Cesium extraction from simulated high-level vitrified wastes
A phase separation technique was applied to a simulated high-level vitrified waste, which consisted of nonradioactive elements, to determine the efficient extraction of cesium from the vitrified material. Experimentally, the simulated vitrified material was melted at 900–1000 °C and subsequently ann...
Gespeichert in:
Veröffentlicht in: | Progress in nuclear energy (New series) 2018-09, Vol.108, p.34-42 |
---|---|
Hauptverfasser: | , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
container_end_page | 42 |
---|---|
container_issue | |
container_start_page | 34 |
container_title | Progress in nuclear energy (New series) |
container_volume | 108 |
creator | Xu, Zhanglian Okada, Takashi Yonezawa, Susumu |
description | A phase separation technique was applied to a simulated high-level vitrified waste, which consisted of nonradioactive elements, to determine the efficient extraction of cesium from the vitrified material. Experimentally, the simulated vitrified material was melted at 900–1000 °C and subsequently annealed at 700 °C under the reductive atmosphere. The sodium-potassium-rich materials were found to be phase-separated on the glass surface that was in contact with the gas phase, which enhanced the leachability of cesium in the glass. Such phase separation was not observed under other atmospheres (a CO2-rich or air atmosphere), thus elucidating the effect of the reductive atmosphere. The glass was converted to particles with higher surface area through a dropping test of the molten glass in the melting stage, and the sodium-potassium-rich materials, subsequently, were more effectively phase-separated on the surfaces. During water leaching, 70–90% of the total cesium was extracted from the particles.
•Na-K-rich materials can be separated from a simulated high-level vitrified waste.•Such phase separation occurred during heat treatment under a reductive atmosphere.•Leachability of Cs in the vitrified material was enhanced by the phase separation.•Cs extraction success from the heat-treated product was between 70 and 90%. |
doi_str_mv | 10.1016/j.pnucene.2018.05.008 |
format | Article |
fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_journals_2113602663</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0149197018301331</els_id><sourcerecordid>2113602663</sourcerecordid><originalsourceid>FETCH-LOGICAL-c403t-29d25b5fbac9a259f10deac20d18abdf9c78c86a042bd49cc4abe346563178163</originalsourceid><addsrcrecordid>eNqFkEtLxDAUhYMoOI7-BKHguvUmTdoUBJHBFwy40XVIk1snpY8xSUf993aY2bs6cDnnXM5HyDWFjAItbttsO0wGB8wYUJmByADkCVlQWcqUM8ZPyQIor1JalXBOLkJoAWhJhViQuxUGN_UJ_kSvTXTjkDR-7JPg-qnTEW2ycZ-btMMddsnORe8aNx-_dYgYLslZo7uAV0ddko-nx_fVS7p-e35dPaxTwyGPKassE7Voam0qzUTVULCoDQNLpa5tU5lSGllo4Ky2vDKG6xpzXogip6WkRb4kN4ferR-_JgxRtePkh_mlYpTmBbCiyGeXOLiMH0Pw2Kitd732v4qC2oNSrTqCUntQCoSaQc25-0MO5wk7h14F43AwaJ1HE5Ud3T8NfwcrdJI</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2113602663</pqid></control><display><type>article</type><title>Cesium extraction from simulated high-level vitrified wastes</title><source>Elsevier ScienceDirect Journals</source><creator>Xu, Zhanglian ; Okada, Takashi ; Yonezawa, Susumu</creator><creatorcontrib>Xu, Zhanglian ; Okada, Takashi ; Yonezawa, Susumu</creatorcontrib><description>A phase separation technique was applied to a simulated high-level vitrified waste, which consisted of nonradioactive elements, to determine the efficient extraction of cesium from the vitrified material. Experimentally, the simulated vitrified material was melted at 900–1000 °C and subsequently annealed at 700 °C under the reductive atmosphere. The sodium-potassium-rich materials were found to be phase-separated on the glass surface that was in contact with the gas phase, which enhanced the leachability of cesium in the glass. Such phase separation was not observed under other atmospheres (a CO2-rich or air atmosphere), thus elucidating the effect of the reductive atmosphere. The glass was converted to particles with higher surface area through a dropping test of the molten glass in the melting stage, and the sodium-potassium-rich materials, subsequently, were more effectively phase-separated on the surfaces. During water leaching, 70–90% of the total cesium was extracted from the particles.
