Immobilization of Radioactive Cesium in Pyrolytic-Carbon-Coated Zeolite
All waste forms currently being developed for radwaste disposal have difficulty immobilizing cesium. A new waste form was developed to dispose of cesium by loading up to 5 wt% Cs onto zeolite granules. These zeolite particles are then heat‐treated and coated with pyrolytic carbon and/or BC to comple...
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| Veröffentlicht in: | J. Am. Ceram. Soc.; (United States) 1983-06, Vol.66 (6), p.389-392 |
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| creator | STINTON, DAVID P. LACKEY, W. J. ANGELINI, PETER |
| description | All waste forms currently being developed for radwaste disposal have difficulty immobilizing cesium. A new waste form was developed to dispose of cesium by loading up to 5 wt% Cs onto zeolite granules. These zeolite particles are then heat‐treated and coated with pyrolytic carbon and/or BC to completely immobilize cesium. The leach rate of cesium from pyrocarbon‐coated zeolite is 3 to 4 orders of magnitude less than for other waste forms. We therefore propose that cesium be removed from the primary waste stream and loaded onto zeolite granules for subsequent coating. The total waste form (primary waste form plus coated zeolite) would have acceptable leach resistance for all radwaste components and be extremely leach‐resistant for cesium. |
| doi_str_mv | 10.1111/j.1151-2916.1983.tb10066.x |
| format | Article |
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The total waste form (primary waste form plus coated zeolite) would have acceptable leach resistance for all radwaste components and be extremely leach‐resistant for cesium.</description><identifier>ISSN: 0002-7820</identifier><identifier>EISSN: 1551-2916</identifier><identifier>DOI: 10.1111/j.1151-2916.1983.tb10066.x</identifier><identifier>CODEN: JACTAW</identifier><language>eng</language><publisher>Oxford, UK: Blackwell Publishing Ltd</publisher><subject>052002 - Nuclear Fuels- Waste Disposal & Storage ; ALKALI METAL ISOTOPES ; Applied sciences ; Building materials. Ceramics. Glasses ; CARBIDES ; CARBON ; CARBON COMPOUNDS ; Ceramic industries ; CESIUM ISOTOPES ; CHEMICAL COATING ; Chemical industry and chemicals ; CHEMICAL VAPOR DEPOSITION ; DEPOSITION ; DISSOLUTION ; ELEMENTS ; Exact sciences and technology ; HEAT TREATMENTS ; HIGH-LEVEL RADIOACTIVE WASTES ; INORGANIC ION EXCHANGERS ; ION EXCHANGE MATERIALS ; ISOTOPES ; LEACHING ; MANAGEMENT ; MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES ; MATERIALS ; MINERALS ; Miscellaneous ; NONMETALS ; PERFORMANCE TESTING ; PYROLYTIC CARBON ; RADIOACTIVE MATERIALS ; RADIOACTIVE WASTE DISPOSAL ; RADIOACTIVE WASTES ; RECOMMENDATIONS ; SEPARATION PROCESSES ; SILICON CARBIDES ; SILICON COMPOUNDS ; SURFACE COATING ; TESTING ; WASTE DISPOSAL ; WASTE MANAGEMENT ; WASTES ; ZEOLITES</subject><ispartof>J. Am. Ceram. 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J.</creatorcontrib><creatorcontrib>ANGELINI, PETER</creatorcontrib><creatorcontrib>Oak Ridge National Lab., TN</creatorcontrib><title>Immobilization of Radioactive Cesium in Pyrolytic-Carbon-Coated Zeolite</title><title>J. Am. Ceram. Soc.; (United States)</title><description>All waste forms currently being developed for radwaste disposal have difficulty immobilizing cesium. A new waste form was developed to dispose of cesium by loading up to 5 wt% Cs onto zeolite granules. These zeolite particles are then heat‐treated and coated with pyrolytic carbon and/or BC to completely immobilize cesium. The leach rate of cesium from pyrocarbon‐coated zeolite is 3 to 4 orders of magnitude less than for other waste forms. We therefore propose that cesium be removed from the primary waste stream and loaded onto zeolite granules for subsequent coating. The total waste form (primary waste form plus coated zeolite) would have acceptable leach resistance for all radwaste components and be extremely leach‐resistant for cesium.