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CORDIS - Resultados de investigaciones de la UE
CORDIS

OPEn HPC theRmomechanical tools for the development of eAtf fuels

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

Plan for the Exploitation and Dissemination of Results (se abrirá en una nueva ventana)

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.

Results of the verification activities (se abrirá en una nueva ventana)

Verification report of the tools developed in WP4 with•benchmark performed between OFFBEAT and existing 3D codes (ALCYONE, BISON) on specific study cases for which those codes are validated with experimental data. •verification of MMM and SPH codes by comparing their results to analytical calculations in simple configurations•verification of the large-strain solver, the gas conductance model and other developments made in WP4 on OFFBEAT•verification of the models linked to the coupling computational scheme OFFBEAT/SCIANTIX.

Synthesis of first plenary EUG meeting (se abrirá en una nueva ventana)

minutes of the meeting

MMM advanced tool for mesoscale simulations of nuclear fuel (se abrirá en una nueva ventana)

Open source code and user’s guide of the HPC 3D toolset named MMM for mesoscale simulations based on the open-source codes MFEM-MFront with:•functionalities for non-linear behaviour and for handling polycrystalline microstructures with a metallic phase at interfaces, and including the statistical distribution of porosities•a generation tool to build representative volume elements, including a staggered algorithm for the thermo-mechanics coupling and a phase field approach for fuel fragmentation•reader and writer routines for data exchange between OFFBEAT and MMM

Procedure for input data transfer in OFFBEAT (se abrirá en una nueva ventana)

Open source code and user’s guide of one-way coupling routines for 3D neutronics, thermal hydraulics and physical chemical calculations with the 3D thermomechanical simulation using the OFFBEAT code.

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 fuel pellet creep and cracking at the microstructure and engineering (se abrirá en una nueva ventana)

Mechanical models and material parameters describing thermo-elasticity, creep and rupture for oxide fuels. Mechanical laws will be provided for the two scales addressed in the simulation tools developed in WP4:•the mesoscale with single crystal viscoplasticity in UO2 and polycrystalline Representative Volume Element•the engineering scale with homogenized mechanical law focusing on the impact of heterogeneities induced by polycrystalline microstructure and porous microstructureDescription of the state of the art database used for the material parameter identification. Improvements and physical justifications based on small-scale simulation results of WP1.

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

OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions (se abrirá en una nueva ventana)

Autores: L. Verma, I. Clifford, P. Konarski, A. Scolaro, H. Ferroukhi
Publicado en: Annals of Nuclear Energy, Edición 208, 2024, ISSN 0306-4549
Editor: Elsevier BV
DOI: 10.1016/J.ANUCENE.2024.110773

Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel (se abrirá en una nueva ventana)

Autores: G. Zullo, A. Scolaro, T. Barani, D. Pizzocri
Publicado en: Nuclear Engineering and Design, Edición 429, 2024, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2024.113602

A multi-fidelity multi-scale methodology to accelerate development of fuel performance codes (se abrirá en una nueva ventana)

Autores: D. Pizzocri, G. Zullo, G. Petrosillo, L. Luzzi, F. Feria, L.E. Herranz
Publicado en: Nuclear Engineering and Design, Edición 432, 2025, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2024.113741

Analysing hydrogen behaviour in liner claddings using OFFBEAT fuel performance code (se abrirá en una nueva ventana)

Autores: L. Verma, I. Clifford, P. Konarski, A. Scolaro, H. Ferroukhi
Publicado en: Annals of Nuclear Energy, Edición 222, 2025, ISSN 0306-4549
Editor: Elsevier BV
DOI: 10.1016/J.ANUCENE.2025.111559

Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/LOCA conditions (se abrirá en una nueva ventana)

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

Experimental characterizations by EBSD and TEM of sub-grain boundaries and dislocations in low irradiated UO2 fuels (se abrirá en una nueva ventana)

Autores: C. Onofri, I. Zacharie-Aubrun, D. Drouan, T. Blay, C. Sabathier, T. Grenèche, K. Hanifi, C. Rodriguez, L. Fayette, S. Reboul, N. Robert, P. Binet, M. Bertolus
Publicado en: Journal of Nuclear Materials, Edición 615, 2025, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2025.155981

Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments (se abrirá en una nueva ventana)

Autores: Edoardo Luciano Brunetto, Alessandro Scolaro, Carlo Fiorina, Andreas Pautz
Publicado en: Nuclear Engineering and Design, Edición 406, 2025, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2023.112232

AI-Powered Convolutional Neural Network Surrogate Modeling for High-Speed Finite Element Analysis in the NPPs Fuel Performance Framework (se abrirá en una nueva ventana)

Autores: Salvatore A. Cancemi, Andrius Ambrutis, Mantas Povilaitis, Rosa Lo Frano
Publicado en: Energies, Edición 18, 2025, ISSN 1996-1073
Editor: MDPI AG
DOI: 10.3390/EN18102557

MFEM/MGIS, a HPC mini-application targeting nonlinear thermo-mechanical simulations of nuclear fuels at mesoscale (se abrirá en una nueva ventana)

Autores: Thomas Helfer; Guillaume Latu; Raphaël Prat; Maxence Wangermez; Francesca Cuteri
Publicado en: Journal of Open Source Software, Edición 10, 2025, ISSN 2475-9066
Editor: creative commons
DOI: 10.21105/JOSS.07719

Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods (se abrirá en una nueva ventana)

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

On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation (se abrirá en una nueva ventana)

Autores: Elisa Cappellari, Davide Pizzocri, Giovanni Zullo, Giovanni Nicodemo, Paul Van Uffelen, Arndt Schubert, Sophie Deanesi, Lelio Luzzi
Publicado en: Journal of Nuclear Materials, Edición 617, 2025, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2025.156116

Investigation of the PCMI failure of pre-hydrided Zy-4 cladding during Reactivity Initiated Accidents with ALCYONE and OFFBEAT fuel performance codes (se abrirá en una nueva ventana)

Autores: Matthieu Reymond, Jérôme Sercombe, Alessandro Scolaro
Publicado en: Nuclear Engineering and Design, Edición 427, 2024, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2024.113430

Data assimilation for accelerated development of fuel performance codes: Towards automatic implementation of material properties correlations (se abrirá en una nueva ventana)

Autores: Giovanni Nicodemo, Giovanni Zullo, Antonio Cammi, Lelio Luzzi, Davide Pizzocri
Publicado en: Journal of Nuclear Materials, Edición 615, 2025, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2025.155954

OperaHPC & SCORPION: accelerated optimization of advanced fuels for Gen-II/III reactors via the synergy of high-performance computing with multiscale material engineering (se abrirá en una nueva ventana)

Autores: Bruno Michel, Konstantina Lambrinou
Publicado en: EPJ Nuclear Sciences & Technologies, Edición 11, 2025, ISSN 2491-9292
Editor: EDP Sciences
DOI: 10.1051/EPJN/2025040

"On the influence of temperature on the 1/2<mml:math xmlns:mml=""http://www.w3.org/1998/Math/MathML"" altimg=""si125.svg"" display=""inline"" id=""d1e451""><mml:mrow><mml:mo>&lt;</mml:mo><mml:mn>110</mml:mn><m" (se abrirá en una nueva ventana)

Autores: Jules-Elémir Suchorski, Adrien Pivano, Jonathan Amodeo
Publicado en: Acta Materialia, Edición 287, 2025, ISSN 1359-6454
Editor: Elsevier BV
DOI: 10.1016/J.ACTAMAT.2025.120771

The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments (se abrirá en una nueva ventana)

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

Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity (se abrirá en una nueva ventana)

Autores: Giovanni Nicodemo, Giovanni Zullo, Fabiola Cappia, Paul Van Uffelen, Alejandra De Lara, Lelio Luzzi, Davide Pizzocri
Publicado en: Journal of Nuclear Materials, Edición 601, 2024, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2024.155301

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