•Na-K-rich materials can be separated from a simulated high-level vitrified waste.•Such phase separation occurred during heat treatment under a reductive atmosphere.•Leachability of Cs in the vitrified material was enhanced by the phase separation.•Cs extraction success from the heat-treated product was between 70 and 90%.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2018.05.008</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Annealing ; Atmosphere ; Cesium ; Chemical elements ; Extraction ; Extraction processes ; Glass ; High-level vitrified waste ; Leaching ; Level (quantity) ; Phase separation ; Potassium ; Radioactive nuclides ; Simulation</subject><ispartof>Progress in nuclear energy (New series), 2018-09, Vol.108, p.34-42</ispartof><rights>2018 Elsevier Ltd</rights><rights>Copyright Elsevier BV Sep 2018</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c403t-29d25b5fbac9a259f10deac20d18abdf9c78c86a042bd49cc4abe346563178163</citedby><cites>FETCH-LOGICAL-c403t-29d25b5fbac9a259f10deac20d18abdf9c78c86a042bd49cc4abe346563178163</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0149197018301331$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27901,27902,65306</link.rule.ids></links><search><creatorcontrib>Xu, Zhanglian</creatorcontrib><creatorcontrib>Okada, Takashi</creatorcontrib><creatorcontrib>Yonezawa, Susumu</creatorcontrib><title>Cesium extraction from simulated high-level vitrified wastes</title><title>Progress in nuclear energy (New series)</title><description>A phase separation technique was applied to a simulated high-level vitrified waste, which consisted of nonradioactive elements, to determine the efficient extraction of cesium from the vitrified material. Experimentally, the simulated vitrified material was melted at 900–1000 °C and subsequently annealed at 700 °C under the reductive atmosphere. The sodium-potassium-rich materials were found to be phase-separated on the glass surface that was in contact with the gas phase, which enhanced the leachability of cesium in the glass. Such phase separation was not observed under other atmospheres (a CO2-rich or air atmosphere), thus elucidating the effect of the reductive atmosphere. The glass was converted to particles with higher surface area through a dropping test of the molten glass in the melting stage, and the sodium-potassium-rich materials, subsequently, were more effectively phase-separated on the surfaces. During water leaching, 70–90% of the total cesium was extracted from the particles.
•Na-K-rich materials can be separated from a simulated high-level vitrified waste.•Such phase separation occurred during heat treatment under a reductive atmosphere.•Leachability of Cs in the vitrified material was enhanced by the phase separation.•Cs extraction success from the heat-treated product was between 70 and 90%.</description><subject>Annealing</subject><subject>Atmosphere</subject><subject>Cesium</subject><subject>Chemical elements</subject><subject>Extraction</subject><subject>Extraction processes</subject><subject>Glass</subject><subject>High-level vitrified waste</subject><subject>Leaching</subject><subject>Level (quantity)</subject><subject>Phase separation</subject><subject>Potassium</subject><subject>Radioactive nuclides</subject><subject>Simulation</subject><issn>0149-1970</issn><issn>1878-4224</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLxDAUhYMoOI7-BKHguvUmTdoUBJHBFwy40XVIk1snpY8xSUf993aY2bs6cDnnXM5HyDWFjAItbttsO0wGB8wYUJmByADkCVlQWcqUM8ZPyQIor1JalXBOLkJoAWhJhViQuxUGN_UJ_kSvTXTjkDR-7JPg-qnTEW2ycZ-btMMddsnORe8aNx-_dYgYLslZo7uAV0ddko-nx_fVS7p-e35dPaxTwyGPKassE7Voam0qzUTVULCoDQNLpa5tU5lSGllo4Ky2vDKG6xpzXogip6WkRb4kN4ferR-_JgxRtePkh_mlYpTmBbCiyGeXOLiMH0Pw2Kitd732v4qC2oNSrTqCUntQCoSaQc25-0MO5wk7h14F43AwaJ1HE5Ud3T8NfwcrdJI</recordid><startdate>201809</startdate><enddate>201809</enddate><creator>Xu, Zhanglian</creator><creator>Okada, Takashi</creator><creator>Yonezawa, Susumu</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>201809</creationdate><title>Cesium