Loading…

Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current

The study presents the results of deep decontamination of the spent ion-exchange resin from the Kursk NPP, where the task of processing and conditioning of the resin is still not solved. The article shows that decontamination of the resin under dynamic conditions with a solution of the composition N...

Full description

Saved in:
Bibliographic Details
Published in:Journal of cleaner production 2024-04, Vol.449, p.141658, Article 141658
Main Authors: Matskevich, A.I., Markin, N.S., Palamarchuk, M.S., Tokar’, E.A., Egorin, A.M.
Format: Article
Language:English
Subjects:
Citations: Items that this one cites
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
cited_by
cites cdi_FETCH-LOGICAL-c257t-6f727ddf6919571d802a963c26849f5a54fb0f54217eb06bc3189085accb95783
container_end_page
container_issue
container_start_page 141658
container_title Journal of cleaner production
container_volume 449
creator Matskevich, A.I.
Markin, N.S.
Palamarchuk, M.S.
Tokar’, E.A.
Egorin, A.M.
description The study presents the results of deep decontamination of the spent ion-exchange resin from the Kursk NPP, where the task of processing and conditioning of the resin is still not solved. The article shows that decontamination of the resin under dynamic conditions with a solution of the composition NaOH – 0.75 mol L−1, NaNO3 – 2.25 mol L−1 reduces its activity by 1 order of magnitude due to removal of Cs-137 (by washing). The subsequent washing of the resin with a solution of H2SO4 – 1.0 mol L−1, FeSO4 – 0.5 mol L−1 results in a decrease of its activity by another 1 order of magnitude due to removal of Eu-152-154 (100%) and partial removal of Co-60 (90%) and Am-241 (92%). It was found that further attempts to reduce the activity of the resin were ineffective due to the presence of insoluble precipitates, whose activity was mainly (more than 98%) accounted for by Co-60 (30.2%) and Nb-94 (68.1%) radionuclides. To remove these poorly soluble precipitates, we suggested decontamination by direct current through placing the resin between an anode and a cathode. A solution of H2SO4 of a concentration of 0.1 mol L−1 was used as an electrolyte. It has been found that an addition of FeSO4 (0.009 mol L−1) increases the rate of precipitate removal more than 1.5-fold. During the treatment by electric current, particles are mechanically removed, whereas insignificant amounts of Cs-137 and Co-60 (no more than 2.6%) enter the electrolyte. After the treatment and washing the resin with a NaNO3 solution, its activity decreases by another three orders of magnitude. The resulting activity of the resin was 350 Bq kg−1, which made it possible to classify it as industrial waste. [Display omitted]
doi_str_mv 10.1016/j.jclepro.2024.141658
format article
fullrecord <record><control><sourceid>elsevier_cross</sourceid><recordid>TN_cdi_crossref_primary_10_1016_j_jclepro_2024_141658</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0959652624011065</els_id><sourcerecordid>S0959652624011065</sourcerecordid><originalsourceid>FETCH-LOGICAL-c257t-6f727ddf6919571d802a963c26849f5a54fb0f54217eb06bc3189085accb95783</originalsourceid><addsrcrecordid>eNqFkM1OwzAQhC0EEqXwCEh-gQQ7je34hFD5lSpxgbPlOOvWUeJUdoIoT4-r9MSF02qknZndD6FbSnJKKL9r89Z0sA9DXpCizGlJOavO0IJWQmZUVPwcLYhkMuOs4JfoKsaWECqIKBfo5xHM4EfdO69HN3g8WBz34EecRAbfZqf9FnCA6HzENgw9HneA_ZQadcB2gg6bQxJ4ShtbbHbQO6M73PzJ1b7BjQtgRmymEFLDNbqwuotwc5pL9Pn89LF-zTbvL2_rh01mCibGjFtRiKaxXFLJBG0qUmjJV6bgVSkt06y0NbGsLKiAmvDarGglScW0MXUyVKslYnOuCUOMAazaB9frcFCUqCNA1aoTQHUEqGaAyXc_-yAd9-UgqGgceAPzG6oZ3D8Jv6JCfuQ</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current</title><source>ScienceDirect Freedom Collection</source><creator>Matskevich, A.I. ; Markin, N.S. ; Palamarchuk, M.S. ; Tokar’, E.A. ; Egorin, A.M.</creator><creatorcontrib>Matskevich, A.I. ; Markin, N.S. ; Palamarchuk, M.S. ; Tokar’, E.A. ; Egorin, A.M.</creatorcontrib><description>The study presents the results of deep decontamination of the spent ion-exchange resin from the Kursk NPP, where the task of processing and conditioning of the resin is still not solved. The article shows that decontamination of the resin under dynamic conditions with a solution of the composition NaOH – 0.75 mol L−1, NaNO3 – 2.25 mol L−1 reduces its activity by 1 order of magnitude due to removal of Cs-137 (by washing). The subsequent washing of the resin with a solution of H2SO4 – 1.0 mol L−1, FeSO4 – 0.5 mol L−1 results in a decrease of its activity by another 1 order of magnitude due to removal of Eu-152-154 (100%) and partial removal of Co-60 (90%) and Am-241 (92%). It was found that further attempts to reduce the activity of the