Combined vitrification of chloride and phosphate wastes by pyroelectrochemical reprocessing of nuclear fuel
The results of an investigation of the combined vitrification of chloride and phosphate wastes, which were obtained as a result of experimental reprocessing of irradiated nuclear fuel by the pyroelectrochemical method, are presented. The optimal composition of the glass matrix is determined, the cha...
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| Veröffentlicht in: | Atomic energy (New York, N.Y.) N.Y.), 2006-12, Vol.101 (6), p.894-896 |
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| container_title | Atomic energy (New York, N.Y.) |
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| creator | Lavrinovich, Yu. G. Kuzin, M. A. Kormilitsyn, M. V. Tomilin, S. V. Gribakin, E. Yu Zakharova, L. V. |
| description | The results of an investigation of the combined vitrification of chloride and phosphate wastes, which were obtained as a result of experimental reprocessing of irradiated nuclear fuel by the pyroelectrochemical method, are presented. The optimal composition of the glass matrix is determined, the characteristics of the model and real samples obtained are presented, and the hydrolytic stability and the thermal stability of the samples are studied. The proposed method of combined vitrification makes it possible to salvage more than 1.5 times more wastes per unit mass of the glass block than separate vitrification.[PUBLICATION ABSTRACT] |
| doi_str_mv | 10.1007/s10512-006-0187-0 |
| format | Article |
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G. ; Kuzin, M. A. ; Kormilitsyn, M. V. ; Tomilin, S. V. ; Gribakin, E. Yu ; Zakharova, L. V.</creator><creatorcontrib>Lavrinovich, Yu. G. ; Kuzin, M. A. ; Kormilitsyn, M. V. ; Tomilin, S. V. ; Gribakin, E. Yu ; Zakharova, L. V.</creatorcontrib><description>The results of an investigation of the combined vitrification of chloride and phosphate wastes, which were obtained as a result of experimental reprocessing of irradiated nuclear fuel by the pyroelectrochemical method, are presented. The optimal composition of the glass matrix is determined, the characteristics of the model and real samples obtained are presented, and the hydrolytic stability and the thermal stability of the samples are studied. The proposed method of combined vitrification makes it possible to salvage more than 1.5 times more wastes per unit mass of the glass block than separate vitrification.[PUBLICATION ABSTRACT]</description><identifier>ISSN: 1063-4258</identifier><identifier>EISSN: 1573-8205</identifier><identifier>DOI: 10.1007/s10512-006-0187-0</identifier><language>eng</language><publisher>New York: Springer Nature B.V</publisher><subject>Chlorides ; Glass ; Mathematical models ; Nuclear fuels ; Optimization ; Phosphates ; Reprocessing ; Vitrification ; Wastes</subject><ispartof>Atomic energy (New York, N.Y.), 2006-12, Vol.101 (6), p.894-896</ispartof><rights>Springer Science+Business Media, Inc. 2006</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c305t-6538e2f566485eae34f5113cddc760bad255e64634b6e1be9d1a729dad14af973</citedby></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27901,27902</link.rule.ids></links><search><creatorcontrib>Lavrinovich, Yu. 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| ispartof | Atomic energy (New York, N.Y.), 2006-12, Vol.101 (6), p.894-896 |
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| source | Springer Nature - Complete Springer Journals |
| subjects | Chlorides Glass Mathematical models Nuclear fuels Optimization Phosphates Reprocessing Vitrification Wastes |
| title | Combined vitrification of chloride and phosphate wastes by pyroelectrochemical reprocessing of nuclear fuel |
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