Modelling of the Extraction of Uranium with Supercritical Carbon Dioxide
A model is presented for the analysis of the results of extraction of uranium in a flow system by supercritical fluid modified with tributylphosphate from a nitric acid matrix, in which the extraction is not limited by the solubility of the uranium species. The model used is that of diffusion out of...
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| Veröffentlicht in: | Journal of nuclear science and technology 2001-06, Vol.38 (6), p.433-438 |
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| container_end_page | 438 |
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| container_issue | 6 |
| container_start_page | 433 |
| container_title | Journal of nuclear science and technology |
| container_volume | 38 |
| creator | CLIFFORD, Anthony A. ZHU, Shuang SMART, Neil G. LIN, Yuehe WAI, Chien M. YOSHIDA, Zenko MEGURO, Yoshihiro ISO, Shuichi |
| description | A model is presented for the analysis of the results of extraction of uranium in a flow system by supercritical fluid modified with tributylphosphate from a nitric acid matrix, in which the extraction is not limited by the solubility of the uranium species. The model used is that of diffusion out of a sphere into a medium in which the extracted uranium is infinitely dilute. Although not a completely accurate representation of the liquid-supercritical fluid system, the model is shown to be a reasonable representation and some conclusions discussed. |
| doi_str_mv | 10.1080/18811248.2001.9715050 |
| format | Article |
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Although not a completely accurate representation of the liquid-supercritical fluid system, the model is shown to be a reasonable representation and some conclusions discussed.</description><subject>Applied sciences</subject><subject>carbon dioxide</subject><subject>clean technology</subject><subject>Energy</subject><subject>Exact sciences and technology</subject><subject>extraction</subject><subject>Fuels</subject><subject>Nuclear fuels</subject><subject>Preparation and processing of nuclear fuels</subject><subject>processing</subject><subject>supercritical fluid</subject><subject>TBP</subject><subject>uranium</subject><subject>waste minimisation</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2001</creationdate><recordtype>article</recordtype><recordid>eNqNkE1LAzEQhoMoWKs_QdiDeNuaj83H3pRarVDxoD2HNJvYyO6mJlva_nuztAVP4mnIzPPOkAeAawRHCAp4h4RACBdihCFEo5IjCik8AYO-n_eDUzCAEOOcIILOwUWMX-nJCiYGYPrqK1PXrv3MvM26pckm2y4o3Tnf9p15UK1bN9nGdcvsfb0yQQfXOa3qbKzCIkGPzm9dZS7BmVV1NFeHOgTzp8nHeJrP3p5fxg-zXBOGYF6VFFVGaca5NqqwdmEpTRNccIwRLUtMlVCoZAJXFjJLoaUlVdhyxCApCjIEt_u9q-C_1yZ2snFRpy-o1vh1lJhxQXjJ_gVCXJIE0j2og48xGCtXwTUq7CSCshcsj4JlL1geBKfczeGAismHTaa0i7_CjBdQJOx-j7nW-tCojQ91JTu1q304Zsjfl34AVSSNCQ</recordid><startdate>20010601</startdate><enddate>20010601</enddate><creator>CLIFFORD, Anthony A.</creator><creator>ZHU, Shuang</creator><creator>SMART, Neil G.</creator><creator>LIN, Yuehe</creator><creator>WAI, Chien M.</creator><creator>YOSHIDA, Zenko</creator><creator>MEGURO, Yoshihiro</creator><creator>ISO, Shuichi</creator><general>Taylor & Francis Group</general><general>Atomic Energy Society of Japan</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>8BQ</scope><scope>8FD</scope><scope>JG9</scope><scope>7TB</scope><scope>FR3</scope></search><sort><creationdate>20010601</creationdate><title>Modelling of the Extraction of Uranium with Supercritical Carbon Dioxide</title><author>CLIFFORD, Anthony A. ; ZHU, Shuang ; SMART, Neil G. ; LIN, Yuehe ; WAI, Chien M. ; YOSHIDA, Zenko ; MEGURO, Yoshihiro ; ISO, Shuichi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c3610-d951deac677cea4ffbf5536124722159925a8a19682df06f50f595a2f71603443</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2001</creationdate><topic>Applied sciences</topic><topic>carbon dioxide</topic><topic>clean technology</topic><topic>Energy</topic><topic>Exact sciences and technology</topic><topic>extraction</topic><topic>Fuels</topic><topic>Nuclear fuels</topic><topic>Preparation and processing of nuclear fuels</topic><topic>processing</topic><topic>supercritical fluid</topic><topic>TBP</topic><topic>uranium</topic><topic>waste minimisation</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>CLIFFORD, Anthony A.</creatorcontrib><creatorcontrib>ZHU, Shuang</creatorcontrib><creatorcontrib>SMART, Neil G.</creatorcontrib><creatorcontrib>LIN, Yuehe</creatorcontrib><creatorcontrib>WAI, Chien M.</creatorcontrib><creatorcontrib>YOSHIDA, Zenko</creatorcontrib><creatorcontrib>MEGURO, Yoshihiro</creatorcontrib><creatorcontrib>ISO, Shuichi</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Materials Research Database</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Engineering Research Database</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>CLIFFORD, Anthony A.</au><au>ZHU, Shuang</au><au>SMART, Neil G.</au><au>LIN, Yuehe</au><au>WAI, Chien M.</au><au>YOSHIDA, Zenko</au><au>MEGURO, Yoshihiro</au><au>ISO, Shuichi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Modelling of the Extraction of Uranium with Supercritical Carbon Dioxide</atitle><jtitle>Journal of nuclear science and technology</jtitle><date>2001-06-01</date><risdate>2001</risdate><volume>38</volume><issue>6</issue><spage>433</spage><epage>438</epage><pages>433-438</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><coden>JNSTAX</coden><abstract>A model is presented for the analysis of the results of extraction of uranium in a flow system by supercritical fluid modified with tributylphosphate from a nitric acid matrix, in which the extraction is not limited by the solubility of the uranium species. The model used is that of diffusion out of a sphere into a medium in which the extracted uranium is infinitely dilute. Although not a completely accurate representation of the liquid-supercritical fluid system, the model is shown to be a reasonable representation and some conclusions discussed.</abstract><cop>Tokyo</cop><pub>Taylor & Francis Group</pub><doi>10.1080/18811248.2001.9715050</doi><tpages>6</tpages><oa>free_for_read</oa></addata></record> |
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| identifier | ISSN: 0022-3131 |
| ispartof | Journal of nuclear science and technology, 2001-06, Vol.38 (6), p.433-438 |
| issn | 0022-3131 1881-1248 |
| language | eng |
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| source | Elektronische Zeitschriftenbibliothek - Frei zugängliche E-Journals; Alma/SFX Local Collection; Free Full-Text Journals in Chemistry |
| subjects | Applied sciences carbon dioxide clean technology Energy Exact sciences and technology extraction Fuels Nuclear fuels Preparation and processing of nuclear fuels processing supercritical fluid TBP uranium waste minimisation |
| title | Modelling of the Extraction of Uranium with Supercritical Carbon Dioxide |
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