resin were ineffective due to the presence of insoluble precipitates, whose activity was mainly (more than 98%) accounted for by Co-60 (30.2%) and Nb-94 (68.1%) radionuclides. To remove these poorly soluble precipitates, we suggested decontamination by direct current through placing the resin between an anode and a cathode. A solution of H2SO4 of a concentration of 0.1 mol L−1 was used as an electrolyte. It has been found that an addition of FeSO4 (0.009 mol L−1) increases the rate of precipitate removal more than 1.5-fold. During the treatment by electric current, particles are mechanically removed, whereas insignificant amounts of Cs-137 and Co-60 (no more than 2.6%) enter the electrolyte. After the treatment and washing the resin with a NaNO3 solution, its activity decreases by another three orders of magnitude. The resulting activity of the resin was 350 Bq kg−1, which made it possible to classify it as industrial waste. [Display omitted]</description><identifier>ISSN: 0959-6526</identifier><identifier>EISSN: 1879-1786</identifier><identifier>DOI: 10.1016/j.jclepro.2024.141658</identifier><language>eng</language><publisher>Elsevier Ltd</publisher><subject>chemical decontamination ; Deep decontamination ; Direct current ; Nuclear fuel cycle ; Spent ion-exchange resins</subject><ispartof>Journal of cleaner production, 2024-04, Vol.449, p.141658, Article 141658</ispartof><rights>2024 Elsevier Ltd</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c257t-6f727ddf6919571d802a963c26849f5a54fb0f54217eb06bc3189085accb95783</cites><orcidid>0000-0001-6833-0418 ; 0000-0001-8974-2235</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></links><search><creatorcontrib>Matskevich, A.I.</creatorcontrib><creatorcontrib>Markin, N.S.</creatorcontrib><creatorcontrib>Palamarchuk, M.S.</creatorcontrib><creatorcontrib>Tokar’, E.A.</creatorcontrib><creatorcontrib>Egorin, A.M.</creatorcontrib><title>Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current</title><title>Journal of cleaner production</title><description>The study presents the results of deep decontamination of the spent ion-exchange resin from the Kursk NPP, where the task of processing and conditioning of the resin is still not solved. The article shows that decontamination of the resin under dynamic conditions with a solution of the composition NaOH – 0.75 mol L−1, NaNO3 – 2.25 mol L−1 reduces its activity by 1 order of magnitude due to removal of Cs-137 (by washing). The subsequent washing of the resin with a solution of H2SO4 – 1.0 mol L−1, FeSO4 – 0.5 mol L−1 results in a decrease of its activity by another 1 order of magnitude due to removal of Eu-152-154 (100%) and partial removal of Co-60 (90%) and Am-241 (92%). It was found that further attempts to reduce the activity of the resin were ineffective due to the presence of insoluble precipitates, whose activity was mainly (more than 98%) accounted for by Co-60 (30.2%) and Nb-94 (68.1%) radionuclides. To remove these poorly soluble precipitates, we suggested decontamination by direct current through placing the resin between an anode and a cathode. A solution of H2SO4 of a concentration of 0.1 mol L−1 was used as an electrolyte. It has been found that an addition of FeSO4 (0.009 mol L−1) increases the rate of precipitate removal more than 1.5-fold. During the treatment by electric current, particles are mechanically removed, whereas insignificant amounts of Cs-137 and Co-60 (no more than 2.6%) enter the electrolyte. After the treatment and washing the resin with a NaNO3 solution, its activity decreases by another three orders of magnitude. The resulting activity of the resin was 350 Bq kg−1, which made it possible to classify it as industrial waste. [Display omitted]</description><subject>chemical decontamination</subject><subject>Deep decontamination</subject><subject>Direct current</subject><subject>Nuclear fuel cycle</subject><subject>Spent ion-exchange resins</subject><issn>0959-6526</issn><issn>1879-1786</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><recordid>eNqFkM1OwzAQhC0EEqXwCEh-gQQ7je34hFD5lSpxgbPlOOvWUeJUdoIoT4-r9MSF02qknZndD6FbSnJKKL9r89Z0sA9DXpCizGlJOavO0IJWQmZUVPwcLYhkMuOs4JfoKsaWECqIKBfo5xHM4EfdO69HN3g8WBz34EecRAbfZqf9FnCA6HzENgw9HneA_ZQadcB2gg6bQxJ4ShtbbHbQO6M73PzJ1b7BjQtgRmymEFLDNbqwuotwc5pL9Pn89LF-zTbvL2_rh01mCibGjFtRiKaxXFLJBG0qUmjJV6bgVSkt06y0NbGsLKiAmvDarGglScW0MXUyVKslYnOuCUOMAazaB9frcFCUqCNA1aoTQHUEqGaAyXc_-yAd9-UgqGgceAPzG6oZ3D8Jv6JCfuQ</recordid><startdate>20240410</startdate><enddate>20240410</enddate><creator>Matskevich, A.I.</creator><creator>Markin, N.S.</creator><creator>Palamarchuk, M.S.</creator><creator>Tokar’, E.A.</creator><creator>Egorin, A.M.