| Nome |
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Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor, file e384c42f-df00-d4b2-e053-9f05fe0a1d67
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312
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DTT - Divertor Tokamak Test facility - Interim Design Report, file e384c430-c89f-d4b2-e053-9f05fe0a1d67
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292
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Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors, file e384c42e-ed18-d4b2-e053-9f05fe0a1d67
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267
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Performance analysis of a graded winding pack design for the EU DEMO TF coil in normal and off-normal conditions, file e384c42f-e555-d4b2-e053-9f05fe0a1d67
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233
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Effects of RANS-Type turbulence models on the convective heat loss computed by CFD in the solar two power tower, file e384c42e-352e-d4b2-e053-9f05fe0a1d67
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229
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Overview of the hydraulic characteristics of the ITER Central Solenoid Model Coil conductors after 15 years of test campaigns, file e384c42f-e0c4-d4b2-e053-9f05fe0a1d67
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213
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Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor, file e384c42f-e0c7-d4b2-e053-9f05fe0a1d67
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158
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Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation, file e384c431-d466-d4b2-e053-9f05fe0a1d67
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123
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Modeling of W7-X superconducting coil cool-down using the 4C code, file e384c42e-7aad-d4b2-e053-9f05fe0a1d67
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84
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Artificial Neural Networks: a viable tool to design heat load smoothing strategies for the ITER Toroidal Field coils, file e384c431-d469-d4b2-e053-9f05fe0a1d67
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80
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Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit, file e384c42f-df56-d4b2-e053-9f05fe0a1d67
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79
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4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil, file e384c42f-f985-d4b2-e053-9f05fe0a1d67
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75
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Progress in the design of the superconducting magnets for the EU DEMO, file e384c430-749c-d4b2-e053-9f05fe0a1d67
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69
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Thermal-hydraulic test and analysis of the ENEA TF conductor sample for the EU DEMO fusion reactor, file e384c430-107c-d4b2-e053-9f05fe0a1d67
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62
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4C code simulation and benchmark of ITER TF magnet cool-down from 300 K to 80 K, file e384c42e-7aae-d4b2-e053-9f05fe0a1d67
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54
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DTT device: Conceptual design of the superconducting magnet system, file e384c42f-df8a-d4b2-e053-9f05fe0a1d67
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51
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Thermal-hydraulic analysis of the DTT Toroidal Field magnets in DC operation, file e384c431-97c6-d4b2-e053-9f05fe0a1d67
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49
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Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code, file e384c42f-e36b-d4b2-e053-9f05fe0a1d67
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44
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Quench propagation in a TF coil of the EU DEMO, file e384c42f-e524-d4b2-e053-9f05fe0a1d67
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42
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Coupling superconducting magnet and refrigerator thermal-hydraulic models for nuclear fusion applications, file e384c431-97c2-d4b2-e053-9f05fe0a1d67
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40
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Analysis of the DC performance of the ITER CSI coil using the 4C code, file e384c42f-e554-d4b2-e053-9f05fe0a1d67
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30
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Integrated deterministic and probabilistic safety assessment of the cooling circuit of a superconducting magnet for nuclear fusion applications, file e384c431-8463-d4b2-e053-9f05fe0a1d67
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27
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Development of a Thermal-Hydraulic Model for the European DEMO TF Coil, file e384c433-552b-d4b2-e053-9f05fe0a1d67
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27
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Identification of the Postulated Initiating Events of Accidents Occurring in a Toroidal Field Magnet of the EU DEMO, file e384c431-b5c6-d4b2-e053-9f05fe0a1d67
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25
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Artificial neural network model for the thermal-hydraulic response of a TF superconducting magnet in ITER, file e384c42e-80a6-d4b2-e053-9f05fe0a1d67
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24
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Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient, file e384c432-fb61-d4b2-e053-9f05fe0a1d67
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21
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Modeling the ITER CS AC Losses Based on the CS Insert Analysis, file e384c431-acca-d4b2-e053-9f05fe0a1d67
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20
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Development of the H4C Model of Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor, file e384c433-ccd9-d4b2-e053-9f05fe0a1d67
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20
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Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code, file ca660a9e-e998-4a65-981e-05377c35422d
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17
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Metamodeling and on-line clustering for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit, file e384c433-e65e-d4b2-e053-9f05fe0a1d67
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16
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Thermal-Hydraulic Analysis of the JT-60SA Central Solenoid Operation, file e384c431-acc8-d4b2-e053-9f05fe0a1d67
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15
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Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation, file e384c432-17ca-d4b2-e053-9f05fe0a1d67
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14
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Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector, file f81f56ff-48ff-4430-9d4c-033ec5f9bada
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11
