsI42eQkwFhg1T_KXhE054fFI</recordid><startdate>20190401</startdate><enddate>20190401</enddate><creator>Barry, Aaron</creator><creator>Livingstone, Steve</creator><creator>Floyd, Mark R.</creator><general>Elsevier B.V</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SR</scope><scope>7ST</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>SOI</scope></search><sort><creationdate>20190401</creationdate><title>Fission product release in thoria and urania defective fuel experiments FDO-680 and FDO-681</title><author>Barry, Aaron ; Livingstone, Steve ; Floyd, Mark R.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c390t-9a8aa1361ad66034d67a0afd728a8326dd36b39e7ec0a8a20897986e73720c013</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>Commercialization</topic><topic>Data processing</topic><topic>Experiments</topic><topic>Fission products</topic><topic>Gases</topic><topic>Heat transport</topic><topic>Nuclear fuels</topic><topic>Rivers</topic><topic>Stability analysis</topic><topic>Thorium dioxide</topic><topic>Thorium oxides</topic><topic>Transport</topic><topic>Uranium dioxide</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Barry, Aaron</creatorcontrib><creatorcontrib>Livingstone, Steve</creatorcontrib><creatorcontrib>Floyd, Mark R.</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Barry, Aaron</au><au>Livingstone, Steve</au><au>Floyd, Mark R.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Fission product release in thoria and urania defective fuel experiments FDO-680 and FDO-681</atitle><jtitle>Journal of nuclear materials</jtitle><date>2019-04-01</date><risdate>2019</risdate><volume>516</volume><spage>309</spage><epage>316</epage><pages>309-316</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>FDO-680 (thoria as ThO2-4%UO2) and FDO-681 (urania) were circa 1975 intentionally defected fuel experiments conducted in the National Research Experimental (NRX) reactor X-2 defect loop in Chalk River, Canada. The intent of these experiments was to determine the release rates of fission gases and radioiodines from a defected ThO2-4%UO2 element and to determine the extent to which a moderately powered ThO2-4%UO2 element would deteriorate when defected. Detailed analysis of the FDO-680 and FDO-681 fission product release data has only recently been undertaken. The objective of analyzing this data is to address a gap in defected thoria fuel behaviour knowledge enroute to commercialisation of thoria fuels. The analysis suggests: 1) thoria fuel has superior stability when defected relative to urania, 2) thoria results in a lower fission product burden in the Primary Heat Transport System (PHTS) than urania under steady-state conditions, and 3) the fission product transport models developed for urania cannot be directly applied to thoria.
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| ispartof | Journal of nuclear materials, 2019-04, Vol.516, p.309-316 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Commercialization Data processing Experiments Fission products Gases Heat transport Nuclear fuels Rivers Stability analysis Thorium dioxide Thorium oxides Transport Uranium dioxide |
| title | Fission product release in thoria and urania defective fuel experiments FDO-680 and FDO-681 |
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