DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation
- Autores
- Soba, Alejandro; Denis, Alicia Catalina
- Año de publicación
- 2015
- Idioma
- inglés
- Tipo de recurso
- artículo
- Estado
- versión publicada
- Descripción
- The version 2.0 of the DIONISIO code, that incorporates diverse new aspects, has been recently developed. One of them is referred to the code architecture that allows taking into account the axial variation of the conditions external to the rod. With this purpose, the rod is divided into a number of axial segments. In each one the program considers the system formed by a pellet and the corresponding cladding portion and solves the numerous phenomena that take place under the local conditions of linear power and coolant temperature, which are given as input parameters. To do this a bi-dimensional domain in the r-z plane is considered where cylindrical symmetry and also symmetry with respect to the pellet mid-plane are assumed. The results obtained for this representative system are assumed valid for the complete segment. The program thus produces in each rod section the values of the temperature, stress, strain, among others as outputs, as functions of the local coordinates r and z. Then, the general rod parameters (internal rod pressure, amount of fission gas released, pellet stack elongation, etc.) are evaluated.Moreover, new calculation tools designed to extend the application range of the code to high burnup, which were reported elsewhere, have also been incorporated to DIONISIO 2.0 in recent times. With these improvements, the code results are compared with some 33 experiments compiled in the IFPE data base, that cover more than 380 fuel rods irradiated up to average burnup levels of 40-60 MWd/kgU. The results of these comparisons, which are presented here, reveal the good quality of the simulations.
Fil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
Fil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; Argentina - Materia
-
Fuel Performance Simulation
High Burnup Structure
Validation Test - 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:11336/46682
Ver los metadatos del registro completo
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DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiationSoba, AlejandroDenis, Alicia CatalinaFuel Performance SimulationHigh Burnup StructureValidation Testhttps://purl.org/becyt/ford/2.5https://purl.org/becyt/ford/2The version 2.0 of the DIONISIO code, that incorporates diverse new aspects, has been recently developed. One of them is referred to the code architecture that allows taking into account the axial variation of the conditions external to the rod. With this purpose, the rod is divided into a number of axial segments. In each one the program considers the system formed by a pellet and the corresponding cladding portion and solves the numerous phenomena that take place under the local conditions of linear power and coolant temperature, which are given as input parameters. To do this a bi-dimensional domain in the r-z plane is considered where cylindrical symmetry and also symmetry with respect to the pellet mid-plane are assumed. The results obtained for this representative system are assumed valid for the complete segment. The program thus produces in each rod section the values of the temperature, stress, strain, among others as outputs, as functions of the local coordinates r and z. Then, the general rod parameters (internal rod pressure, amount of fission gas released, pellet stack elongation, etc.) are evaluated.Moreover, new calculation tools designed to extend the application range of the code to high burnup, which were reported elsewhere, have also been incorporated to DIONISIO 2.0 in recent times. With these improvements, the code results are compared with some 33 experiments compiled in the IFPE data base, that cover more than 380 fuel rods irradiated up to average burnup levels of 40-60 MWd/kgU. The results of these comparisons, which are presented here, reveal the good quality of the simulations.Fil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; ArgentinaFil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; ArgentinaElsevier Science Sa2015-10info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionhttp://purl.org/coar/resource_type/c_6501info:ar-repo/semantics/articuloapplication/pdfapplication/pdfapplication/pdfhttp://hdl.handle.net/11336/46682Soba, Alejandro; Denis, Alicia Catalina; DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation; Elsevier Science Sa; Nuclear Engineering and Design; 292; 10-2015; 213-2210029-5493CONICET DigitalCONICETenginfo:eu-repo/semantics/altIdentifier/url/https://www.sciencedirect.com/science/article/pii/S0029549315002587info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nucengdes.2015.06.008info:eu-repo/semantics/openAccesshttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/reponame:CONICET Digital (CONICET)instname:Consejo Nacional de Investigaciones Científicas y Técnicas2025-10-22T12:11:08Zoai:ri.conicet.gov.ar:11336/46682instacron: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 12:11:09.131CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicasfalse |
| dc.title.none.fl_str_mv |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| title |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| spellingShingle |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation Soba, Alejandro Fuel Performance Simulation High Burnup Structure Validation Test |
| title_short |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| title_full |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| title_fullStr |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| title_full_unstemmed |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| title_sort |
