New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

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New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

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Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

Enhanced Solar-to-Fuel Efficiency of Ceria-Based Thermochemical Cycles via Integrated Electrochemical Oxygen Pumping

A Hybrid Approach to Neutron Transport with Thermal-hydraulic Feedback for Reactor Transient Analysis

Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications

A Coarse-mesh Methodology for the Analysis of One and Two-phase Nuclear Reactor Thermal-hydraulics in a Multi-physics Context

Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX

Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - Part I: Methodology demonstration

Techno-economic analysis and life cycle assessment of a biorefinery utilizing reductive catalytic fractionation

Delayed gamma fraction determination in the zero power reactor CROCUS

Towards the Validation of Noise Experiments in the CROCUS Reactor Using the TRIPOLI-4 Monte Carlo Code in Analog Mode

Scoping the characteristics and benefits of a connected double-null configuration for power exhaust in EU-DEMO