Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate
- Autores
- Rincón, J. Ma.; Ramos, Cinthia Paula; Arboleda Zuluaga, Paula Andrea; Gonzalez Oliver, Carlos Julian R.
- Año de publicación
- 2018
- Idioma
- inglés
- Tipo de recurso
- artículo
- Estado
- versión publicada
- Descripción
- 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: 60P2O5·40Fe2O3 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 Si2U3/Al having additions of these glasses and U3O8 to dilute this Uranium enriched in MTR combustible (Material Testing Reactor).
Fil: Rincón, J. Ma.. Consejo Superior de Investigaciones Cientificas. Museo Nacional de Ciencias Naturales; España. Universidad de Miguel Hernández; España
Fil: Ramos, Cinthia Paula. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina. Universidad de Miguel Hernández; España
Fil: Arboleda Zuluaga, Paula Andrea. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
Fil: Gonzalez Oliver, Carlos Julian R.. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina - Materia
-
BI2O3
IRON PHOSPHATE
NUCLEAR WASTES
U3O8
VITRIFICATION - Nivel de accesibilidad
- acceso abierto
- Condiciones de uso
- https://creativecommons.org/licenses/by-nc-sa/2.5/ar/
- Repositorio
.jpg)
- Institución
- Consejo Nacional de Investigaciones Científicas y Técnicas
- OAI Identificador
- oai:ri.conicet.gov.ar:11336/89433
Ver los metadatos del registro completo
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Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogateRincón, J. Ma.Ramos, Cinthia PaulaArboleda Zuluaga, Paula AndreaGonzalez Oliver, Carlos Julian R.BI2O3IRON PHOSPHATENUCLEAR WASTESU3O8VITRIFICATIONhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2In 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: 60P2O5·40Fe2O3 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 Si2U3/Al having additions of these glasses and U3O8 to dilute this Uranium enriched in MTR combustible (Material Testing Reactor).Fil: Rincón, J. Ma.. Consejo Superior de Investigaciones Cientificas. Museo Nacional de Ciencias Naturales; España. Universidad de Miguel Hernández; EspañaFil: Ramos, Cinthia Paula. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina. Universidad de Miguel Hernández; EspañaFil: Arboleda Zuluaga, Paula Andrea. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; ArgentinaFil: Gonzalez Oliver, Carlos Julian R.. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; ArgentinaElsevier Science2018-09info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/89433Rincón, J. Ma.; Ramos, Cinthia Paula; Arboleda Zuluaga, Paula Andrea; Gonzalez Oliver, Carlos Julian R.; Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate; Elsevier Science; Materials Letters; 227; 9-2018; 82-850167-577XCONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0167577X18307559info:eu-repo/semantics/altIdentifier/doi/10.1016/j.matlet.2018.05.015info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-22T11:08:16Zoai:ri.conicet.gov.ar:11336/89433instacron:CONICETInstitucionalhttp://ri.conicet.gov.ar/Organismo científico-tecnológicoNo correspondehttp://ri.conicet.gov.ar/oai/requestdasensio@conicet.gov.ar; lcarlino@conicet.gov.arArgentinaNo correspondeNo correspondeNo correspondeopendoar:34982025-10-22 11:08:16.439CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse |
| dc.title.none.fl_str_mv |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| title |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| spellingShingle |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate Rincón, J. Ma. BI2O3 IRON PHOSPHATE NUCLEAR WASTES U3O8 VITRIFICATION |
| title_short |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| title_full |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| title_fullStr |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| title_full_unstemmed |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| title_sort |
Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate |
| dc.creator.none.fl_str_mv |
Rincón, J. Ma. Ramos, Cinthia Paula Arboleda Zuluaga, Paula Andrea Gonzalez Oliver, Carlos Julian R. |
| author |
Rincón, J. Ma. |
| author_facet |
Rincón, J. Ma. Ramos, Cinthia Paula Arboleda Zuluaga, Paula Andrea Gonzalez Oliver, Carlos Julian R. |
| author_role |
author |
| author2 |
Ramos, Cinthia Paula Arboleda Zuluaga, Paula Andrea Gonzalez Oliver, Carlos Julian R. |
| author2_role |
author author author |
| dc.subject.none.fl_str_mv |
BI2O3 IRON PHOSPHATE NUCLEAR WASTES U3O8 VITRIFICATION |
| topic |
BI2O3 IRON PHOSPHATE NUCLEAR WASTES U3O8 VITRIFICATION |
| purl_subject.fl_str_mv |
https://purl.org/becyt/ford/2.5 https://purl.org/becyt/ford/2 |
| dc.description.none.fl_txt_mv |
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: 60P2O5·40Fe2O3 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 Si2U3/Al having additions of these glasses and U3O8 to dilute this Uranium enriched in MTR combustible (Material Testing Reactor). Fil: Rincón, J. Ma.. Consejo Superior de Investigaciones Cientificas. Museo Nacional de Ciencias Naturales; España. Universidad de Miguel Hernández; España Fil: Ramos, Cinthia Paula. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Constituyentes; Argentina. Universidad de Miguel Hernández; España Fil: Arboleda Zuluaga, Paula Andrea. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina Fil: Gonzalez Oliver, Carlos Julian R.. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina |
| description |
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: 60P2O5·40Fe2O3 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 Si2U3/Al having additions of these glasses and U3O8 to dilute this Uranium enriched in MTR combustible (Material Testing Reactor). |
| publishDate |
2018 |
| dc.date.none.fl_str_mv |
2018-09 |
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info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion http://purl.org/coar/resource_type/c_6501 info:ar-repo/semantics/articulo |
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article |
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http://hdl.handle.net/11336/89433 Rincón, J. Ma.; Ramos, Cinthia Paula; Arboleda Zuluaga, Paula Andrea; Gonzalez Oliver, Carlos Julian R.; Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate; Elsevier Science; Materials Letters; 227; 9-2018; 82-85 0167-577X CONICET Digital CONICET |
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http://hdl.handle.net/11336/89433 |
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Rincón, J. Ma.; Ramos, Cinthia Paula; Arboleda Zuluaga, Paula Andrea; Gonzalez Oliver, Carlos Julian R.; Vitrification of U3O8 in iron aluminium phosphate matrices including Bi2O3 as uranium surrogate; Elsevier Science; Materials Letters; 227; 9-2018; 82-85 0167-577X CONICET Digital CONICET |
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eng |
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eng |
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Elsevier Science |
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Elsevier Science |
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dasensio@conicet.gov.ar; lcarlino@conicet.gov.ar |
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