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4C Code Analysis of High-Margin Quench Propagation in a DEMO TF Coil, file e384c42e-9d82-d4b2-e053-9f05fe0a1d67
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10
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Integrated design strategy for EU-DEMO first wall protection from plasma transients, file e384c434-65f0-d4b2-e053-9f05fe0a1d67
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10
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Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector, file 3e6bcbac-712c-4f6c-8c2b-898bd1cd80e2
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9
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PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS, file e384c432-c3fb-d4b2-e053-9f05fe0a1d67
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8
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Advanced methods for loss-of-flow accident precursors identification in a superconducting magnet cryogenic cooling circuit, file e384c434-b40a-d4b2-e053-9f05fe0a1d67
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8
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Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code, file e384c42f-e36a-d4b2-e053-9f05fe0a1d67
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7
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Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test, file 58bd6de6-ddfd-46e2-b12b-793ae807d634
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6
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Overview of Progress on the EU DEMO Reactor Magnet System Design, file e384c42f-03b9-d4b2-e053-9f05fe0a1d67
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6
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Analysis of a Loss-of-Flow Accident (LOFA) in a tokamak superconducting toroidal field coil, file e384c42f-8781-d4b2-e053-9f05fe0a1d67
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6
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Quench propagation in a TF coil of the EU DEMO, file e384c42f-e523-d4b2-e053-9f05fe0a1d67
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6
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Modelling the PbLi flow including tritium transport and permeation with GETTHEM, file f45af58c-ec11-45e8-9577-63e1fbe47cba
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6
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3D-FOX—A 3D Transient Electromagnetic Code for Eddy Currents Computation in Superconducting Magnet Structures: DTT TF Fast Current Discharge Analysis, file fcf2cc2a-b53c-43b2-9a4c-f53436b68991
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6
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Thermal-hydraulic analysis of transients in the HELIOS loop including a CICC section representative of the JT-60SA Central Solenoid, file e384c42e-78d0-d4b2-e053-9f05fe0a1d67
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5
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PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS, file e384c42e-817c-d4b2-e053-9f05fe0a1d67
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5
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Analysis of AC Losses in the ITER Central Solenoid Insert Coil, file e384c42f-4441-d4b2-e053-9f05fe0a1d67
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5
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Analysis of the DC performance of the ITER CSI coil using the 4C code, file e384c42f-dfbf-d4b2-e053-9f05fe0a1d67
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5
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Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor, file e384c432-4b75-d4b2-e053-9f05fe0a1d67
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5
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The DEMO magnet system – Status and future challenges, file e384c434-631d-d4b2-e053-9f05fe0a1d67
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5
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Erratum: Integrated design strategy for EU-DEMO first wall protection from plasma transients (Fusion Engineering and Design (2022) 177, (113067) (S0920379622000679), (10.1016/j.fusengdes.2022.113067)), file 7eeaf873-6652-4587-8274-1fa9547ddf79
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4
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Dynamic modeling of a Supercritical Helium closed loop with the 4C code, file e384c42e-146d-d4b2-e053-9f05fe0a1d67
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4
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A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors, file e384c42e-269f-d4b2-e053-9f05fe0a1d67
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4
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Verification of the Predictive Capabilities of the 4C Code Cryogenic Circuit Model, file e384c42e-2d7d-d4b2-e053-9f05fe0a1d67
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4
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Development of a Thermal-Hydraulic Model for the European DEMO TF Coil, file e384c42e-becc-d4b2-e053-9f05fe0a1d67
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4
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Analysis of the cooldown of the ITER central solenoid model coil and insert coil, file e384c42f-4198-d4b2-e053-9f05fe0a1d67
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4
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Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes, file e384c42f-4b8a-d4b2-e053-9f05fe0a1d67
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4
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DTT device: Conceptual design of the superconducting magnet system, file e384c42f-e3cf-d4b2-e053-9f05fe0a1d67
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4
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Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient, file e384c42f-e869-d4b2-e053-9f05fe0a1d67
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4
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Design and optimization of Artificial Neural Networks for the modelling of superconducting magnets operation in tokamak fusion reactors, file e384c430-0a15-d4b2-e053-9f05fe0a1d67
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4
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AC Losses in the First ITER CS Module Tests: Experimental Results and Comparison to Analytical Models, file e384c434-a018-d4b2-e053-9f05fe0a1d67
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4
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Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector, file 374bb9fa-f6eb-4633-9870-01baf8e0c3cc
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3
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Computation of JT-60SA TF coil temperature margin using the 4C code, file e384c42e-16d1-d4b2-e053-9f05fe0a1d67
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3
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Mitigation of the Temperature Margin Reduction due to the Nuclear Radiation on the ITER TF Coils, file e384c42e-23e6-d4b2-e053-9f05fe0a1d67
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3
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CFD analysis of a regular sector of the ITER vacuum vessel. Part I: Flow distribution and pressure drop, file e384c42e-2bb9-d4b2-e053-9f05fe0a1d67
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3
