Location preferences of fission products in high density U(Mo) dispersion fuel element
- Autores
- Alonso, Paula Regina; Forti, Mariano D.; Kniznik, Laura; Rubiolo, Gerardo Hector; Torres, Dario Nelson; Gargano, Pablo Hugo
- Año de publicación
- 2019
- Idioma
- inglés
- Tipo de recurso
- artículo
- Estado
- versión publicada
- Descripción
- In the frame of the RERTR (Reduced Enrichment for Research and Test Reactors) program a fuel element is being developed with the concept of high density bcc uranium that can remain stable during fabrication and later irradiation, dispersed in aluminum powder. The whole constitutes a compact material which is later rolled with an aluminum-silicon clad plate. Under further irradiation, an interaction layer (IL) grows through a diffusion process around the fuel element particle, leading to the swelling of the fuel element and formation of pores. This behavior can lead to catastrophic failure of the disperse fuel. Therefore it is our great interest to gain knowledge about the influence the fission products (FP) have over the IL formation and swelling. The stable compounds that have been observed in the IL of U(Mo)/Al(Si) tested in diffusion pair experiments are U(Al, Si)3, USi2, U1+xSi2-x, U3Si5 UMo2Al20 and U6Mo4Al43. Among them, U(Al, Si)3 has been observed to remain stable when subject to irradiation, delaying or stopping the IL swelling. Compositional analysis shows that La, Ce, Pr and Nd are some of the FP present in the burned dispersed fuel. Hence, these are the considered elements for a first evaluation of the problem that we performed in this work by means of computational methods.
Fil: Alonso, Paula Regina. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Forti, Mariano D.. Universidad Nacional de San Martín; Argentina
Fil: Kniznik, Laura. Universidad Nacional de San Martín; Argentina
Fil: Rubiolo, Gerardo Hector. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Torres, Dario Nelson. No especifíca;
Fil: Gargano, Pablo Hugo. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina - Materia
-
FISSION PRODUCTS
COMPUTATIONAL CALCULATION
HIGH DENSITY FUEL, URANIUM
INTER DIFFUSION LAYER - Nivel de accesibilidad
- acceso abierto
- Condiciones de uso
- https://creativecommons.org/licenses/by-nc/2.5/ar/
- Repositorio
.jpg)
- Institución
- Consejo Nacional de Investigaciones Científicas y Técnicas
- OAI Identificador
- oai:ri.conicet.gov.ar:11336/119187
Ver los metadatos del registro completo
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Location preferences of fission products in high density U(Mo) dispersion fuel elementAlonso, Paula ReginaForti, Mariano D.Kniznik, LauraRubiolo, Gerardo HectorTorres, Dario NelsonGargano, Pablo HugoFISSION PRODUCTSCOMPUTATIONAL CALCULATIONHIGH DENSITY FUEL, URANIUMINTER DIFFUSION LAYERhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2In the frame of the RERTR (Reduced Enrichment for Research and Test Reactors) program a fuel element is being developed with the concept of high density bcc uranium that can remain stable during fabrication and later irradiation, dispersed in aluminum powder. The whole constitutes a compact material which is later rolled with an aluminum-silicon clad plate. Under further irradiation, an interaction layer (IL) grows through a diffusion process around the fuel element particle, leading to the swelling of the fuel element and formation of pores. This behavior can lead to catastrophic failure of the disperse fuel. Therefore it is our great interest to gain knowledge about the influence the fission products (FP) have over the IL formation and swelling. The stable compounds that have been observed in the IL of U(Mo)/Al(Si) tested in diffusion pair experiments are U(Al, Si)3, USi2, U1+xSi2-x, U3Si5 UMo2Al20 and U6Mo4Al43. Among them, U(Al, Si)3 has been observed to remain stable when subject to irradiation, delaying or stopping the IL swelling. Compositional analysis shows that La, Ce, Pr and Nd are some of the FP present in the burned dispersed fuel. Hence, these are the considered elements for a first evaluation of the problem that we performed in this work by means of computational methods.Fil: Alonso, Paula Regina. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Forti, Mariano D.. Universidad Nacional de San Martín; ArgentinaFil: Kniznik, Laura. Universidad Nacional de San Martín; ArgentinaFil: Rubiolo, Gerardo Hector. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Torres, Dario Nelson. No especifíca;Fil: Gargano, Pablo Hugo. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaMedCrave2019-02info: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/11336/119187Alonso, Paula Regina; Forti, Mariano D.; Kniznik, Laura; Rubiolo, Gerardo Hector; Torres, Dario Nelson; et al.; Location preferences of fission products in high density U(Mo) dispersion fuel element; MedCrave; Material Science & Engineering International Journal; 3; 1; 2-2019; 21-222574-9927CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://medcraveonline.com/MSEIJ/MSEIJ-03-00083.pdfinfo:eu-repo/semantics/altIdentifier/url/https://medcraveonline.com/MSEIJ/location-preferences-of-fission-products-in-high-density-umo-dispersion-fuel-elementnbsp.htmlinfo:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-22T12:12:17Zoai:ri.conicet.gov.ar:11336/119187instacron: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 12:12:17.742CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse |
| dc.title.none.fl_str_mv |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| title |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| spellingShingle |
Location preferences of fission products in high density U(Mo) dispersion fuel element Alonso, Paula Regina FISSION PRODUCTS COMPUTATIONAL CALCULATION HIGH DENSITY FUEL, URANIUM INTER DIFFUSION LAYER |
| title_short |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| title_full |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| title_fullStr |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| title_full_unstemmed |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| title_sort |
Location preferences of fission products in high density U(Mo) dispersion fuel element |
| dc.creator.none.fl_str_mv |
Alonso, Paula Regina Forti, Mariano D. Kniznik, Laura Rubiolo, Gerardo Hector Torres, Dario Nelson Gargano, Pablo Hugo |
| author |
Alonso, Paula Regina |
| author_facet |
Alonso, Paula Regina Forti, Mariano D. Kniznik, Laura Rubiolo, Gerardo Hector Torres, Dario Nelson Gargano, Pablo Hugo |
| author_role |
author |
| author2 |
Forti, Mariano D. Kniznik, Laura Rubiolo, Gerardo Hector Torres, Dario Nelson Gargano, Pablo Hugo |
| author2_role |
author author author author author |
| dc.subject.none.fl_str_mv |
FISSION PRODUCTS COMPUTATIONAL CALCULATION HIGH DENSITY FUEL, URANIUM INTER DIFFUSION LAYER |
| topic |
FISSION PRODUCTS COMPUTATIONAL CALCULATION HIGH DENSITY FUEL, URANIUM INTER DIFFUSION LAYER |
| 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 the frame of the RERTR (Reduced Enrichment for Research and Test Reactors) program a fuel element is being developed with the concept of high density bcc uranium that can remain stable during fabrication and later irradiation, dispersed in aluminum powder. The whole constitutes a compact material which is later rolled with an aluminum-silicon clad plate. Under further irradiation, an interaction layer (IL) grows through a diffusion process around the fuel element particle, leading to the swelling of the fuel element and formation of pores. This behavior can lead to catastrophic failure of the disperse fuel. Therefore it is our great interest to gain knowledge about the influence the fission products (FP) have over the IL formation and swelling. The stable compounds that have been observed in the IL of U(Mo)/Al(Si) tested in diffusion pair experiments are U(Al, Si)3, USi2, U1+xSi2-x, U3Si5 UMo2Al20 and U6Mo4Al43. Among them, U(Al, Si)3 has been observed to remain stable when subject to irradiation, delaying or stopping the IL swelling. Compositional analysis shows that La, Ce, Pr and Nd are some of the FP present in the burned dispersed fuel. Hence, these are the considered elements for a first evaluation of the problem that we performed in this work by means of computational methods. Fil: Alonso, Paula Regina. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina Fil: Forti, Mariano D.. Universidad Nacional de San Martín; Argentina Fil: Kniznik, Laura. Universidad Nacional de San Martín; Argentina Fil: Rubiolo, Gerardo Hector. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina Fil: Torres, Dario Nelson. No especifíca; Fil: Gargano, Pablo Hugo. Universidad Nacional de San Martín; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina |
| description |
In the frame of the RERTR (Reduced Enrichment for Research and Test Reactors) program a fuel element is being developed with the concept of high density bcc uranium that can remain stable during fabrication and later irradiation, dispersed in aluminum powder. The whole constitutes a compact material which is later rolled with an aluminum-silicon clad plate. Under further irradiation, an interaction layer (IL) grows through a diffusion process around the fuel element particle, leading to the swelling of the fuel element and formation of pores. This behavior can lead to catastrophic failure of the disperse fuel. Therefore it is our great interest to gain knowledge about the influence the fission products (FP) have over the IL formation and swelling. The stable compounds that have been observed in the IL of U(Mo)/Al(Si) tested in diffusion pair experiments are U(Al, Si)3, USi2, U1+xSi2-x, U3Si5 UMo2Al20 and U6Mo4Al43. Among them, U(Al, Si)3 has been observed to remain stable when subject to irradiation, delaying or stopping the IL swelling. Compositional analysis shows that La, Ce, Pr and Nd are some of the FP present in the burned dispersed fuel. Hence, these are the considered elements for a first evaluation of the problem that we performed in this work by means of computational methods. |
| publishDate |
2019 |
| dc.date.none.fl_str_mv |
2019-02 |
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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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publishedVersion |
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http://hdl.handle.net/11336/119187 Alonso, Paula Regina; Forti, Mariano D.; Kniznik, Laura; Rubiolo, Gerardo Hector; Torres, Dario Nelson; et al.; Location preferences of fission products in high density U(Mo) dispersion fuel element; MedCrave; Material Science & Engineering International Journal; 3; 1; 2-2019; 21-22 2574-9927 CONICET Digital CONICET |
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http://hdl.handle.net/11336/119187 |
| identifier_str_mv |
Alonso, Paula Regina; Forti, Mariano D.; Kniznik, Laura; Rubiolo, Gerardo Hector; Torres, Dario Nelson; et al.; Location preferences of fission products in high density U(Mo) dispersion fuel element; MedCrave; Material Science & Engineering International Journal; 3; 1; 2-2019; 21-22 2574-9927 CONICET Digital CONICET |
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eng |
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eng |
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MedCrave |
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