| Nome |
# |
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Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c0d-8364-4599-e053-1705fe0aef77
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842
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A preliminary approach to the ALFRED reactor control strategy, file e0c31c0d-66e1-4599-e053-1705fe0aef77
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375
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Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c0d-6393-4599-e053-1705fe0aef77
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335
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Development of a control-oriented power plant simulator for the molten salt fast reactor, file e0c31c0f-0215-4599-e053-1705fe0aef77
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247
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POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations, file e0c31c11-269a-4599-e053-1705fe0aef77
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230
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Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor, file e0c31c0f-0c3f-4599-e053-1705fe0aef77
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220
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An Adjoint Proper Orthogonal Decomposition method for a neutronics reduced order model, file e0c31c0f-2191-4599-e053-1705fe0aef77
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207
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Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor, file e0c31c0d-1f54-4599-e053-1705fe0aef77
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200
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A Monte Carlo-based exploration framework for identifying components vulnerable to cyber threats in nuclear power plants, file e0c31c0b-d933-4599-e053-1705fe0aef77
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189
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Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors, file e0c31c10-2877-4599-e053-1705fe0aef77
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173
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POD-Galerkin reduced order methods for CFD using Finite Volume Discretisation: vortex shedding around a circular cylinder, file e0c31c0c-22e0-4599-e053-1705fe0aef77
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168
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Preliminary analysis and design of the energy conversion system for the molten salt fast reactor, file e0c31c10-6076-4599-e053-1705fe0aef77
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167
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Development of the ALFRED reactor full power mode control system, file e0c31c0e-77a0-4599-e053-1705fe0aef77
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162
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Multiphysics analysis of the MSFR helium bubbling system: A comparison between neutron diffusion, SP3 neutron transport and Monte Carlo approaches, file e0c31c0d-7420-4599-e053-1705fe0aef77
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150
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Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor, file e0c31c0c-7580-4599-e053-1705fe0aef77
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140
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An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response, file e0c31c0c-ac7b-4599-e053-1705fe0aef77
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138
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An Initiative for the Development and Application of Open-source Multi-physics Simulation in Support of R&D and E&T in Nuclear Science and Technology, file e0c31c10-6e29-4599-e053-1705fe0aef77
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126
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Development of a CFD – LES model for the dynamic analysis of the DYNASTY natural circulation loop, file e0c31c11-9580-4599-e053-1705fe0aef77
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123
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Simplified 0-D semi-analytical model for fuel draining in molten salt reactors, file e0c31c0f-24f1-4599-e053-1705fe0aef77
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117
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Study of an intrinsically safe infrastructure for training and
research on nuclear technologies, file e0c31c0c-e9f5-4599-e053-1705fe0aef77
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112
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Void Coefficient Sensitivity Analysis for the Triga Mark II Reactor at L.E.N.A. (UniPV), file e0c31c10-3771-4599-e053-1705fe0aef77
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99
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A Reduced Order Kalman Filter for Computational Fluid-Dynamics Applications, file e0c31c0d-77cd-4599-e053-1705fe0aef77
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92
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A mass conservative Kalman filter algorithm for computational thermo-fluid dynamics, file e0c31c0c-ab93-4599-e053-1705fe0aef77
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91
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Development of best estimate numerical tools for LFR design and safety analysis, file e0c31c11-2334-4599-e053-1705fe0aef77
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85
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An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purposes, file e0c31c12-3088-4599-e053-1705fe0aef77
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71
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Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor, file e0c31c0e-77a7-4599-e053-1705fe0aef77
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66
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ALFRED reactor and hybrid systems: A test case, file 3041902a-f265-4360-83ff-2e0aac260999
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65
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Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor, file e0c31c12-c914-4599-e053-1705fe0aef77
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65
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Object-oriented modeling, simulation and control of a 6-DoF parallel kinematic manipulator for remote handling in DONES facility, file b1c0ca38-3539-4a4f-a2f9-b6ae02e94910