</description><subject>052002 - Nuclear Fuels- Waste Disposal & Storage</subject><subject>ALKALI METAL ISOTOPES</subject><subject>Applied sciences</subject><subject>Building materials. Ceramics. Glasses</subject><subject>CARBIDES</subject><subject>CARBON</subject><subject>CARBON COMPOUNDS</subject><subject>Ceramic industries</subject><subject>CESIUM ISOTOPES</subject><subject>CHEMICAL COATING</subject><subject>Chemical industry and chemicals</subject><subject>CHEMICAL VAPOR DEPOSITION</subject><subject>DEPOSITION</subject><subject>DISSOLUTION</subject><subject>ELEMENTS</subject><subject>Exact sciences and technology</subject><subject>HEAT TREATMENTS</subject><subject>HIGH-LEVEL RADIOACTIVE WASTES</subject><subject>INORGANIC ION EXCHANGERS</subject><subject>ION EXCHANGE MATERIALS</subject><subject>ISOTOPES</subject><subject>LEACHING</subject><subject>MANAGEMENT</subject><subject>MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</subject><subject>MATERIALS</subject><subject>MINERALS</subject><subject>Miscellaneous</subject><subject>NONMETALS</subject><subject>PERFORMANCE TESTING</subject><subject>PYROLYTIC CARBON</subject><subject>RADIOACTIVE MATERIALS</subject><subject>RADIOACTIVE WASTE DISPOSAL</subject><subject>RADIOACTIVE WASTES</subject><subject>RECOMMENDATIONS</subject><subject>SEPARATION PROCESSES</subject><subject>SILICON CARBIDES</subject><subject>SILICON COMPOUNDS</subject><subject>SURFACE COATING</subject><subject>TESTING</subject><subject>WASTE DISPOSAL</subject><subject>WASTE MANAGEMENT</subject><subject>WASTES</subject><subject>ZEOLITES</subject><issn>0002-7820</issn><issn>1551-2916</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1983</creationdate><recordtype>article</recordtype><sourceid>K30</sourceid><recordid>eNqVkV1v0zAYhSMEEmXsP0QDcZfir9gON2iK1jLUQTWGkLixHOeNcEniYbvQ8utxlGoX3M0XfmX58TnyOVl2gdESp_V2l0aJC1JhvsSVpMvYYIQ4Xx6eZAtcnq6eZguEECmEJOh59iKEXTomnC2y9fUwuMb29q-O1o256_Jb3VqnTbS_Ia8h2P2Q2zHfHr3rj9Gaota-cWNROx2hzb-D622El9mzTvcBzk_zLPu6urqrPxSbz-vr-nJTGCZQVTRdKVogUoBAhspO45a0FFhjKqFp2mUreYspkgx4w2mFNGaEQwembUtS0bPsYtZ1IVoVTLI2P4wbRzBRCcwk5iJBb2bo3rtfewhRDTYY6Hs9gtsHRShhSOIJfPUfuHN7P6YPKExSnIJxzhL1bqaMdyF46NS9t4P2R4WRmmpQOzXVoKas1VSDOtWgDunx65OFDkb3ndejseFBoWKElBwl7P2M_bE9HB9hoD5e1ldUTskUs4INEQ4PCtr_VCkSUapvn9ZKrLZfNqubrbqj_wDD7qq5</recordid><startdate>198306</startdate><enddate>198306</enddate><creator>STINTON, DAVID P.</creator><creator>LACKEY, W. J.</creator><creator>ANGELINI, PETER</creator><general>Blackwell Publishing Ltd</general><general>Blackwell</general><general>American Ceramic Society</general><scope>BSCLL</scope><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>HDMVH</scope><scope>K30</scope><scope>PAAUG</scope><scope>PAWHS</scope><scope>PAWZZ</scope><scope>PAXOH</scope><scope>PBHAV</scope><scope>PBQSW</scope><scope>PBYQZ</scope><scope>PCIWU</scope><scope>PCMID</scope><scope>PCZJX</scope><scope>PDGRG</scope><scope>PDWWI</scope><scope>PETMR</scope><scope>PFVGT</scope><scope>PGXDX</scope><scope>PIHIL</scope><scope>PISVA</scope><scope>PJCTQ</scope><scope>PJTMS</scope><scope>PLCHJ</scope><scope>PMHAD</scope><scope>PNQDJ</scope><scope>POUND</scope><scope>PPLAD</scope><scope>PQAPC</scope><scope>PQCAN</scope><scope>PQCMW</scope><scope>PQEME</scope><scope>PQHKH</scope><scope>PQMID</scope><scope>PQNCT</scope><scope>PQNET</scope><scope>PQSCT</scope><scope>PQSET</scope><scope>PSVJG</scope><scope>PVMQY</scope><scope>PZGFC</scope><scope>7QQ</scope><scope>8FD</scope><scope>JG9</scope><scope>OTOTI</scope></search><sort><creationdate>198306</creationdate><title>Immobilization of Radioactive Cesium in Pyrolytic-Carbon-Coated Zeolite</title><author>STINTON, DAVID P. ; LACKEY, W. J. ; ANGELINI, PETER</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c4709-bf57de287e70c38fa1d2d3e4bc97a3bc98d86d13084e6b6390a1426efecdd5293</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1983</creationdate><topic>052002 - Nuclear Fuels- Waste Disposal & Storage</topic><topic>ALKALI METAL ISOTOPES</topic><topic>Applied sciences</topic><topic>Building materials. Ceramics. Glasses</topic><topic>CARBIDES</topic><topic>CARBON</topic><topic>CARBON COMPOUNDS</topic><topic>Ceramic