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Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin, file e384c42e-2d79-d4b2-e053-9f05fe0a1d67
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3
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Evaluation of the neutron activation of JET in-vessel components following DT irradiation, file e384c42e-30f1-d4b2-e053-9f05fe0a1d67
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3
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Application of the 4C code to the thermal-hydraulic analysis of the CS superconducting magnets in EAST, file e384c42e-344e-d4b2-e053-9f05fe0a1d67
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3
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Validation of the 4C Thermal-Hydraulic Code against 25 kA Safety Discharge in the ITERToroidal Field Model Coil (TFMC), file e384c42e-7e17-d4b2-e053-9f05fe0a1d67
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3
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ITER Central Solenoid Insert Test Results, file e384c42e-97bf-d4b2-e053-9f05fe0a1d67
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3
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Analyses of low- and high-margin Quench Propagation in the European DEMO TF Coil Winding Pack, file e384c42f-1300-d4b2-e053-9f05fe0a1d67
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3
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Analysis of the ITER central solenoid insert (CSI) coil stability tests, file e384c42f-867c-d4b2-e053-9f05fe0a1d67
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3
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Characterization of the ITER CS conductor and projection to the ITER CS performance, file e384c42f-e86a-d4b2-e053-9f05fe0a1d67
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3
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Performance analysis of the NbTi PF coils for the EU DEMO fusion reactor, file e384c42f-eafd-d4b2-e053-9f05fe0a1d67
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3
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Progress in the design of the superconducting magnets for the EU DEMO, file e384c430-749b-d4b2-e053-9f05fe0a1d67
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3
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Modeling Quench Propagation in the ENEA HTS Cable-In-Conduit Conductor, file e384c432-81db-d4b2-e053-9f05fe0a1d67
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3
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Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications, file e384c432-99ec-d4b2-e053-9f05fe0a1d67
|
3
|
|
AC Losses in the First ITER CS Module Tests: Experimental Results and Comparison to Analytical Models, file e384c434-07b7-d4b2-e053-9f05fe0a1d67
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3
|
|
AC Losses in the Second Module of the ITER Central Solenoid, file e384c434-6e47-d4b2-e053-9f05fe0a1d67
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3
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Multiscale hydraulic modeling of the ITER TF he inlets during nominal and off-normal operation, file 0fb86c27-d739-4b8c-b0eb-8603970b783e
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2
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Development and validation of the 4C thermal–hydraulic model of the ITER Central Solenoid modules, file 96654296-9e70-4a19-9c92-212f730fa054
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2
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Multiscale hydraulic modeling of the ITER TF he inlets during nominal and off-normal operation, file b5b89e8f-e20d-415d-a0a0-f87fa38b4a68
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2
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MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS, file e384c42e-1088-d4b2-e053-9f05fe0a1d67
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2
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Parametric analysis of the ITER TF fast discharge using the 4C code, file e384c42e-1469-d4b2-e053-9f05fe0a1d67
|
2
|
|
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors, file e384c42e-19f1-d4b2-e053-9f05fe0a1d67
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2
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4C code analysis of thermal-hydraulic transients in the KSTAR PF1 superconducting coil, file e384c42e-1ac9-d4b2-e053-9f05fe0a1d67
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2
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Validation of the 4C code against data from the HELIOS loop at CEA Grenoble, file e384c42e-1aca-d4b2-e053-9f05fe0a1d67
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2
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4C modeling of pulsed-load smoothing in the HELIOS facility using a controlled bypass valve, file e384c42e-2d78-d4b2-e053-9f05fe0a1d67
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2
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Modeling of pulsed heat load in a cryogenic SHe loop using Artificial Neural Networks, file e384c42e-2d7a-d4b2-e053-9f05fe0a1d67
|
2
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First Validation of the FRENETIC Code Thermal-Hydraulic Model against the ENEA Integral Circulation Experiment, file e384c42e-2d7b-d4b2-e053-9f05fe0a1d67
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2
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Thermal-Hydraulic Code-to-Code Benchmark in a Simplified EBR-II Geometry, file e384c42e-2d7c-d4b2-e053-9f05fe0a1d67
|
2
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Benchmark and preliminary validation of the thermal-hydraulic module of the FRENETIC code against EBR-II data, file e384c42e-30c9-d4b2-e053-9f05fe0a1d67
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2
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CFD analysis of the ITER first wall 06 panel. Part I: Model set-up andflow distribution, file e384c42e-352c-d4b2-e053-9f05fe0a1d67
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2
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Incorporating Artificial Neural Networks in the dynamic thermal-hydraulic model of a controlled cryogenic circuit, file e384c42e-3a7c-d4b2-e053-9f05fe0a1d67
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2
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Analysis of Quench Propagation in the ITER Poloidal Field Conductor Insert (PFCI), file e384c42e-7e15-d4b2-e053-9f05fe0a1d67
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2
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Thermal-hydraulic modeling of a novel HTS CICC for nuclear fusion applications, file e384c42f-06fe-d4b2-e053-9f05fe0a1d67
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2
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Analysis of Quench Propagation in the ITER Central Solenoid Insert (CSI) Coil, file e384c42f-7b56-d4b2-e053-9f05fe0a1d67
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2
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Analysis of a protected Loss Of Flow Accident (LOFA) in the ITER TF coil cooling circuit, file e384c42f-df55-d4b2-e053-9f05fe0a1d67
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2
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Mechanical analysis of the ENEA TF coil proposal for the EU DEMO fusion reactor, file e384c42f-f0e5-d4b2-e053-9f05fe0a1d67
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2
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| Totale |
3.079 |
Archivio Istituzionale della Ricerca