Electrochemical recovery of plutonium from aqueous carbonate waste solutions
Recovery of plutonium from aqueous carbonate waste solutions generated during the reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and the remediation of radioactive waste. Reported methods proceed through secondary waste generation caused by acidificatio...
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| Veröffentlicht in: | Chemical communications (Cambridge, England) England), 2022-01, Vol.58 (8), p.1111-1114 |
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| container_title | Chemical communications (Cambridge, England) |
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| creator | Agarwal, Rahul Dumpala, Rama Mohana Rao Sharma, Manoj K Noronha, Donald M Gamare, Jayashree S Jayachandran, Kavitha Nandi, Chiranjit Kaity, Santu |
| description | Recovery of plutonium from aqueous carbonate waste solutions generated during the reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and the remediation of radioactive waste. Reported methods proceed through secondary waste generation caused by acidification of carbonate waste and make the recovery process cumbersome. Herein, we report a simple method for the recovery of Pu as solid PuO
2
powder from carbonate waste solution in a two-step process. (i) Pu was selectively electrochemically precipitated as plutonium-hydroxide in the presence of interfering U, Th, Ru, Zr, Nb, Cs and the degradation products of tri-butyl phosphate by bulk electrolysis at −0.9 V using a Pt gauze electrode and (ii) the precipitate was annealed at 973 K for conversion to pure PuO
2
powder. The present approach is simple, avoids the generation of secondary waste and reduces the exposure of working personnel to radiation.
A simple method was developed for the electrochemical recovery of Pu as pure PuO
2
powder in the presence of different interfering ions and radiolytic and hydrolytic degradation products of TBP in a carbonate medium. |
| doi_str_mv | 10.1039/d1cc06603j |
| format | Article |
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2
powder from carbonate waste solution in a two-step process. (i) Pu was selectively electrochemically precipitated as plutonium-hydroxide in the presence of interfering U, Th, Ru, Zr, Nb, Cs and the degradation products of tri-butyl phosphate by bulk electrolysis at −0.9 V using a Pt gauze electrode and (ii) the precipitate was annealed at 973 K for conversion to pure PuO
2
powder. The present approach is simple, avoids the generation of secondary waste and reduces the exposure of working personnel to radiation.
A simple method was developed for the electrochemical recovery of Pu as pure PuO
2
powder in the presence of different interfering ions and radiolytic and hydrolytic degradation products of TBP in a carbonate medium.</description><identifier>ISSN: 1359-7345</identifier><identifier>EISSN: 1364-548X</identifier><identifier>DOI: 10.1039/d1cc06603j</identifier><identifier>PMID: 34979537</identifier><language>eng</language><publisher>England: Royal Society of Chemistry</publisher><subject>Acidification ; Electrolysis ; Gauze ; Nuclear fuel reprocessing ; Nuclear reactors ; Plutonium ; Plutonium dioxide ; Radioactive wastes ; Spent nuclear fuels ; Zirconium</subject><ispartof>Chemical communications (Cambridge, England), 2022-01, Vol.58 (8), p.1111-1114</ispartof><rights>Copyright Royal Society of Chemistry 2022</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-6966a6761587c9bec2ecd9fb536414338124abce4742fa86cb1ac1eb21acee803</citedby><cites>FETCH-LOGICAL-c337t-6966a6761587c9bec2ecd9fb536414338124abce4742fa86cb1ac1eb21acee803</cites><orcidid>0000-0003-1785-6959 ; 0000-0003-3891-7001</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/34979537$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Agarwal, Rahul</creatorcontrib><creatorcontrib>Dumpala, Rama Mohana Rao</creatorcontrib><creatorcontrib>Sharma, Manoj K</creatorcontrib><creatorcontrib>Noronha, Donald M</creatorcontrib><creatorcontrib>Gamare, Jayashree S</creatorcontrib><creatorcontrib>Jayachandran, Kavitha</creatorcontrib><creatorcontrib>Nandi, Chiranjit</creatorcontrib><creatorcontrib>Kaity, Santu</creatorcontrib><title>Electrochemical recovery of plutonium from aqueous carbonate waste solutions</title><title>Chemical communications (Cambridge, England)</title><addtitle>Chem Commun (Camb)</addtitle><description>Recovery of plutonium from aqueous carbonate waste solutions generated during the reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and the remediation of radioactive waste. Reported methods proceed through secondary waste generation caused by acidification of carbonate waste and make the recovery process cumbersome. Herein, we report a simple method for the recovery of Pu as solid PuO
2
powder from carbonate waste solution in a two-step process. (i) Pu was selectively electrochemically precipitated as plutonium-hydroxide in the presence of interfering U, Th, Ru, Zr, Nb, Cs and the degradation products of tri-butyl phosphate by bulk electrolysis at −0.9 V using a Pt gauze electrode and (ii) the precipitate was annealed at 973 K for conversion to pure PuO
2
powder. The present approach is simple, avoids the generation of secondary waste and reduces the exposure of working personnel to radiation.