extraction from simulated high-level vitrified wastes</title><author>Xu, Zhanglian ; Okada, Takashi ; Yonezawa, Susumu</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c403t-29d25b5fbac9a259f10deac20d18abdf9c78c86a042bd49cc4abe346563178163</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Annealing</topic><topic>Atmosphere</topic><topic>Cesium</topic><topic>Chemical elements</topic><topic>Extraction</topic><topic>Extraction processes</topic><topic>Glass</topic><topic>High-level vitrified waste</topic><topic>Leaching</topic><topic>Level (quantity)</topic><topic>Phase separation</topic><topic>Potassium</topic><topic>Radioactive nuclides</topic><topic>Simulation</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Xu, Zhanglian</creatorcontrib><creatorcontrib>Okada, Takashi</creatorcontrib><creatorcontrib>Yonezawa, Susumu</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Progress in nuclear energy (New series)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Xu, Zhanglian</au><au>Okada, Takashi</au><au>Yonezawa, Susumu</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Cesium extraction from simulated high-level vitrified wastes</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2018-09</date><risdate>2018</risdate><volume>108</volume><spage>34</spage><epage>42</epage><pages>34-42</pages><issn>0149-1970</issn><eissn>1878-4224</eissn><abstract>A phase separation technique was applied to a simulated high-level vitrified waste, which consisted of nonradioactive elements, to determine the efficient extraction of cesium from the vitrified material. Experimentally, the simulated vitrified material was melted at 900–1000 °C and subsequently annealed at 700 °C under the reductive atmosphere. The sodium-potassium-rich materials were found to be phase-separated on the glass surface that was in contact with the gas phase, which enhanced the leachability of cesium in the glass. Such phase separation was not observed under other atmospheres (a CO2-rich or air atmosphere), thus elucidating the effect of the reductive atmosphere. The glass was converted to particles with higher surface area through a dropping test of the molten glass in the melting stage, and the sodium-potassium-rich materials, subsequently, were more effectively phase-separated on the surfaces. During water leaching, 70–90% of the total cesium was extracted from the particles.
•Na-K-rich materials can be separated from a simulated high-level vitrified waste.•Such phase separation occurred during heat treatment under a reductive atmosphere.•Leachability of Cs in the vitrified material was enhanced by the phase separation.•Cs extraction success from the heat-treated product was between 70 and 90%.</abstract><cop>Oxford</cop><pub>Elsevier Ltd</pub><doi>10.1016/j.pnucene.2018.05.008</doi><tpages>9</tpages></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0149-1970 |
ispartof | Progress in nuclear energy (New series), 2018-09, Vol.108, p.34-42 |
issn | 0149-1970 1878-4224 |
language | eng |
recordid | cdi_proquest_journals_2113602663 |
source | Elsevier ScienceDirect Journals |
subjects | Annealing Atmosphere Cesium Chemical elements Extraction Extraction processes Glass High-level vitrified waste Leaching Level (quantity) Phase separation Potassium Radioactive nuclides Simulation |
title | Cesium extraction from simulated high-level vitrified wastes |
url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-02-05T13%3A53%3A48IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Cesium%20extraction%20from%20simulated%20high-level%20vitrified%20wastes&rft.jtitle=Progress%20in%20nuclear%20energy%20(New%20series)&rft.au=Xu,%20Zhanglian&rft.date=2018-09&rft.volume=108&rft.spage=34&rft.epage=42&rft.pages=34-42&rft.issn=0149-1970&rft.eissn=1878-4224&rft_id=info:doi/10.1016/j.pnucene.2018.05.008&rft_dat=%3Cproquest_cross%3E2113602663%3C/proquest_cross%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2113602663&rft_id=info:pmid/&rft_els_id=S0149197018301331&rfr_iscdi=true |