Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout
Grout and glass formulations were developed for the stabilization of highly radioactive tank sludges. These formulations were tested in the laboratory with a surrogate and with a sample of an actual mixed waste tank sludge. The grout formulation was tested at wet-sludge loadings of 50–60 wt%, giving...
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Veröffentlicht in: | Waste management (Elmsford) 1999-01, Vol.19 (7), p.453-465 |
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creator | Spence, R.D Gilliam, T.M Mattus, C.H Mattus, A.J |
description | Grout and glass formulations were developed for the stabilization of highly radioactive tank sludges. These formulations were tested in the laboratory with a surrogate and with a sample of an actual mixed waste tank sludge. The grout formulation was tested at wet-sludge loadings of 50–60 wt%, giving a volume increase of about 40–50 vol%. Dried sludge was vitrified into glass at waste oxide loadings of 40–50 wt%, giving a volume decrease of about 50–60 vol%. The Resource Conservation and Recovery Act (RCRA) metals included in surrogate testing were Ag, Ba, Cd, Cr, Ni, Pb, Se, Tl and Hg. Since vitrification would volatilize, not stabilize mercury, it was not included in the surrogates vitrified. The actual sludge sample was only characteristically hazardous for mercury by the toxic characteristic leaching procedure (TCLP) but exceeded the Universal Treatment Standard (UTS) limit for chromium. The grout and glass formulations stabilized these RCRA metals within UTS limits. In addition, a grout leachability index of about 9–10 was measured for both
85Sr and
137Cs, meeting the recommended requirement of >6. The glass leachability index was estimated to be >18 for cold cesium and strontium. |
doi_str_mv | 10.1016/S0956-053X(99)00237-8 |
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85Sr and
137Cs, meeting the recommended requirement of >6. The glass leachability index was estimated to be >18 for cold cesium and strontium.</description><identifier>ISSN: 0956-053X</identifier><identifier>EISSN: 1879-2456</identifier><identifier>DOI: 10.1016/S0956-053X(99)00237-8</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>137Cs ; 85Sr ; Applied sciences ; BARIUM ; BENCH-SCALE EXPERIMENTS ; CADMIUM ; CESIUM 137 ; CHROMIUM ; Exact sciences and technology ; GLASS ; Grout ; HIGH-LEVEL RADIOACTIVE WASTES ; LEAD ; MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES ; MERCURY ; Mixed waste ; MIXTURES ; NICKEL ; Pollution ; RADIOACTIVE WASTE PROCESSING ; Radioactive wastes ; RCRA metals ; SELENIUM ; SILVER ; SLUDGES ; SOLIDIFICATION ; STABILIZATION ; STRONTIUM 85 ; THALLIUM ; Wastes</subject><ispartof>Waste management (Elmsford), 1999-01, Vol.19 (7), p.453-465</ispartof><rights>1999</rights><rights>2000 INIST-CNRS</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c483t-3c5c82c0859329ddd5eae97e2703880e9b4e3a185e4aaecf6a262f1e23b434223</citedby><cites>FETCH-LOGICAL-c483t-3c5c82c0859329ddd5eae97e2703880e9b4e3a185e4aaecf6a262f1e23b434223</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/S0956-053X(99)00237-8$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,780,784,885,3550,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=1184675$$DView record in Pascal Francis$$Hfree_for_read</backlink><backlink>$$Uhttps://www.osti.gov/biblio/20018989$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Spence, R.D</creatorcontrib><creatorcontrib>Gilliam, T.M</creatorcontrib><creatorcontrib>Mattus, C.H</creatorcontrib><creatorcontrib>Mattus, A.J</creatorcontrib><creatorcontrib>Oak Ridge National Lab., TN (US)</creatorcontrib><title>Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout</title><title>Waste