All Stories

  1. Parametrical Choice of the Optimized Fusion System for a FFHR
  2. RFP-MSR Hybrid Reactor Model for Tritium Breeding and Actinides Transmutation †
  3. Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment
  4. Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels
  5. Evolution of Standardized Specifications on Materials, Manufacturing and In-Service Inspection of Nuclear Reactor Vessels
  6. Nuclear Hydrogen Production: Modeling and Preliminary Optimization of a Helical Tube Heat Exchanger
  7. Approaching Nuclear Safety Culture in Fission and Fusion Technology
  8. NOVEL HYBRID PILOT EXPERIMENT PROPOSAL FOR A FUSION-FISSION SUBCRITICAL COUPLED SYSTEM
  9. PILOT FFHR BASED ON A RFP AS A FUSION CORE
  10. Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor
  11. Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review
  12. Development of a Reduced Order Model for Fuel Burnup Analysis
  13. An ADS irradiation facility for fast and slow neutrons
  14. Study hydrogen embrittlement and determination of E110 fuel cladding mechanical properties by ring compression testing
  15. Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops
  16. CFD preliminary assessment of a protrusions based facility
  17. Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility
  18. Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors
  19. Assessment of a 2D CFD model for a single phase natural circulation loop
  20. CFD initial assessment of a protrusions based experimental facility
  21. Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons
  22. Numerical investigation of turbulent flow within a channel with chamfered edge ribs in stream-wise direction
  23. New infrastructure for studies of transmutation and fast systems concepts
  24. A useful observable for estimating keff in fast subcritical systems
  25. A low power ADS for transmutation studies in fast systems
  26. Preliminary CFD Assessment of an Experimental Test Facility Operating with Heavy Liquid Metals
  27. A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle
  28. Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up
  29. A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA
  30. Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR
  31. Contributing to the nuclear 3S's via a methodology aiming at enhancing the synergies between nuclear security and safety
  32. The VHTR and GFR and their use in innovative symbiotic fuel cycles
  33. Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
  34. Nuclear Desalination: An Alternative Solution to the Water Shortage
  35. Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors
  36. Nuclear Systems for Hydrogen Production: State of Art and Perspectives in Transport Sector
  37. Cross Sections Influence on Monte Carlo Based Burnup Codes
  38. Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration
  39. An intrinsically safe facility for forefront research and training on nuclear technologies — Burnup and transmutation
  40. Study of an intrinsically safe infrastructure for training and research on nuclear technologies
  41. Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0©
  42. Corrosion issues in high temperature gas-cooled reactor (HTR) systems
  43. Generation IV reactor designs, operation and fuel cycle
  44. Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices
  45. Analysis of Pebble-Fueled Zone Modeling Influence on High-Temperature Reactor Core Calculations
  46. Assessment of LWR-HTR-GCFR Integrated Cycle
  47. Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle”
  48. GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides
  49. Innovative Gas-Cooled Reactors
  50. Preliminary Evaluation of a Nuclear Scenario Involving Innovative Gas Cooled Reactors
  51. The Influence of the Packing Factor on the Fuel Temperature Hot Spots in a Particle-Bed GCFR
  52. The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles
  53. An in-vivo comparison study between standard and PET-based approach to assess the therapeutic dose in neutron capture therapies
  54. HTR Pebble Fuel Burnup Experimental Benchmark
  55. A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors
  56. HTGR reactor physics and fuel cycle studies
  57. An additional performance of HTRS: the waste radiotoxicity minimisation
  58. The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation