Recovering Uranium from Graphite Fuel Elements
S>A method for the recovery of uranium from high-density, graphitized uranium-graphite fuel elements was developed on a laboratory scale as a head-end treatment for tributyl phosphate solvent extraction processes. Simultaneous disintegration and leaching of the uranium occur when the fuel is cont...
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| Veröffentlicht in: | Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol 1961-04, Vol.53 (4), p.279-281 |
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| container_end_page | 281 |
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| container_issue | 4 |
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| container_title | Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol |
| container_volume | 53 |
| creator | Bradley, Mildred J Ferris, Leslie M |
| description | S>A method for the recovery of uranium from high-density, graphitized uranium-graphite fuel elements was developed on a laboratory scale as a head-end treatment for tributyl phosphate solvent extraction processes. Simultaneous disintegration and leaching of the uranium occur when the fuel is contacted with 90% HNO/sub 3/, either at room temperature or at the boiling point. More than 99.8% uranium was recovered when the fuel contained at least 5% (weight) uranium, but only 97% was recovered from fuel containing 0.7% (weight). Alternative techniques involve disintegration with bromine, ICl, or lBr prior to leaching with boiling 15.8M HNO/sub 3/. After bromine disintegration, 96 and 99.8% of the uranium were recovered from fuels containing 0.7 and 9% (weight) uranium, respectively. Both ICl and IBr were better disintegrating agents than bromine; however, uranium recovery after ICl disintegration was lower. (auth) |
| doi_str_mv | 10.1021/ie50616a022 |
| format | Article |
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Simultaneous disintegration and leaching of the uranium occur when the fuel is contacted with 90% HNO/sub 3/, either at room temperature or at the boiling point. More than 99.8% uranium was recovered when the fuel contained at least 5% (weight) uranium, but only 97% was recovered from fuel containing 0.7% (weight). Alternative techniques involve disintegration with bromine, ICl, or lBr prior to leaching with boiling 15.8M HNO/sub 3/. After bromine disintegration, 96 and 99.8% of the uranium were recovered from fuels containing 0.7 and 9% (weight) uranium, respectively. Both ICl and IBr were better disintegrating agents than bromine; however, uranium recovery after ICl disintegration was lower. 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Ind. Eng. Chem. Superseded by Chem. Technol</title><addtitle>Ind. Eng. Chem</addtitle><description>S>A method for the recovery of uranium from high-density, graphitized uranium-graphite fuel elements was developed on a laboratory scale as a head-end treatment for tributyl phosphate solvent extraction processes. Simultaneous disintegration and leaching of the uranium occur when the fuel is contacted with 90% HNO/sub 3/, either at room temperature or at the boiling point. More than 99.8% uranium was recovered when the fuel contained at least 5% (weight) uranium, but only 97% was recovered from fuel containing 0.7% (weight). Alternative techniques involve disintegration with bromine, ICl, or lBr prior to leaching with boiling 15.8M HNO/sub 3/. After bromine disintegration, 96 and 99.8% of the uranium were recovered from fuels containing 0.7 and 9% (weight) uranium, respectively. Both ICl and IBr were better disintegrating agents than bromine; however, uranium recovery after ICl disintegration was lower. (auth)</description><subject>BOILING</subject><subject>BROMINE</subject><subject>BUTYL PHOSPHATES</subject><subject>CHEMISTRY</subject><subject>FUEL ELEMENTS</subject><subject>FUELS</subject><subject>GRAPHITE</subject><subject>IODINE BROMIDES</subject><subject>IODINE CHLORIDES</subject><subject>LEACHING</subject><subject>NITRIC ACID</subject><subject>RECOVERY</subject><subject>SOLVENT EXTRACTION</subject><subject>TEMPERATURE</subject><subject>URANIUM</subject><subject>USES</subject><issn>0019-7866</issn><issn>1541-5724</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1961</creationdate><recordtype>article</recordtype><recordid>eNpt0E1LAzEQBuAgCtbqyT-wePEgWyeZ3SR7lNJWQfGj7Tmk2cRu7e6WZCv6742siAdPMwMPw8xLyDmFEQVGryubA6dcA2MHZEDzjKa5YNkhGQDQIhWS82NyEsImjjJnxYCMXqxp362vmtdk6XVT7evE-bZOZl7v1lVnk-nebpPJ1ta26cIpOXJ6G-zZTx2S5XSyGN-m94-zu_HNfaoRoUtXGkrmsMwBkEujMyu4KRAK6aTgWFK-kg7BWWQUY5Nrg9YZmZnScGQrHJKLfm8bukoFEw8xa9M2jTWdyoAzQIzoqkfGtyF469TOV7X2n4qC-s5D_ckj6rTXVejsxy_V_k1xgSJXi6e5Eg8Lkc1xrJ6jv-y9NkFt2r1v4sP_bv4CGEhsrA</recordid><startdate>19610401</startdate><enddate>19610401</enddate><creator>Bradley, Mildred J</creator><creator>Ferris, Leslie M</creator><general>American Chemical Society</general><scope>BSCLL</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>OTOTI</scope></search><sort><creationdate>19610401</creationdate><title>Recovering Uranium from Graphite Fuel Elements</title><author>Bradley, Mildred J ; Ferris, Leslie M</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-a330t-ba0d2f3d500368ca4e76c93098f8763d16b8f30fe3213f305ac3efc84cdc632b3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1961</creationdate><topic>BOILING</topic><topic>BROMINE</topic><topic>BUTYL PHOSPHATES</topic><topic>CHEMISTRY</topic><topic>FUEL ELEMENTS</topic><topic>FUELS</topic><topic>GRAPHITE</topic><topic>IODINE BROMIDES</topic><topic>IODINE CHLORIDES</topic><topic>LEACHING</topic><topic>NITRIC ACID</topic><topic>RECOVERY</topic><topic>SOLVENT EXTRACTION</topic><topic>TEMPERATURE</topic><topic>URANIUM</topic><topic>USES</topic><toplevel>online_resources</toplevel><creatorcontrib>Bradley, Mildred J</creatorcontrib><creatorcontrib>Ferris, Leslie M</creatorcontrib><creatorcontrib>Oak Ridge National Lab., Tenn</creatorcontrib><collection>Istex</collection><collection>CrossRef</collection><collection>OSTI.GOV</collection><jtitle>Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Bradley, Mildred J</au><au>Ferris, Leslie M</au><aucorp>Oak Ridge National Lab., Tenn</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Recovering Uranium from Graphite Fuel Elements</atitle><jtitle>Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol</jtitle><addtitle>Ind. Eng. Chem</addtitle><date>1961-04-01</date><risdate>1961</risdate><volume>53</volume><issue>4</issue><spage>279</spage><epage>281</epage><pages>279-281</pages><issn>0019-7866</issn><eissn>1541-5724</eissn><abstract>S>A method for the recovery of uranium from high-density, graphitized uranium-graphite fuel elements was developed on a laboratory scale as a head-end treatment for tributyl phosphate solvent extraction processes. Simultaneous disintegration and leaching of the uranium occur when the fuel is contacted with 90% HNO/sub 3/, either at room temperature or at the boiling point. More than 99.8% uranium was recovered when the fuel contained at least 5% (weight) uranium, but only 97% was recovered from fuel containing 0.7% (weight). Alternative techniques involve disintegration with bromine, ICl, or lBr prior to leaching with boiling 15.8M HNO/sub 3/. After bromine disintegration, 96 and 99.8% of the uranium were recovered from fuels containing 0.7 and 9% (weight) uranium, respectively. Both ICl and IBr were better disintegrating agents than bromine; however, uranium recovery after ICl disintegration was lower. (auth)</abstract><pub>American Chemical Society</pub><doi>10.1021/ie50616a022</doi><tpages>3</tpages></addata></record> |
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| identifier | ISSN: 0019-7866 |
| ispartof | Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol, 1961-04, Vol.53 (4), p.279-281 |
| issn | 0019-7866 1541-5724 |
| language | eng |
| recordid | cdi_crossref_primary_10_1021_ie50616a022 |
| source | American Chemical Society Journals |
| subjects | BOILING BROMINE BUTYL PHOSPHATES CHEMISTRY FUEL ELEMENTS FUELS GRAPHITE IODINE BROMIDES IODINE CHLORIDES LEACHING NITRIC ACID RECOVERY SOLVENT EXTRACTION TEMPERATURE URANIUM USES |
| title | Recovering Uranium from Graphite Fuel Elements |
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