CORDIS proporciona enlaces a los documentos públicos y las publicaciones de los proyectos de los programas marco HORIZONTE.
Los enlaces a los documentos y las publicaciones de los proyectos del Séptimo Programa Marco, así como los enlaces a algunos tipos de resultados específicos, como conjuntos de datos y «software», se obtienen dinámicamente de OpenAIRE .
Resultado final
the report will describe the procedures for the exploitation of the results obtained during the project
Best practices and QA protocols for code development (se abrirá en una nueva ventana)Report describing best practices and QA protocols used for the open source code development in WP4
Models for high-fidelity multidimensional fuel performance analysis (se abrirá en una nueva ventana)Open source code and user’s guide of the new model developments concerning:•review and down-select available behavioural models,•develop a coupled modelling of stress and swelling in SCIANTIX,•open-source code for fission gas behaviour embedded in OFFBEAT•model for high-burnup structures in SCIANTIX, •extended cross-section lookup tables available in the burnup module of SCIANTIX•3D methodologies for the gap conductance, including the use of a view-factor approach for radiative heat transfer•models for cladding oxidation, hydrogen transport and geometric imperfections.
First Newsletter (se abrirá en una nueva ventana)First electronic newsletter
Results of TEM and SEM characterization of irradiated fuel before mechanical testing (se abrirá en una nueva ventana)The irradiated fuel samples tested in the mechanical set-up in task 1.1 will be characterized before the mechanical tests to measure their initial state. Images and measurements concern the dislocation densities (TEM), and the grain size and the orientations distribution (SEM).
Results from the boundary condition simulations and coupling of neutronics and thermal hydraulics to OFFBEAT (se abrirá en una nueva ventana)Neutronics and thermal hydraulics simulation results and associated boundary loading conditions for the fuel performance code OFFBEAT. Boundary loading conditions will be provided for representative irradiation conditions, as expected for the development and the validation in WP4 and WP5, with nominal irradiation including operating power transients, and design basis accidents such as LOCA and RIA. Detailed description of the methodology and associated open source codes.
Synthesis of first plenary EUG meeting (se abrirá en una nueva ventana)minutes of the meeting
Results from the fuel reference state calculations (se abrirá en una nueva ventana)Fuel reference state (i.e. chemical-physical material changes and the associated mechanical loading) evolution will be provided during representative loading condition under design basis accidents such as LOCA and RIA, as expected for the development and the validation in WP4 and WP5. Fuel data will be derived from validated 1.5D fuel performance codes.
Second Newsletter (se abrirá en una nueva ventana)second electronic newsletter
Mechanical laws for cladding, including based on results of INCA project for coated cladding (se abrirá en una nueva ventana)Mechanical models and material parameters describing thermo-elasticity, creep and rupture for zirconium alloys under irradiation, including coating behaviour for EATF claddings. Description of the state of the art data base and material parameter identification for Zirconium alloy. Reverse engineering methodology used for the coating mechanical law
Numerical and mathematical approaches for computation time reduction (se abrirá en una nueva ventana)Bibliographic report with a detailed analysis and description of computation time reduction methods based on machine learning models (MLM) with:•the Proper Orthogonal Decomposition (POD)•the Non-uniform Transformation Field Analysis (NTFA)•the Support Vector Machine approach (SVM)
Publicaciones
Autores:
Pau Aragón, Francisco Feria, Luis E. Herranz, Arndt Schubert, Paul Van Uffelen
Publicado en:
Annals of Nuclear Energy, Edición 211, 2024, ISSN 0306-4549
Editor:
Elsevier BV
DOI:
10.1016/j.anucene.2024.110950
Autores:
G. Zullo, D. Pizzocri, A. Scolaro, P. Van Uffelen, F. Feria, L.E. Herranz, L. Luzzi
Publicado en:
Journal of Nuclear Materials, Edición 601, 2024, ISSN 0022-3115
Editor:
Elsevier BV
DOI:
10.1016/J.JNUCMAT.2024.155305
Autores:
G. Zullo, D. Pizzocri, L. Luzzi
Publicado en:
Journal of Nuclear Materials, Edición 587, 2023, ISSN 0022-3115
Editor:
Elsevier BV
DOI:
10.1016/j.jnucmat.2023.154744
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