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Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

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Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

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

Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM

Extension of miniature neutron scintillators features in CROCUS: novel acquisition scheme and extended flux range

Preliminary analysis of the PETALE program and comparison to simulations

Highly localized azimuthal measurements in the CROCUS reactor towards the validaiton of high-fidelity neutronics codes

Experimental and numerical study of stochastic branching noise in nuclear reactors

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Development and verification of a methodology for neutron noise response to fuel assembly vibrations

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS