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CORDIS

OPEn HPC theRmomechanical tools for the development of eAtf fuels

CORDIS bietet Links zu öffentlichen Ergebnissen und Veröffentlichungen von HORIZONT-Projekten.

Links zu Ergebnissen und Veröffentlichungen von RP7-Projekten sowie Links zu einigen Typen spezifischer Ergebnisse wie Datensätzen und Software werden dynamisch von OpenAIRE abgerufen.

Leistungen

Plan for the Exploitation and Dissemination of Results (öffnet in neuem Fenster)

the report will describe the procedures for the exploitation of the results obtained during the project

Best practices and QA protocols for code development (öffnet in neuem Fenster)

Report describing best practices and QA protocols used for the open source code development in WP4

Models for high-fidelity multidimensional fuel performance analysis (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

First electronic newsletter

Results of TEM and SEM characterization of irradiated fuel before mechanical testing (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

minutes of the meeting

MMM advanced tool for mesoscale simulations of nuclear fuel (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

second electronic newsletter

Mechanical laws for fuel pellet creep and cracking at the microstructure and engineering (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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 (öffnet in neuem Fenster)

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)

Veröffentlichungen

OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions (öffnet in neuem Fenster)

Autoren: L. Verma, I. Clifford, P. Konarski, A. Scolaro, H. Ferroukhi
Veröffentlicht in: Annals of Nuclear Energy, Ausgabe 208, 2024, ISSN 0306-4549
Herausgeber: Elsevier BV
DOI: 10.1016/J.ANUCENE.2024.110773

Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel (öffnet in neuem Fenster)

Autoren: G. Zullo, A. Scolaro, T. Barani, D. Pizzocri
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 429, 2024, ISSN 0029-5493
Herausgeber: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2024.113602

A multi-fidelity multi-scale methodology to accelerate development of fuel performance codes (öffnet in neuem Fenster)

Autoren: D. Pizzocri, G. Zullo, G. Petrosillo, L. Luzzi, F. Feria, L.E. Herranz
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 432, 2025, ISSN 0029-5493
Herausgeber: Elsevier BV
DOI: 10.1016/J.NUCENGDES.2024.113741

Analysing hydrogen behaviour in liner claddings using OFFBEAT fuel performance code (öffnet in neuem Fenster)

Autoren: L. Verma, I. Clifford, P. Konarski, A. Scolaro, H. Ferroukhi
Veröffentlicht in: Annals of Nuclear Energy, Ausgabe 222, 2025, ISSN 0306-4549
Herausgeber: Elsevier BV
DOI: 10.1016/J.ANUCENE.2025.111559

Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/LOCA conditions (öffnet in neuem Fenster)

Autoren: Pau Aragón, Francisco Feria, Luis E. Herranz, Arndt Schubert, Paul Van Uffelen
Veröffentlicht in: Annals of Nuclear Energy, Ausgabe 211, 2024, ISSN 0306-4549
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: 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
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 615, 2025, ISSN 0022-3115
Herausgeber: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2025.155981

Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments (öffnet in neuem Fenster)

Autoren: Edoardo Luciano Brunetto, Alessandro Scolaro, Carlo Fiorina, Andreas Pautz
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 406, 2025, ISSN 0029-5493
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: Salvatore A. Cancemi, Andrius Ambrutis, Mantas Povilaitis, Rosa Lo Frano
Veröffentlicht in: Energies, Ausgabe 18, 2025, ISSN 1996-1073
Herausgeber: MDPI AG
DOI: 10.3390/EN18102557

MFEM/MGIS, a HPC mini-application targeting nonlinear thermo-mechanical simulations of nuclear fuels at mesoscale (öffnet in neuem Fenster)

Autoren: Thomas Helfer; Guillaume Latu; Raphaël Prat; Maxence Wangermez; Francesca Cuteri
Veröffentlicht in: Journal of Open Source Software, Ausgabe 10, 2025, ISSN 2475-9066
Herausgeber: creative commons
DOI: 10.21105/JOSS.07719

Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods (öffnet in neuem Fenster)

Autoren: G. Zullo, D. Pizzocri, A. Scolaro, P. Van Uffelen, F. Feria, L.E. Herranz, L. Luzzi
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 601, 2024, ISSN 0022-3115
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: Elisa Cappellari, Davide Pizzocri, Giovanni Zullo, Giovanni Nicodemo, Paul Van Uffelen, Arndt Schubert, Sophie Deanesi, Lelio Luzzi
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 617, 2025, ISSN 0022-3115
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: Matthieu Reymond, Jérôme Sercombe, Alessandro Scolaro
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 427, 2024, ISSN 0029-5493
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: Giovanni Nicodemo, Giovanni Zullo, Antonio Cammi, Lelio Luzzi, Davide Pizzocri
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 615, 2025, ISSN 0022-3115
Herausgeber: 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 (öffnet in neuem Fenster)

Autoren: Bruno Michel, Konstantina Lambrinou
Veröffentlicht in: EPJ Nuclear Sciences & Technologies, Ausgabe 11, 2025, ISSN 2491-9292
Herausgeber: 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" (öffnet in neuem Fenster)

Autoren: Jules-Elémir Suchorski, Adrien Pivano, Jonathan Amodeo
Veröffentlicht in: Acta Materialia, Ausgabe 287, 2025, ISSN 1359-6454
Herausgeber: Elsevier BV
DOI: 10.1016/J.ACTAMAT.2025.120771

The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments (öffnet in neuem Fenster)

Autoren: G. Zullo, D. Pizzocri, L. Luzzi
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 587, 2023, ISSN 0022-3115
Herausgeber: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154744

Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity (öffnet in neuem Fenster)

Autoren: Giovanni Nicodemo, Giovanni Zullo, Fabiola Cappia, Paul Van Uffelen, Alejandra De Lara, Lelio Luzzi, Davide Pizzocri
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 601, 2024, ISSN 0022-3115
Herausgeber: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2024.155301

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