Paolo Vinai
Visar 62 publikationer
On the use of neutron flux gradient with ANNs for the detection of diverted spent nuclear fuel
On the simulation of neutron noise induced by vibrations of fuel pins in a fuel assembly
Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Sensitivity analysis in core diagnostics
Modelling and simulations of reactor neutron noise induced by mechanical vibrations
Ringhals Diagnostics and Monitoring, Annual Research Report 2021-2022
Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
Understanding xenon oscillations through physics-based Reduced Order Modelling
Machine learning for analysis of real nuclear plant data in the frequency domain
Conceptual design and initial evaluation of a neutron flux gradient detector
CORE SIM+: A flexible diffusion-based solver for neutron noise simulations
On the simulation of neutron noise using a discrete ordinates method
Development and test of a novel neutronic verification scheme for Molten Salt Reactors
Analysis of the neutron noise induced by fuel assembly vibrations
Monte Carlo-based dynamic calculations of stationary perturbations
Numerical solution of two-energy-group neutron noise diffusion problems with fine spatial meshes
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
Neutron noise-based anomaly classification and localization using machine learning
Two-level multigrid preconditioning of a neutron noise diffusion solver
Development of a frequency-domain reactor noise simulator based on a neutron transport method
JHR neutron deterministic calculation scheme improvement thanks to Monte Carlo analysis in depletion
Neutron noise modelling for nuclear reactor diagnostics
A deep learning approach to anomaly detection in nuclear reactors
Overview of the CORTEX project
Noise-based core monitoring and diagnostics – Overview of the CORTEX project
A deterministic against Monte-Carlo depletion calculation benchmark for JHR core configurations
A numerical framework for bubble transport in a subcooled fluid flow
Assessment of Critical Heat Flux correlations in narrow rectangular channels
A Two-fluid/DQMOM Methodology for Condensation in Bubbly Flow
On the prediction of single-phase forced convection heat transfer in narrow rectangular channels
Influence of an SN solver in a fine-mesh neutronics/thermal- hydraulics framework
Building a comprehensive nuclear education in Sweden
On the possible dependence of the decay ratio on the void reactivity feedback
An Assesment Study of the POLCA-T Code Based on NUPEC Data
An assessment study of the POLCA-T code based on NUPEC data
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Visar 8 forskningsprojekt
Nukleär icke-spridning och kärnämneskontroll
Core monitoring and diagnostics in SMRs using reactor neutron noise and machine learning
A new approach to partial defect testing of spent nuclear fuel for safeguards applications
Studier av härdstabilitet vid lastföljning med ROM-metoder
DEterministisk MOdellering av Jules HorowitzReaktorn (DEMO-JHR)
Planering för infrastrukturerna MYRRHA och ELECTRA (PRIME)