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Comparison Among Monte Carlo Based Burnup Codes Applied to the GFR Demonstrator ALLEGRO, file e268c4c8-6ce8-a6b7-e053-3a05fe0adea1
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164
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An ADS irradiation facility for fast and slow neutrons, file e268c4c7-1c14-a6b7-e053-3a05fe0adea1
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143
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Study hydrogen embrittlement and determination of E110 fuel cladding mechanical properties by ring compression testing, file e268c4c9-9277-a6b7-e053-3a05fe0adea1
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116
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Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops, file e268c4c9-1042-a6b7-e053-3a05fe0adea1
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104
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Myrrha primary heat exchanger tube rupture: Phenomenology and evolution, file e268c4c9-531f-a6b7-e053-3a05fe0adea1
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102
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A low power ADS for transmutation studies in fast systems, file e268c4c8-4178-a6b7-e053-3a05fe0adea1
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94
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Development of a Reduced Order Model for Fuel Burnup Analysis, file e268c4cb-fac3-a6b7-e053-3a05fe0adea1
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79
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Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors, file e268c4cb-c8d3-a6b7-e053-3a05fe0adea1
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73
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Assessment of a 2D CFD model for a single phase natural circulation loop, file e268c4c8-05cd-a6b7-e053-3a05fe0adea1
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72
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Preliminary CFD assessment of an experimental test facility operating with heavy liquid metals, file e268c4c7-d53a-a6b7-e053-3a05fe0adea1
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71
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A useful observable for estimating keff in fast subcritical systems, file e268c4c8-01d3-a6b7-e053-3a05fe0adea1
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68
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New infrastructure for studies of transmutation and fast systems concepts, file e268c4c8-01d1-a6b7-e053-3a05fe0adea1
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60
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Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors, file e268c4cb-c8d4-a6b7-e053-3a05fe0adea1
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17
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Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant, file e268c4c6-b4d3-a6b7-e053-3a05fe0adea1
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15
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Novel hybrid pilot experiment proposal for a fusion-fission subcritical coupled system, file e268c4cd-bde9-a6b7-e053-3a05fe0adea1
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14
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Approaching Nuclear Safety Culture in Fission and Fusion Technology, file e268c4cd-cc45-a6b7-e053-3a05fe0adea1
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14
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CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator, file e268c4c9-39d9-a6b7-e053-3a05fe0adea1
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13
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Nuclear Hydrogen Production: Modeling and Preliminary Optimization of a Helical Tube Heat Exchanger, file e268c4cd-ab57-a6b7-e053-3a05fe0adea1
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12
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Nuclear Desalination: an Alternative Solution to the Water Shortage, file e268c4c6-1a67-a6b7-e053-3a05fe0adea1
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11
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A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA, file e268c4c6-d7a9-a6b7-e053-3a05fe0adea1
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11
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Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels, file e268c4ce-99dd-a6b7-e053-3a05fe0adea1
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11
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Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review, file e268c4cc-ec5b-a6b7-e053-3a05fe0adea1
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9
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HTR Pebble Fuel Burnup Experimental Benchmark, file e268c4c6-4956-a6b7-e053-3a05fe0adea1
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8
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Development of CFD models and pre-test calculations for thermal-hydraulics and freezing experiments on Lead coolant, file e268c4c8-2f14-a6b7-e053-3a05fe0adea1
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8
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Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor, file e268c4cd-8d9b-a6b7-e053-3a05fe0adea1
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8
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A Preliminary Study of an Improved Area Method, Adapted to Short Time Transients in Sub-Critical Systems., file e268c4c6-3b68-a6b7-e053-3a05fe0adea1
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7
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Evolution of Standardized Specifications on Materials, Manufacturing and In‐Service Inspection of Nuclear Reactor Vessels, file e268c4cd-fccd-a6b7-e053-3a05fe0adea1
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7
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Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment, file 5abc0129-e66c-4829-b66f-b2af382a9bd2