</creator><general>Elsevier Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><orcidid>https://orcid.org/0000-0001-6833-0418</orcidid><orcidid>https://orcid.org/0000-0001-8974-2235</orcidid></search><sort><creationdate>20240410</creationdate><title>Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current</title><author>Matskevich, A.I. ; Markin, N.S. ; Palamarchuk, M.S. ; Tokar’, E.A. ; Egorin, A.M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c257t-6f727ddf6919571d802a963c26849f5a54fb0f54217eb06bc3189085accb95783</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><topic>chemical decontamination</topic><topic>Deep decontamination</topic><topic>Direct current</topic><topic>Nuclear fuel cycle</topic><topic>Spent ion-exchange resins</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Matskevich, A.I.</creatorcontrib><creatorcontrib>Markin, N.S.</creatorcontrib><creatorcontrib>Palamarchuk, M.S.</creatorcontrib><creatorcontrib>Tokar’, E.A.</creatorcontrib><creatorcontrib>Egorin, A.M.</creatorcontrib><collection>CrossRef</collection><jtitle>Journal of cleaner production</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Matskevich, A.I.</au><au>Markin, N.S.</au><au>Palamarchuk, M.S.</au><au>Tokar’, E.A.</au><au>Egorin, A.M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current</atitle><jtitle>Journal of cleaner production</jtitle><date>2024-04-10</date><risdate>2024</risdate><volume>449</volume><spage>141658</spage><pages>141658-</pages><artnum>141658</artnum><issn>0959-6526</issn><eissn>1879-1786</eissn><abstract>The study presents the results of deep decontamination of the spent ion-exchange resin from the Kursk NPP, where the task of processing and conditioning of the resin is still not solved. The article shows that decontamination of the resin under dynamic conditions with a solution of the composition NaOH – 0.75 mol L−1, NaNO3 – 2.25 mol L−1 reduces its activity by 1 order of magnitude due to removal of Cs-137 (by washing). The subsequent washing of the resin with a solution of H2SO4 – 1.0 mol L−1, FeSO4 – 0.5 mol L−1 results in a decrease of its activity by another 1 order of magnitude due to removal of Eu-152-154 (100%) and partial removal of Co-60 (90%) and Am-241 (92%). It was found that further attempts to reduce the activity of the resin were ineffective due to the presence of insoluble precipitates, whose activity was mainly (more than 98%) accounted for by Co-60 (30.2%) and Nb-94 (68.1%) radionuclides. To remove these poorly soluble precipitates, we suggested decontamination by direct current through placing the resin between an anode and a cathode. A solution of H2SO4 of a concentration of 0.1 mol L−1 was used as an electrolyte. It has been found that an addition of FeSO4 (0.009 mol L−1) increases the rate of precipitate removal more than 1.5-fold. During the treatment by electric current, particles are mechanically removed, whereas insignificant amounts of Cs-137 and Co-60 (no more than 2.6%) enter the electrolyte. After the treatment and washing the resin with a NaNO3 solution, its activity decreases by another three orders of magnitude. The resulting activity of the resin was 350 Bq kg−1, which made it possible to classify it as industrial waste. [Display omitted]</abstract><pub>Elsevier Ltd</pub><doi>10.1016/j.jclepro.2024.141658</doi><orcidid>https://orcid.org/0000-0001-6833-0418</orcidid><orcidid>https://orcid.org/0000-0001-8974-2235</orcidid></addata></record>
fulltext fulltext
identifier ISSN: 0959-6526
ispartof Journal of cleaner production, 2024-04, Vol.449, p.141658, Article 141658
issn 0959-6526
1879-1786
language eng
recordid cdi_crossref_primary_10_1016_j_jclepro_2024_141658
source ScienceDirect Freedom Collection
subjects chemical decontamination
Deep decontamination
Direct current
Nuclear fuel cycle
Spent ion-exchange resins
title Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current
url http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-30T23%3A22%3A58IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-elsevier_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Decontamination%20of%20spent%20ion-exchange%20resins%20from%20the%20nuclear%20fuel%20cycle%20using%20chemical%20decontamination%20and%20direct%20current&rft.jtitle=Journal%20of%20cleaner%20production&rft.au=Matskevich,%20A.I.&rft.date=2024-04-10&rft.volume=449&rft.spage=141658&rft.pages=141658-&rft.artnum=141658&rft.issn=0959-6526&rft.eissn=1879-1786&rft_id=info:doi/10.1016/j.jclepro.2024.141658&rft_dat=%3Celsevier_cross%3ES0959652624011065%3C/elsevier_cross%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-c257t-6f727ddf6919571d802a963c26849f5a54fb0f54217eb06bc3189085accb95783%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true