All Stories

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