A simple method was developed for the electrochemical recovery of Pu as pure PuO
2
powder in the presence of different interfering ions and radiolytic and hydrolytic degradation products of TBP in a carbonate medium.</description><subject>Acidification</subject><subject>Electrolysis</subject><subject>Gauze</subject><subject>Nuclear fuel reprocessing</subject><subject>Nuclear reactors</subject><subject>Plutonium</subject><subject>Plutonium dioxide</subject><subject>Radioactive wastes</subject><subject>Spent nuclear fuels</subject><subject>Zirconium</subject><issn>1359-7345</issn><issn>1364-548X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><recordid>eNpd0c1LwzAYBvAgipvTi3el4EWEatKkaXocdX4x8KLgraTv3mJH28ykVfbfm7o5wRySQH68PDwh5JTRa0Z5erNgAFRKypd7ZMy4FGEs1Nv-cI_TMOEiHpEj55bULxarQzLiIk3SmCdjMp_VCJ018I5NBboOLIL5RLsOTBms6r4zbdU3QWlNE-iPHk3vAtC2MK3uMPjSzu_OeFeZ1h2Tg1LXDk-254S83s1esodw_nz_mE3nIXCedKFMpdQykT5LAmmBECEs0rKIfXQmOFcsEroAFImISq0kFEwDwyLyB6KifEIuN3NX1vhMrsubygHWtW6HgHkkma-DKq48vfhHl6a3rU_nVTRAxiOvrjYKrHHOYpmvbNVou84ZzYeO81uWZT8dP3l8vh3ZFw0udvS3VA_ONsA62L3-fRL_BhuBgSg</recordid><startdate>20220125</startdate><enddate>20220125</enddate><creator>Agarwal, Rahul</creator><creator>Dumpala, Rama Mohana Rao</creator><creator>Sharma, Manoj K</creator><creator>Noronha, Donald M</creator><creator>Gamare, Jayashree S</creator><creator>Jayachandran, Kavitha</creator><creator>Nandi, Chiranjit</creator><creator>Kaity, Santu</creator><general>Royal Society of Chemistry</general><scope>NPM</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>JG9</scope><scope>L7M</scope><scope>7X8</scope><orcidid>https://orcid.org/0000-0003-1785-6959</orcidid><orcidid>https://orcid.org/0000-0003-3891-7001</orcidid></search><sort><creationdate>20220125</creationdate><title>Electrochemical recovery of plutonium from aqueous carbonate waste solutions</title><author>Agarwal, Rahul ; Dumpala, Rama Mohana Rao ; Sharma, Manoj K ; Noronha, Donald M ; Gamare, Jayashree S ; Jayachandran, Kavitha ; Nandi, Chiranjit ; Kaity, Santu</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c337t-6966a6761587c9bec2ecd9fb536414338124abce4742fa86cb1ac1eb21acee803</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>Acidification</topic><topic>Electrolysis</topic><topic>Gauze</topic><topic>Nuclear fuel reprocessing</topic><topic>Nuclear reactors</topic><topic>Plutonium</topic><topic>Plutonium dioxide</topic><topic>Radioactive wastes</topic><topic>Spent nuclear fuels</topic><topic>Zirconium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Agarwal, Rahul</creatorcontrib><creatorcontrib>Dumpala, Rama Mohana Rao</creatorcontrib><creatorcontrib>Sharma, Manoj K</creatorcontrib><creatorcontrib>Noronha, Donald M</creatorcontrib><creatorcontrib>Gamare, Jayashree S</creatorcontrib><creatorcontrib>Jayachandran, Kavitha</creatorcontrib><creatorcontrib>Nandi, Chiranjit</creatorcontrib><creatorcontrib>Kaity, Santu</creatorcontrib><collection>PubMed</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>MEDLINE - Academic</collection><jtitle>Chemical communications (Cambridge, England)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Agarwal, Rahul</au><au>Dumpala, Rama Mohana Rao</au><au>Sharma, Manoj K</au><au>Noronha, Donald M</au><au>Gamare, Jayashree S</au><au>Jayachandran, Kavitha</au><au>Nandi, Chiranjit</au><au>Kaity, Santu</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Electrochemical recovery of plutonium from aqueous carbonate waste solutions</atitle><jtitle>Chemical communications (Cambridge, England)</jtitle><addtitle>Chem Commun (Camb)</addtitle><date>2022-01-25</date><risdate>2022</risdate><volume>58</volume><issue>8</issue><spage>1111</spage><epage>1114</epage><pages>1111-1114</pages><issn>1359-7345</issn><eissn>1364-548X</eissn><abstract>Recovery of plutonium from aqueous carbonate waste solutions generated during the reprocessing of spent nuclear fuel is a key concern for sustainable nuclear energy programmes and the remediation of radioactive waste. Reported methods proceed through secondary waste generation caused by acidification of carbonate waste and make the recovery process cumbersome. Herein, we report a simple method for the recovery of Pu as solid PuO
2
powder from carbonate waste solution in a two-step process. (i) Pu was selectively electrochemically precipitated as plutonium-hydroxide in the presence of interfering U, Th, Ru, Zr, Nb, Cs and the degradation products of tri-butyl phosphate by bulk electrolysis at −0.9 V using a Pt gauze electrode and (ii) the precipitate was annealed at 973 K for conversion to pure PuO
2
powder. The present approach is simple, avoids the generation of secondary waste and reduces the exposure of working personnel to radiation.
A simple method was developed for the electrochemical recovery of Pu as pure PuO
2
powder in the presence of different interfering ions and radiolytic and hydrolytic degradation products of TBP in a carbonate medium.</abstract><cop>England</cop><pub>Royal Society of Chemistry</pub><pmid>34979537</pmid><doi>10.1039/d1cc06603j</doi><tpages>4</tpages><orcidid>https://orcid.org/0000-0003-1785-6959</orcidid><orcidid>https://orcid.org/0000-0003-3891-7001</orcidid></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 1359-7345 |
| ispartof | Chemical communications (Cambridge, England), 2022-01, Vol.58 (8), p.1111-1114 |
| issn | 1359-7345 1364-548X |
| language | eng |
| recordid | cdi_proquest_miscellaneous_2616600838 |
| source | Royal Society Of Chemistry Journals 2008-; Alma/SFX Local Collection |
| subjects | Acidification Electrolysis Gauze Nuclear fuel reprocessing Nuclear reactors Plutonium Plutonium dioxide Radioactive wastes Spent nuclear fuels Zirconium |
| title | Electrochemical recovery of plutonium from aqueous carbonate waste solutions |
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