OPEn HPC theRmomechanical tools for the development of eAtf fuels

Project Information

OperaHPC

Grant agreement ID: 101061453

EC signature date 22 July 2022

Start date 1 November 2022

End date 30 April 2027

Funded under

• Euratom Research and Training Programme (EURATOM)

Total cost

€ 4 515 551,70

EU contribution

€ 2 846 944,00

Coordinated by

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

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Deliverables

Documents, reports (11)

Plan for the Exploitation and Dissemination of Results

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

Best practices and QA protocols for code development

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

Models for high-fidelity multidimensional fuel performance analysis

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

First electronic newsletter

Results of TEM and SEM characterization of irradiated fuel before mechanical testing

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

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

minutes of the meeting

Results from the fuel reference state calculations

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

second electronic newsletter

Mechanical laws for cladding, including based on results of INCA project for coated cladding

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

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)

Publications

Peer reviewed articles (3)

Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/LOCA conditions

Author(s): Pau Aragón, Francisco Feria, Luis E. Herranz, Arndt Schubert, Paul Van Uffelen
Published in: Annals of Nuclear Energy, Issue 211, 2024, ISSN 0306-4549
Publisher: Elsevier BV
DOI: 10.1016/j.anucene.2024.110950

Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods

Author(s): G. Zullo, D. Pizzocri, A. Scolaro, P. Van Uffelen, F. Feria, L.E. Herranz, L. Luzzi
Published in: Journal of Nuclear Materials, Issue 601, 2024, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/J.JNUCMAT.2024.155305

The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments

Author(s): G. Zullo, D. Pizzocri, L. Luzzi
Published in: Journal of Nuclear Materials, Issue 587, 2023, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154744