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6
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Corrosion issues in high temperature gas cooled reactor (HTR) systems, file e268c4c6-0fd0-a6b7-e053-3a05fe0adea1
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6
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Reset text, file e268c4c6-186f-a6b7-e053-3a05fe0adea1
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6
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Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration, file e268c4c6-d2cd-a6b7-e053-3a05fe0adea1
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6
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CFD preliminary assessment of a protrusions based facility, file e268c4c8-f99f-a6b7-e053-3a05fe0adea1
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6
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Multi-group analysis of Minor Actinides transmutation in a Fusion Hybrid Reactor, file 829c2f31-44dd-4b33-9d1e-64d90bd02192
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5
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HTR-N Plutonium Cell Burnup Benchmark: Definition, Results Intercomparison, file e268c4c6-419e-a6b7-e053-3a05fe0adea1
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4
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CFD initial assessment of a protrusions based experimental facility, file e268c4c8-05cb-a6b7-e053-3a05fe0adea1
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4
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An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization, file e268c4c5-fa10-a6b7-e053-3a05fe0adea1
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3
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Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility, file e268c4c8-f99d-a6b7-e053-3a05fe0adea1
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3
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PILOT FFHR BASED ON A RFP AS A FUSION CORE, file 47be02aa-5c99-4915-a4b5-b06dd40fd624
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2
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Nuclear Thermal Propulsion for Earth Orbit and Interplanetary Missions: Challenges and Issues, file d68952f4-1366-4eb3-8a9b-0557fedad7b3
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2
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ANALYSIS OF PEBBLE FUELLED ZONE MODELING INFLUENCE ON HTR CORE CALCULATIONS, file e268c4c5-fa9b-a6b7-e053-3a05fe0adea1
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2
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Generation IV reactor designs, operation and fuel cycle, file e268c4c6-11f5-a6b7-e053-3a05fe0adea1
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2
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Cross Sections Influence on Monte Carlo Based Burnup Codes Applied to a GFR-like Configuration, file e268c4c6-3b70-a6b7-e053-3a05fe0adea1
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2
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Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors, file e268c4c6-4566-a6b7-e053-3a05fe0adea1
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2
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Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons, file e268c4c8-05c8-a6b7-e053-3a05fe0adea1
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2
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HTGR reactor physics and fuel cycle studies, file e268c4c5-f809-a6b7-e053-3a05fe0adea1
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1
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Preliminary Evaluation of a Nuclear Scenario involving Innovative Gas Cooled Reactors, file e268c4c5-f875-a6b7-e053-3a05fe0adea1
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1
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Innovative Gas Cooled Reactors, file e268c4c6-0fcf-a6b7-e053-3a05fe0adea1
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1
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Innovative Gas-Cooled Reactors, file e268c4c6-1d6a-a6b7-e053-3a05fe0adea1
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1
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The VHTR and GFR and their use in innovative symbiotic fuel cycles, file e268c4c6-3b6e-a6b7-e053-3a05fe0adea1
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1
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The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation, file e268c4c6-43cd-a6b7-e053-3a05fe0adea1
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1
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Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors - The EU FP6 Project PUMA, file e268c4c6-455c-a6b7-e053-3a05fe0adea1
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1
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An In-vivo Comparative Study Between Standard and PET-Based Approach to Assess the Therapeutic Dose in Neutron Capture Therapies, file e268c4c6-4775-a6b7-e053-3a05fe0adea1
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1
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A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation, file e268c4c8-0695-a6b7-e053-3a05fe0adea1
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1
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Study of an intrinsically safe infrastructure for training and research on nuclear technologies, file e268c4c9-27c3-a6b7-e053-3a05fe0adea1
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1
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An ADS irradiation facility for fast and slow neutrons, file e268c4c9-ce75-a6b7-e053-3a05fe0adea1
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1
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Calculation tool for heat exchanger tube rupture in pool-type reactors, file e268c4cb-1bab-a6b7-e053-3a05fe0adea1
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1
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| Totale |
1.386 |