Nome |
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The molten salt reactor (MSR) in generation IV: Overview and perspectives, file e0c31c0d-6a55-4599-e053-1705fe0aef77
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2.214
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Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches, file e0c31c0d-c0f8-4599-e053-1705fe0aef77
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1.358
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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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815
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Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, file e0c31c0d-2fb9-4599-e053-1705fe0aef77
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624
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Fuel Modelling in Accident Conditions (FUMAC), file e0c31c0e-fee8-4599-e053-1705fe0aef77
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619
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Modelling and analysis of the MSFR transient behaviour, file e0c31c0d-d7dc-4599-e053-1705fe0aef77
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436
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DarkSide-20k Preliminary Design Report: The Global Argon Dark Matter Collaboration, file e0c31c11-287f-4599-e053-1705fe0aef77
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374
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A preliminary approach to the ALFRED reactor control strategy, file e0c31c0d-66e1-4599-e053-1705fe0aef77
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369
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Object-oriented modelling and simulation for the ALFRED dynamics, file e0c31c0d-6393-4599-e053-1705fe0aef77
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327
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Neutronic Benchmark of the Molten Salt Fast Reactor in the frame of the EVOL and MARS Collaborative Projects, file e0c31c0c-e3e6-4599-e053-1705fe0aef77
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311
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A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics, file e0c31c0e-779f-4599-e053-1705fe0aef77
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281
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Dynamic stability of natural circulation loops for single phase fluids with internal heat generation, file e0c31c0e-6273-4599-e053-1705fe0aef77
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236
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Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling, file e0c31c0e-7d2c-4599-e053-1705fe0aef77
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224
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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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217
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Vaporization behaviour of a PuF3-containing fuel mixture for the Molten Salt Fast Reactor, file e0c31c0f-346e-4599-e053-1705fe0aef77
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206
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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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Vaporization behaviour of the Molten Salt Fast Reactor fuel: The LiF-ThF4-UF4 system, file e0c31c0b-f8b3-4599-e053-1705fe0aef77
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176
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Synthesis of plutonium trifluoride by hydro-fluorination and novel thermodynamic data for the PuF3-LiF system, file e0c31c0b-c09f-4599-e053-1705fe0aef77
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162
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Innovative preparation route for uranium carbide using citric acid as a carbon source, file e0c31c09-cecb-4599-e053-1705fe0aef77
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151
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The solidification behaviour of the UO2-ThO2 system in a laser heating study, file e0c31c08-1e6f-4599-e053-1705fe0aef77
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149
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Development of the ALFRED reactor full power mode control system, file e0c31c0e-77a0-4599-e053-1705fe0aef77
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149
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Final report on rod cladding failure during SGTR, file eedd6d35-ee8e-41eb-a9f7-a64f0d904d50
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149
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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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146
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SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes, file e0c31c0f-4faa-4599-e053-1705fe0aef77
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146
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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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141
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The Role of Italian universities/CIRTEN for the engineering study of a fission-fusion hybrid reactor (FFHR), file e0c31c0a-7b8f-4599-e053-1705fe0aef77
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140
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A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77
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134
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DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS, file e0c31c0f-ff4d-4599-e053-1705fe0aef77
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125
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Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0f-3db2-4599-e053-1705fe0aef77
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123
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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation, file e0c31c0f-aa25-4599-e053-1705fe0aef77
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122
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Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, file e0c31c0b-9f7d-4599-e053-1705fe0aef77
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119
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Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant, file e0c31c0c-8282-4599-e053-1705fe0aef77
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109
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An Experimental Facility to Investigate the Natural Circulation Dynamics in Presence of Distributed Heat Sources, file e0c31c0a-38b1-4599-e053-1705fe0aef77
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108
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Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics, file e0c31c0d-d7dd-4599-e053-1705fe0aef77
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108
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Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor, file e0c31c08-1ec8-4599-e053-1705fe0aef77
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107
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Microhardness and Young's modulus of high burn-up UO2 fuel, file e0c31c09-bec0-4599-e053-1705fe0aef77
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103
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Spark plasma sintering of fine uranium carbide powder, file e0c31c09-fb14-4599-e053-1705fe0aef77
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97
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On the melting behaviour of calcium monoxide under different atmospheres: A laser heating study, file e0c31c0d-ead1-4599-e053-1705fe0aef77
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92
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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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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions, file e0c31c12-7f7d-4599-e053-1705fe0aef77
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84
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High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide, file e0c31c07-bdd7-4599-e053-1705fe0aef77
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77
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Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG, file e0c31c11-0a0c-4599-e053-1705fe0aef77
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75
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Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon, file e0c31c0f-6f93-4599-e053-1705fe0aef77
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74
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Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77
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74
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A preliminary approach to the MSFR control issues, file e0c31c0d-a8d6-4599-e053-1705fe0aef77
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72