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50
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Development of a reduced order model for fuel burnup analysis, file e0c31c10-6e27-4599-e053-1705fe0aef77
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50
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On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives, file e0c31c12-512d-4599-e053-1705fe0aef77
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50
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Multiphysics analysis of RANS-based turbulent transport of solid fission products in the Molten Salt Fast Reactor, file e0c31c12-cc35-4599-e053-1705fe0aef77
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47
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A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor, file e0c31c0e-83ce-4599-e053-1705fe0aef77
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44
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A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors, file e0c31c11-730b-4599-e053-1705fe0aef77
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44
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Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor, file 2053c5be-1ebc-43f3-b714-ddf19fbeff80
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41
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Derivation and Implementation in OpenFOAM of a Point-Kinetics Model for Molten Salt Reactors, file 652630d5-12a5-4d40-9611-9b936c62f762
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40
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Modelling and CFD analysis of the DYNASTY loop facility, file 40058902-3004-45e3-9a11-8a055fe929ad
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32
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Development of an OpenFOAM multiphysics solver for solid fission products transport in the Molten Salt Fast Reactor, file 1e646d31-6508-48e3-9286-e61b83896f1e
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19
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Numerical methodology for design and evaluation of natural circulation systems for MSR applications, file 971a79bd-78c2-41ce-a656-a2b86c2da698
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16
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An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics, file e0c31c0e-2704-4599-e053-1705fe0aef77
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16
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Analysis of the Effect of Fuel Compressibility on Super-Prompt-Critical Dynamics of the Molten Salt Fast Reactor, file e0c31c0c-de49-4599-e053-1705fe0aef77
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10
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POD-Galerkin method for finite volume approximation of Navier-Stokes and RANS equations, file e0c31c09-c080-4599-e053-1705fe0aef77
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9
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Analysis of the Void Reactivity Effect in the Molten Salt Fast Reactor: Impact of the Helium Bubbling System, file e0c31c0d-432c-4599-e053-1705fe0aef77
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9
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On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors, file a22a1d70-9d2f-458b-8f8f-8f10282cba2d
|
8
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An OpenFOAM Solver for Criticality Safety Assessment in Dynamic Compression Events, file e0c31c0c-fcc9-4599-e053-1705fe0aef77
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7
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Design and Safety Studies of the Molten Salt Fast Reactor Concept in the Frame of the SAMOFAR H2020 Project, file e0c31c0d-86b2-4599-e053-1705fe0aef77
|
7
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Reduced Order Methods for the Improvement of Control-Oriented Modelling of Nuclear Power Plants, file e0c31c0b-29e5-4599-e053-1705fe0aef77
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6
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An Euler-Euler Multiphysics Solver for the Analysis of the Helium Bubbling System in the MSFR, file e0c31c0b-9728-4599-e053-1705fe0aef77
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6
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Linear Stability Analysis of a Heated Channel in the Supercritical Water Reactor, file e0c31c0c-0af2-4599-e053-1705fe0aef77
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6
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Sensitivity And Uncertainty Analysis of the TRIGA Mark II Reactor Using First and Second Order Perturbation Theory, file e0c31c0f-35a3-4599-e053-1705fe0aef77
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6
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Modeling and simulation of nuclear hybrid energy systems architectures, file 9e6ae74b-1fbf-4a60-a67d-854d74334f74
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5
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Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator, file e0c31c0b-e0bb-4599-e053-1705fe0aef77
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5
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A CFD-based simulation tool for the stability analysis of natural circulation systems, file e0c31c0e-d903-4599-e053-1705fe0aef77
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5
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1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop, file 7819fe50-ef53-47be-b12b-ed31a1c216c4
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4
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Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c08-1def-4599-e053-1705fe0aef77
|
4
|
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Development of the ALFRED reactor full power mode control system, file e0c31c09-54b7-4599-e053-1705fe0aef77
|
4
|
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Multi-physics tools development, file e0c31c0b-02b4-4599-e053-1705fe0aef77
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4
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Development of a power plant simulator, file e0c31c0b-290c-4599-e053-1705fe0aef77
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4
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Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core, file e0c31c10-2b5a-4599-e053-1705fe0aef77
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4
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Flow pattern visualization and definition of transition criteria for two-phase flow in Chevron-type corrugated channels, file 3b8d4232-4c5d-41f0-a207-ba63072f144f
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3
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Numerical Modeling and Simulation of Melting Phenomena for Freeze Valve Analysis in Molten Salt Reactors, file 89098f12-57ba-4d30-b705-1ae63bbb9e91
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3
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A reduced order model for fission gas diffusion in columnar grains, file c302733e-ec86-4a6f-b53d-00bf256fb749
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3
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Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c08-14e3-4599-e053-1705fe0aef77
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3
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A preliminary approach to the ALFRED reactor control strategy, file e0c31c08-19a8-4599-e053-1705fe0aef77
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3
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Study of a low-power, fast-neutron-based ADS, file e0c31c08-494b-4599-e053-1705fe0aef77
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3
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A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor, file e0c31c08-5d87-4599-e053-1705fe0aef77
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3
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ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY, file e0c31c09-c17a-4599-e053-1705fe0aef77
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3
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Improvement of the Control-Oriented Modelling of the GEN-IV Lead-Cooled Fast Reactor: Development of Reduced Order Methods, file e0c31c0a-4b66-4599-e053-1705fe0aef77
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3
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A reduced order model for investigating the dynamics of the Gen-IV LFR coolant pool, file e0c31c0a-4d20-4599-e053-1705fe0aef77
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3
|
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Development of a Data-Driven Approach Based on Kalman Filtering for CFD Reactor Analysis, file e0c31c0d-29e3-4599-e053-1705fe0aef77
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3
|
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Effects of a multi-physics coupling approach in Monte Carlo burnup calculations, file e0c31c0d-5b9f-4599-e053-1705fe0aef77
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3
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Complete Thermal-Hydraulic Modelling of the Pavia TRIGA Mark II Research Reactor for the Study of the Natural Circulation Regime, file e0c31c0d-7ac5-4599-e053-1705fe0aef77
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3
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Analysis of the Operational and Safety Features of the In-Core Bubbling System of the Molten Salt Fast Reactor, file 5914799c-c8a5-48ce-9458-73f50baeeeaa
|
2
|
|
ELSMOR – towards European Licensing of Small Modular Reactors: Methodology recommendations for light-water small modular reactors safety assessment, file 732c5e95-c7df-41e3-8381-96a3614d411f
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2
|
|
Analysis of the void coefficient in Pavia TRIGA Mark-II reactor: Monte Carlo numerical evaluation and comparison with experimental data, file cf9e3669-c043-42b7-86cc-8317345879dc
|
2
|
|
An intrinsically safe facility for forefront research and training on nuclear technologies — Kinetics and dynamics, file e0c31c08-2185-4599-e053-1705fe0aef77
|
2
|
|
Control approach to the load frequency regulation of a Generation IV Lead-cooled Fast Reactor, file e0c31c08-4e01-4599-e053-1705fe0aef77
|
2
|
|
Spatial neutronics modelling to evaluate the temperature reactivity feedbacks in a Lead-cooled Fast Reactor, file e0c31c09-4169-4599-e053-1705fe0aef77
|
2
|
|
Description of initial reference design and identification of safety aspects, file e0c31c0a-8027-4599-e053-1705fe0aef77
|
2
|
|
A Serpent/OpenFOAM coupling approach for the study of the fuel burnup, file e0c31c0b-c38a-4599-e053-1705fe0aef77
|
2
|
|
A 3D CFD Model for the Study of Natural Circulation in the Pavia TRIGA Mark II Research Reactor, file e0c31c0b-edfc-4599-e053-1705fe0aef77
|
2
|
|
Instabilities of burnup calculations in a SERPENT/OPENFOAM coupling, file e0c31c0d-5e51-4599-e053-1705fe0aef77
|
2
|
|
Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant, file e0c31c11-957f-4599-e053-1705fe0aef77
|
2
|
|
Assessment of the integrated mass conservative Kalman filter algorithm for Computational Thermo-Fluid Dynamics on the TRIGA Mark II reactor, file e0c31c11-ddca-4599-e053-1705fe0aef77
|
2
|
|
Reduced order modeling for coupled thermal-hydraulics and reactor physics problems, file e0c31c11-ddcb-4599-e053-1705fe0aef77
|
2
|
|
Large Eddy Simulation of the Dynamic Behaviour of the Dynasty Natural Circulation Loop, file 1f72d662-9746-4509-9d74-5a614111242d
|
1
|
|
Dynamics of Natural Circulation in Presence of Distributed Heating: Results of the SAMOFAR CFD Simulation Campaign, file 2cf5eb6e-dd85-443e-870f-86e398f5804e
|
1
|
|
1D Modelica Modeling of the DYNASTY-eDYNASTY Coupled Natural Circulation Loops, file cf2ac903-5188-463a-8e67-a893bf5bdb6b
|
1
|
|
Definition and Selection of Transients, file e0c31c0a-7ae6-4599-e053-1705fe0aef77
|
1
|
|
Comparison of Several RANS Modelling for the Pavia TRIGA Mark II Research Reactor, file e0c31c0c-01bd-4599-e053-1705fe0aef77
|
1
|
|
Verification and Validation studies, file e0c31c0c-5bf3-4599-e053-1705fe0aef77
|
1
|
|
A multi-physics modelling approach for the analysis of Lead Fast Reactors, file e0c31c0d-58a1-4599-e053-1705fe0aef77
|
1
|
|
Dynamic Mode Decomposition for the Control of Nuclear Power Plants, file e0c31c0d-58a2-4599-e053-1705fe0aef77
|
1
|
|
An improved zero-dimensional model for simulation of TRIGA Mark II dynamic response, file e0c31c0f-243f-4599-e053-1705fe0aef77
|
1
|
|
Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method, file e0c31c0f-2dde-4599-e053-1705fe0aef77
|
1
|
|
Requirements of LES in Modelling Natural Circulation Loops: Preliminary Study in a Pipe Geometry, file e0c31c10-bd17-4599-e053-1705fe0aef77
|
1
|
|
An empirical interpolation method for two-dimensional vector fields and vector measurements, file e0c31c11-6eb2-4599-e053-1705fe0aef77
|
1
|
|
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System, file e0c31c11-9c65-4599-e053-1705fe0aef77
|
1
|
| Totale |
5.695 |