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation |
| dc.creator.none.fl_str_mv |
Soba, Alejandro Denis, Alicia Catalina |
| author |
Soba, Alejandro |
| author_facet |
Soba, Alejandro Denis, Alicia Catalina |
| author_role |
author |
| author2 |
Denis, Alicia Catalina |
| author2_role |
author |
| dc.subject.none.fl_str_mv |
Fuel Performance Simulation High Burnup Structure Validation Test |
| topic |
Fuel Performance Simulation High Burnup Structure Validation Test |
| purl_subject.fl_str_mv |
https://purl.org/becyt/ford/2.5 https://purl.org/becyt/ford/2 |
| dc.description.none.fl_txt_mv |
The version 2.0 of the DIONISIO code, that incorporates diverse new aspects, has been recently developed. One of them is referred to the code architecture that allows taking into account the axial variation of the conditions external to the rod. With this purpose, the rod is divided into a number of axial segments. In each one the program considers the system formed by a pellet and the corresponding cladding portion and solves the numerous phenomena that take place under the local conditions of linear power and coolant temperature, which are given as input parameters. To do this a bi-dimensional domain in the r-z plane is considered where cylindrical symmetry and also symmetry with respect to the pellet mid-plane are assumed. The results obtained for this representative system are assumed valid for the complete segment. The program thus produces in each rod section the values of the temperature, stress, strain, among others as outputs, as functions of the local coordinates r and z. Then, the general rod parameters (internal rod pressure, amount of fission gas released, pellet stack elongation, etc.) are evaluated.Moreover, new calculation tools designed to extend the application range of the code to high burnup, which were reported elsewhere, have also been incorporated to DIONISIO 2.0 in recent times. With these improvements, the code results are compared with some 33 experiments compiled in the IFPE data base, that cover more than 380 fuel rods irradiated up to average burnup levels of 40-60 MWd/kgU. The results of these comparisons, which are presented here, reveal the good quality of the simulations. Fil: Soba, Alejandro. Comisión Nacional de Energía Atómica; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina Fil: Denis, Alicia Catalina. Comisión Nacional de Energía Atómica; Argentina |
| description |
The version 2.0 of the DIONISIO code, that incorporates diverse new aspects, has been recently developed. One of them is referred to the code architecture that allows taking into account the axial variation of the conditions external to the rod. With this purpose, the rod is divided into a number of axial segments. In each one the program considers the system formed by a pellet and the corresponding cladding portion and solves the numerous phenomena that take place under the local conditions of linear power and coolant temperature, which are given as input parameters. To do this a bi-dimensional domain in the r-z plane is considered where cylindrical symmetry and also symmetry with respect to the pellet mid-plane are assumed. The results obtained for this representative system are assumed valid for the complete segment. The program thus produces in each rod section the values of the temperature, stress, strain, among others as outputs, as functions of the local coordinates r and z. Then, the general rod parameters (internal rod pressure, amount of fission gas released, pellet stack elongation, etc.) are evaluated.Moreover, new calculation tools designed to extend the application range of the code to high burnup, which were reported elsewhere, have also been incorporated to DIONISIO 2.0 in recent times. With these improvements, the code results are compared with some 33 experiments compiled in the IFPE data base, that cover more than 380 fuel rods irradiated up to average burnup levels of 40-60 MWd/kgU. The results of these comparisons, which are presented here, reveal the good quality of the simulations. |
| publishDate |
2015 |
| dc.date.none.fl_str_mv |
2015-10 |
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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 |
| format |
article |
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publishedVersion |
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http://hdl.handle.net/11336/46682 Soba, Alejandro; Denis, Alicia Catalina; DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation; Elsevier Science Sa; Nuclear Engineering and Design; 292; 10-2015; 213-221 0029-5493 CONICET Digital CONICET |
| url |
http://hdl.handle.net/11336/46682 |
| identifier_str_mv |
Soba, Alejandro; Denis, Alicia Catalina; DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation; Elsevier Science Sa; Nuclear Engineering and Design; 292; 10-2015; 213-221 0029-5493 CONICET Digital CONICET |
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eng |
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eng |
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openAccess |
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Elsevier Science Sa |
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Elsevier Science Sa |
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CONICET Digital (CONICET) - Consejo Nacional de Investigaciones Científicas y Técnicas |
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dasensio@conicet.gov.ar; lcarlino@conicet.gov.ar |
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