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Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77
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72
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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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Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes, file e0c31c10-d8a9-4599-e053-1705fe0aef77
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63
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Isobaric heat capacity of solid and liquid thorium tetrafluoride, file e0c31c0f-2e56-4599-e053-1705fe0aef77
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61
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Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77
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60
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77
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57
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Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour, file e0c31c10-f6f8-4599-e053-1705fe0aef77
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56
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Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77
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53
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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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46
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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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42
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Laser melting of nano-crystalline uranium dioxide, file e0c31c0d-6892-4599-e053-1705fe0aef77
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40
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX, file 349fe6f6-fa64-44f8-aec3-7a8681055a88
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38
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS, file d13d261f-9f9a-4562-8111-6b2968efa829
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38
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Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions, file 4a4c0296-13dc-4e2c-b862-41e38364b1b6
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34
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Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents, file f4ebaf42-d062-4a67-8c8f-8800dc2da342
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32
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Synthesis of INSPYRE results, file d48a7793-5d73-4d02-95c2-ff437496291b
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30
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Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e7e10bd5-806d-4a25-bb59-2875e7d449d7
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30
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Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution, file e0c31c12-87ff-4599-e053-1705fe0aef77
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27
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On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation, file e0c31c12-e999-4599-e053-1705fe0aef77
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27
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Synthesis of the presentation of INSPYRE results to the User Group, file 9a0544ca-5818-490a-85d3-5a4c8b737046
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26
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Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77
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26
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A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure, file e0c31c0e-99d1-4599-e053-1705fe0aef77
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25
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Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77
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24
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Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77
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24
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Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data, file e0c31c11-831e-4599-e053-1705fe0aef77
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21
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Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study, file 67e60494-3ef6-499b-8963-3f77d2331374
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20
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SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range, file e0c31c11-2bf9-4599-e053-1705fe0aef77
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20
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Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating, file 38e09468-c997-40f3-ab61-818ae4e4f0aa
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18
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A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77
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18
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Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX, file 51c36818-c26d-4300-b58e-37b5bc8c7a52
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16
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On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error, file e0c31c12-4a03-4599-e053-1705fe0aef77
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16
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Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases, file fbc03e51-510d-4843-8083-35c8f07eddb4
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14
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Synthesis of the First User Group Meeting, file e0c31c11-000a-4599-e053-1705fe0aef77
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13
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Description of new meso-scale models and their implementation in fuel performance codes, file f6e82746-a87a-47b7-83bf-d9526b4bc972
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11
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Cryogenic Characterization of FBK RGB-HD SiPMs, file e0c31c0b-88d1-4599-e053-1705fe0aef77
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10
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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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Third Yearly Activity Report, file 0c5e3fa9-5fbd-42e1-9cb8-2743db035309
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9
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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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DarkSide-20k: A 20 tonne two-phase LAr TPC for direct dark matter detection at LNGS, file e0c31c0b-c015-4599-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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Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions, file e0c31c0f-0a02-4599-e053-1705fe0aef77
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9
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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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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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Towards multi-physics description of fuel behaviour for accidental conditions, file 0c5511c1-ac74-4094-926f-0b879e7fbf96
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5
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Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, file e0c31c08-1d4f-4599-e053-1705fe0aef77
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5
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Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop, file e0c31c0a-3ad7-4599-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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A surrogate model for the helium production rate in fast reactor MOX fuels, file 1888f666-30df-4998-9078-06f8d76bfe67
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4
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A modelling methodology for the description of helium behaviour accounting for the grain-size distribution, file 24714dd1-5353-40ed-89b1-d8ad52be28bc
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4
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Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F, file a6d0aca8-8468-4fbb-bb76-009d1762af4e
|
4
|
Best practices and QA protocols for code development, file c4e790d9-b3ed-40f8-999d-9fa78dd49637
|
4
|
A laser heating study of the CeO2 solid/liquid transition: challenges related to a refractory compound with a very high oxygen pressure, file e0c31c07-be20-4599-e053-1705fe0aef77
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4
|
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
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4
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Totale |
13.504 |