Iodine solubility in a low-activity waste borosilicate glass at 1000°C
The purpose of this study was to determine the solubility of iodine in a low-activity waste borosilicate glass when heated inside an evacuated and sealed fused quartz ampoule. The iodine was added to glass frit as KI in quantities of 99.4–24,005ppm iodine (by mass). Each mixture was added to an ampo...
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| Veröffentlicht in: | Journal of nuclear materials 2014-09, Vol.452 (1-3), p.178-188 |
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| container_title | Journal of nuclear materials |
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| creator | Riley, Brian J. Schweiger, Michael J. Kim, Dong-Sang Lukens, Wayne W. Williams, Benjamin D. Iovin, Cristian Rodriguez, Carmen P. Overman, Nicole R. Bowden, Mark E. Dixon, Derek R. Crum, Jarrod V. McCloy, John S. Kruger, Albert A. |
| description | The purpose of this study was to determine the solubility of iodine in a low-activity waste borosilicate glass when heated inside an evacuated and sealed fused quartz ampoule. The iodine was added to glass frit as KI in quantities of 99.4–24,005ppm iodine (by mass). Each mixture was added to an ampoule, heated at 1000°C for 2h, and then air quenched. In samples with ⩾11,999ppm iodine, low viscosity salt phases were observed on the surface of the melts that solidified into a white coating upon cooling. These salts were identified by X-ray diffraction as mixtures of KI, NaI, and Na2SO4. Iodine concentrations in glass specimens were analyzed with inductively-coupled plasma mass spectrometry, and the overall iodine solubility was determined to be 10,000ppm. Several crystalline inclusions of iodine sodalite, Na8(AlSiO4)6I2, were observed in the 24,005ppm specimen. |
| doi_str_mv | 10.1016/j.jnucmat.2014.04.027 |
| format | Article |
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The iodine was added to glass frit as KI in quantities of 99.4–24,005ppm iodine (by mass). Each mixture was added to an ampoule, heated at 1000°C for 2h, and then air quenched. In samples with ⩾11,999ppm iodine, low viscosity salt phases were observed on the surface of the melts that solidified into a white coating upon cooling. These salts were identified by X-ray diffraction as mixtures of KI, NaI, and Na2SO4. Iodine concentrations in glass specimens were analyzed with inductively-coupled plasma mass spectrometry, and the overall iodine solubility was determined to be 10,000ppm. Several crystalline inclusions of iodine sodalite, Na8(AlSiO4)6I2, were observed in the 24,005ppm specimen.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2014.04.027</identifier><language>eng</language><publisher>United States: Elsevier B.V</publisher><subject>INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY ; MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</subject><ispartof>Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.178-188</ispartof><rights>2014 Elsevier B.V.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c2987-2f6a1c5e22b1a20e5b0a1480c341b42a74962f9aba3f8241039d9fde0bc5f1093</citedby><cites>FETCH-LOGICAL-c2987-2f6a1c5e22b1a20e5b0a1480c341b42a74962f9aba3f8241039d9fde0bc5f1093</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0022311514002426$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,776,780,881,3537,27901,27902,65534</link.rule.ids><backlink>$$Uhttps://www.osti.gov/servlets/purl/1378575$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Riley, Brian J.</creatorcontrib><creatorcontrib>Schweiger, Michael J.</creatorcontrib><creatorcontrib>Kim, Dong-Sang</creatorcontrib><creatorcontrib>Lukens, Wayne W.</creatorcontrib><creatorcontrib>Williams, Benjamin D.</creatorcontrib><creatorcontrib>Iovin, Cristian</creatorcontrib><creatorcontrib>Rodriguez, Carmen P.</creatorcontrib><creatorcontrib>Overman, Nicole R.</creatorcontrib><creatorcontrib>Bowden, Mark E.</creatorcontrib><creatorcontrib>Dixon, Derek R.</creatorcontrib><creatorcontrib>Crum, Jarrod V.</creatorcontrib><creatorcontrib>McCloy, John S.</creatorcontrib><creatorcontrib>Kruger, Albert A.</creatorcontrib><creatorcontrib>Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)</creatorcontrib><title>Iodine solubility in a low-activity waste borosilicate glass at 1000°C</title><title>Journal of nuclear materials</title><description>The purpose of this study was to determine the solubility of iodine in a low-activity waste borosilicate glass when heated inside an evacuated and sealed fused quartz ampoule. The iodine was added to glass frit as KI in quantities of 99.4–24,005ppm iodine (by mass). Each mixture was added to an ampoule, heated at 1000°C for 2h, and then air quenched. In samples with ⩾11,999ppm iodine, low viscosity salt phases were observed on the surface of the melts that solidified into a white coating upon cooling. These salts were identified by X-ray diffraction as mixtures of KI, NaI, and Na2SO4. Iodine concentrations in glass specimens were analyzed with inductively-coupled plasma mass spectrometry, and the overall iodine solubility was determined to be 10,000ppm. Several crystalline inclusions of iodine sodalite, Na8(AlSiO4)6I2, were observed in the 24,005ppm specimen.</description><subject>INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY</subject><subject>MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><recordid>eNqFUMFKw0AQXUTBWv0EIXhPnNlku8lJpGgtFLzoeZlsNrohzUp229K_8hv8MjfUu_BgmOG9NzOPsVuEDAEX913WDTu9pZBxwCKDCC7P2AxLmadFyeGczQA4T3NEccmuvO8AQFQgZmy1do0dTOJdv6ttb8MxsUNCSe8OKelg99PkQD6YpHaj85GiKTYfPXmfUEgwWv18L6_ZRUu9Nzd_dc7en5_eli_p5nW1Xj5uUs2rUqa8XRBqYTivkTgYUQNhUYLOC6wLTrKoFrytqKa8LXmBkFdN1TYGai1ahCqfs7uTr_PBKq9tMPpTu2EwOijMZSmkiCRxIul4sR9Nq75Gu6XxqBDUFJnq1F9kaopMQQSXUfdw0pn4wd6acVpgBm0aO07-jbP_OPwC87F3CQ</recordid><startdate>201409</startdate><enddate>201409</enddate><creator>Riley, Brian J.</creator><creator>Schweiger, Michael J.</creator><creator>Kim, Dong-Sang</creator><creator>Lukens, Wayne W.</creator><creator>Williams, Benjamin D.</creator><creator>Iovin, Cristian</creator><creator>Rodriguez, Carmen P.</creator><creator>Overman, Nicole R.</creator><creator>Bowden, Mark E.</creator><creator>Dixon, Derek R.</creator><creator>Crum, Jarrod V.</creator><creator>McCloy, John S.</creator><creator>Kruger, Albert A.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>OIOZB</scope><scope>OTOTI</scope></search><sort><creationdate>201409</creationdate><title>Iodine solubility in a low-activity waste borosilicate glass at 1000°C</title><author>Riley, Brian J. ; Schweiger, Michael J. ; Kim, Dong-Sang ; Lukens, Wayne W. ; Williams, Benjamin D. ; Iovin, Cristian ; Rodriguez, Carmen P. ; Overman, Nicole R. ; Bowden, Mark E. ; Dixon, Derek R. ; Crum, Jarrod V. ; McCloy, John S. ; Kruger, Albert A.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c2987-2f6a1c5e22b1a20e5b0a1480c341b42a74962f9aba3f8241039d9fde0bc5f1093</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY</topic><topic>MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Riley, Brian J.</creatorcontrib><creatorcontrib>Schweiger, Michael J.</creatorcontrib><creatorcontrib>Kim, Dong-Sang</creatorcontrib><creatorcontrib>Lukens, Wayne W.</creatorcontrib><creatorcontrib>Williams, Benjamin D.</creatorcontrib><creatorcontrib>Iovin, Cristian</creatorcontrib><creatorcontrib>Rodriguez, Carmen P.</creatorcontrib><creatorcontrib>Overman, Nicole R.</creatorcontrib><creatorcontrib>Bowden, Mark E.</creatorcontrib><creatorcontrib>Dixon, Derek R.</creatorcontrib><creatorcontrib>Crum, Jarrod V.</creatorcontrib><creatorcontrib>McCloy, John S.</creatorcontrib><creatorcontrib>Kruger, Albert A.</creatorcontrib><creatorcontrib>Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)</creatorcontrib><collection>CrossRef</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Riley, Brian J.</au><au>Schweiger, Michael J.</au><au>Kim, Dong-Sang</au><au>Lukens, Wayne W.</au><au>Williams, Benjamin D.</au><au>Iovin, Cristian</au><au>Rodriguez, Carmen P.</au><au>Overman, Nicole R.</au><au>Bowden, Mark E.</au><au>Dixon, Derek R.</au><au>Crum, Jarrod V.</au><au>McCloy, John S.</au><au>Kruger, Albert A.</au><aucorp>Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Iodine solubility in a low-activity waste borosilicate glass at 1000°C</atitle><jtitle>Journal of nuclear materials</jtitle><date>2014-09</date><risdate>2014</risdate><volume>452</volume><issue>1-3</issue><spage>178</spage><epage>188</epage><pages>178-188</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>The purpose of this study was to determine the solubility of iodine in a low-activity waste borosilicate glass when heated inside an evacuated and sealed fused quartz ampoule. 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| subjects | INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES |
| title | Iodine solubility in a low-activity waste borosilicate glass at 1000°C |
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