management (Elmsford)</title><description>Grout and glass formulations were developed for the stabilization of highly radioactive tank sludges. These formulations were tested in the laboratory with a surrogate and with a sample of an actual mixed waste tank sludge. The grout formulation was tested at wet-sludge loadings of 50–60 wt%, giving a volume increase of about 40–50 vol%. Dried sludge was vitrified into glass at waste oxide loadings of 40–50 wt%, giving a volume decrease of about 50–60 vol%. The Resource Conservation and Recovery Act (RCRA) metals included in surrogate testing were Ag, Ba, Cd, Cr, Ni, Pb, Se, Tl and Hg. Since vitrification would volatilize, not stabilize mercury, it was not included in the surrogates vitrified. The actual sludge sample was only characteristically hazardous for mercury by the toxic characteristic leaching procedure (TCLP) but exceeded the Universal Treatment Standard (UTS) limit for chromium. The grout and glass formulations stabilized these RCRA metals within UTS limits. In addition, a grout leachability index of about 9–10 was measured for both
85Sr and
137Cs, meeting the recommended requirement of >6. The glass leachability index was estimated to be >18 for cold cesium and strontium.</description><subject>137Cs</subject><subject>85Sr</subject><subject>Applied sciences</subject><subject>BARIUM</subject><subject>BENCH-SCALE EXPERIMENTS</subject><subject>CADMIUM</subject><subject>CESIUM 137</subject><subject>CHROMIUM</subject><subject>Exact sciences and technology</subject><subject>GLASS</subject><subject>Grout</subject><subject>HIGH-LEVEL RADIOACTIVE WASTES</subject><subject>LEAD</subject><subject>MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</subject><subject>MERCURY</subject><subject>Mixed waste</subject><subject>MIXTURES</subject><subject>NICKEL</subject><subject>Pollution</subject><subject>RADIOACTIVE WASTE PROCESSING</subject><subject>Radioactive wastes</subject><subject>RCRA metals</subject><subject>SELENIUM</subject><subject>SILVER</subject><subject>SLUDGES</subject><subject>SOLIDIFICATION</subject><subject>STABILIZATION</subject><subject>STRONTIUM 85</subject><subject>THALLIUM</subject><subject>Wastes</subject><issn>0956-053X</issn><issn>1879-2456</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1999</creationdate><recordtype>article</recordtype><recordid>eNqFkEtrFEEQgAcx4Br9CcKAIuYwpp8z3ScJwaiwkEMUvDW13TVrS-907OpRk1_v7G7Qo6eiiq9eX9O84OwtZ7w_v2FW9x3T8usba88YE3LozKNmxc1gO6F0_7hZ_UWeNE-JvjPGleFs1eAaNrlAzeWupQqbmOI91Jinc8ophjhGf0jbPLY0l5K3ULGFKbTg6wyp3cXfGLpfQEuZ0hy22Map3SYgOmDbkuf6rDkZIRE-f4inzZer958vP3br6w-fLi_WnVdG1k567Y3wzGgrhQ0haAS0A4qBSWMY2o1CCdxoVADoxx5EL0aOQm6UVELI0-blcW6mGh35WNF_83ma0FcnlqeNNXahXh-p25J_zEjV7SJ5TAkmzDM5PijFjOkXUB9BXzJRwdHdlriDcuc4c3v17qDe7b06a91BvTNL36uHBUAe0lhg8pH-NXOj-kEv2LsjhouSnxHL_mKcPIZY9geHHP-z6A82tJm8</recordid><startdate>19990101</startdate><enddate>19990101</enddate><creator>Spence, R.D</creator><creator>Gilliam, T.M</creator><creator>Mattus, C.H</creator><creator>Mattus, A.J</creator><general>Elsevier Ltd</general><general>Elsevier Science</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7T2</scope><scope>7TV</scope><scope>7U2</scope><scope>C1K</scope><scope>OTOTI</scope></search><sort><creationdate>19990101</creationdate><title>Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout</title><author>Spence, R.D ; Gilliam, T.M ; Mattus, C.H ; Mattus, A.J</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c483t-3c5c82c0859329ddd5eae97e2703880e9b4e3a185e4aaecf6a262f1e23b434223</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1999</creationdate><topic>137Cs</topic><topic>85Sr</topic><topic>Applied sciences</topic><topic>BARIUM</topic><topic>BENCH-SCALE