industries</topic><topic>CESIUM ISOTOPES</topic><topic>CHEMICAL COATING</topic><topic>Chemical industry and chemicals</topic><topic>CHEMICAL VAPOR DEPOSITION</topic><topic>DEPOSITION</topic><topic>DISSOLUTION</topic><topic>ELEMENTS</topic><topic>Exact sciences and technology</topic><topic>HEAT TREATMENTS</topic><topic>HIGH-LEVEL RADIOACTIVE WASTES</topic><topic>INORGANIC ION EXCHANGERS</topic><topic>ION EXCHANGE MATERIALS</topic><topic>ISOTOPES</topic><topic>LEACHING</topic><topic>MANAGEMENT</topic><topic>MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</topic><topic>MATERIALS</topic><topic>MINERALS</topic><topic>Miscellaneous</topic><topic>NONMETALS</topic><topic>PERFORMANCE TESTING</topic><topic>PYROLYTIC CARBON</topic><topic>RADIOACTIVE MATERIALS</topic><topic>RADIOACTIVE WASTE DISPOSAL</topic><topic>RADIOACTIVE WASTES</topic><topic>RECOMMENDATIONS</topic><topic>SEPARATION PROCESSES</topic><topic>SILICON CARBIDES</topic><topic>SILICON COMPOUNDS</topic><topic>SURFACE COATING</topic><topic>TESTING</topic><topic>WASTE DISPOSAL</topic><topic>WASTE MANAGEMENT</topic><topic>WASTES</topic><topic>ZEOLITES</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>STINTON, DAVID P.</creatorcontrib><creatorcontrib>LACKEY, W. 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Am. Ceram. Soc.; (United States)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>STINTON, DAVID P.</au><au>LACKEY, W. J.</au><au>ANGELINI, PETER</au><aucorp>Oak Ridge National Lab., TN</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Immobilization of Radioactive Cesium in Pyrolytic-Carbon-Coated Zeolite</atitle><jtitle>J. Am. Ceram. Soc.; (United States)</jtitle><date>1983-06</date><risdate>1983</risdate><volume>66</volume><issue>6</issue><spage>389</spage><epage>392</epage><pages>389-392</pages><issn>0002-7820</issn><eissn>1551-2916</eissn><coden>JACTAW</coden><abstract>All waste forms currently being developed for radwaste disposal have difficulty immobilizing cesium. A new waste form was developed to dispose of cesium by loading up to 5 wt% Cs onto zeolite granules. These zeolite particles are then heat‐treated and coated with pyrolytic carbon and/or BC to completely immobilize cesium. The leach rate of cesium from pyrocarbon‐coated zeolite is 3 to 4 orders of magnitude less than for other waste forms. We therefore propose that cesium be removed from the primary waste stream and loaded onto zeolite granules for subsequent coating. The total waste form (primary waste form plus coated zeolite) would have acceptable leach resistance for all radwaste components and be extremely leach‐resistant for cesium.</abstract><cop>Oxford, UK</cop><pub>Blackwell Publishing Ltd</pub><doi>10.1111/j.1151-2916.1983.tb10066.x</doi><tpages>4</tpages></addata></record> |
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| identifier | ISSN: 0002-7820 |
| ispartof | J. Am. Ceram. Soc.; (United States), 1983-06, Vol.66 (6), p.389-392 |
| issn | 0002-7820 1551-2916 |
| language | eng |
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| source | Periodicals Index Online; Wiley Online Library All Journals |
| subjects | 052002 - Nuclear Fuels- Waste Disposal & Storage ALKALI METAL ISOTOPES Applied sciences Building materials. Ceramics. Glasses CARBIDES CARBON CARBON COMPOUNDS Ceramic industries CESIUM ISOTOPES CHEMICAL COATING Chemical industry and chemicals CHEMICAL VAPOR DEPOSITION DEPOSITION DISSOLUTION ELEMENTS Exact sciences and technology HEAT TREATMENTS HIGH-LEVEL RADIOACTIVE WASTES INORGANIC ION EXCHANGERS ION EXCHANGE MATERIALS ISOTOPES LEACHING MANAGEMENT MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES MATERIALS MINERALS Miscellaneous NONMETALS PERFORMANCE TESTING PYROLYTIC CARBON RADIOACTIVE MATERIALS RADIOACTIVE WASTE DISPOSAL RADIOACTIVE WASTES RECOMMENDATIONS SEPARATION PROCESSES SILICON CARBIDES SILICON COMPOUNDS SURFACE COATING TESTING WASTE DISPOSAL WASTE MANAGEMENT WASTES ZEOLITES |
| title | Immobilization of Radioactive Cesium in Pyrolytic-Carbon-Coated Zeolite |
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