Artículo
DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation
Fecha de publicación:
10/2015
Editorial:
Elsevier Science Sa
Revista:
Nuclear Engineering and Design
ISSN:
0029-5493
Idioma:
Inglés
Tipo de recurso:
Artículo publicado
Clasificación temática:
Resumen
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.
Palabras clave:
Fuel Performance Simulation
,
High Burnup Structure
,
Validation Test
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Articulos(CSC)
Articulos de CENTRO DE SIMULACION COMPUTACIONAL P/APLIC. TECNOLOGICAS
Articulos de CENTRO DE SIMULACION COMPUTACIONAL P/APLIC. TECNOLOGICAS
Citación
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
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