EXPERIMENTS</topic><topic>CADMIUM</topic><topic>CESIUM 137</topic><topic>CHROMIUM</topic><topic>Exact sciences and technology</topic><topic>GLASS</topic><topic>Grout</topic><topic>HIGH-LEVEL RADIOACTIVE WASTES</topic><topic>LEAD</topic><topic>MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</topic><topic>MERCURY</topic><topic>Mixed waste</topic><topic>MIXTURES</topic><topic>NICKEL</topic><topic>Pollution</topic><topic>RADIOACTIVE WASTE PROCESSING</topic><topic>Radioactive wastes</topic><topic>RCRA metals</topic><topic>SELENIUM</topic><topic>SILVER</topic><topic>SLUDGES</topic><topic>SOLIDIFICATION</topic><topic>STABILIZATION</topic><topic>STRONTIUM 85</topic><topic>THALLIUM</topic><topic>Wastes</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Spence, R.D</creatorcontrib><creatorcontrib>Gilliam, T.M</creatorcontrib><creatorcontrib>Mattus, C.H</creatorcontrib><creatorcontrib>Mattus, A.J</creatorcontrib><creatorcontrib>Oak Ridge National Lab., TN (US)</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Health and Safety Science Abstracts (Full archive)</collection><collection>Pollution Abstracts</collection><collection>Safety Science and Risk</collection><collection>Environmental Sciences and Pollution Management</collection><collection>OSTI.GOV</collection><jtitle>Waste management (Elmsford)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Spence, R.D</au><au>Gilliam, T.M</au><au>Mattus, C.H</au><au>Mattus, A.J</au><aucorp>Oak Ridge National Lab., TN (US)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout</atitle><jtitle>Waste management (Elmsford)</jtitle><date>1999-01-01</date><risdate>1999</risdate><volume>19</volume><issue>7</issue><spage>453</spage><epage>465</epage><pages>453-465</pages><issn>0956-053X</issn><eissn>1879-2456</eissn><abstract>Grout and glass formulations were developed for the stabilization of highly radioactive tank sludges. These formulations were tested in the laboratory with a surrogate and with a sample of an actual mixed waste tank sludge. The grout formulation was tested at wet-sludge loadings of 50–60 wt%, giving a volume increase of about 40–50 vol%. Dried sludge was vitrified into glass at waste oxide loadings of 40–50 wt%, giving a volume decrease of about 50–60 vol%. The Resource Conservation and Recovery Act (RCRA) metals included in surrogate testing were Ag, Ba, Cd, Cr, Ni, Pb, Se, Tl and Hg. Since vitrification would volatilize, not stabilize mercury, it was not included in the surrogates vitrified. The actual sludge sample was only characteristically hazardous for mercury by the toxic characteristic leaching procedure (TCLP) but exceeded the Universal Treatment Standard (UTS) limit for chromium. The grout and glass formulations stabilized these RCRA metals within UTS limits. In addition, a grout leachability index of about 9–10 was measured for both
85Sr and
137Cs, meeting the recommended requirement of >6. The glass leachability index was estimated to be >18 for cold cesium and strontium.</abstract><cop>Oxford</cop><cop>New York, NY</cop><pub>Elsevier Ltd</pub><doi>10.1016/S0956-053X(99)00237-8</doi><tpages>13</tpages><oa>free_for_read</oa></addata></record> |
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subjects | 137Cs 85Sr Applied sciences BARIUM BENCH-SCALE EXPERIMENTS CADMIUM CESIUM 137 CHROMIUM Exact sciences and technology GLASS Grout HIGH-LEVEL RADIOACTIVE WASTES LEAD MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES MERCURY Mixed waste MIXTURES NICKEL Pollution RADIOACTIVE WASTE PROCESSING Radioactive wastes RCRA metals SELENIUM SILVER SLUDGES SOLIDIFICATION STABILIZATION STRONTIUM 85 THALLIUM Wastes |
title | Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout |
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