1. Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate.
- Author
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Rincón, J. Ma., Ramos, C., Arboleda, P., and González Oliver, C.J.R.
- Subjects
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RADIOACTIVE waste vitrification , *IRON compounds , *URANIUM compounds , *BISMUTH oxides , *THERMAL stability , *CRYSTALLIZATION - Abstract
In order to encapsulate nuclear wastes (NW) enriched in Uranium, they have been designed and obtained vitrified matrices of iron aluminum phosphates including substitution of U by Bi. These glasses have been designed and obtained formulating all from the starting binary composition: 60P 2 O 5 ·40Fe 2 O 3 where the Fe/P ratio was 0.67. The thermal behavior has been investigated by DTA/TG analysis and thermal expansion, as well as identification of some phases by TEM/EDS. The vitrified structures are difficult to crystallize as is the case of the (Fe + U) contents in the range of 0.50 per P atom. Glasses with Bi-oxide are less resistant to crystallization than those containing U. The glasses here investigated depict a reasonable water chemical stability due to the high percentage of P O Fe O bonds and the presence of U (4+ to 6+). Lately, it has been also investigated the calcination of simulated miniplates of Si 2 U 3 /Al having additions of these glasses and U 3 O 8 to dilute this Uranium enriched in MTR combustible (Material Testing Reactor). [ABSTRACT FROM AUTHOR]
- Published
- 2018
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