All Stories

  1. On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions
  2. Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
  3. Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies.
  4. Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application.
  5. Preliminary Thermo-Mechanical Characterization of Cement-Based Materials for LLW Immobilization
  6. Current status of MELCOR 2.2 for fusion safety analyses
  7. ERMSAR-2022 conference “Severe accident research: Eleven years after the Fukushima accident”
  8. Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs
  9. Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5
  10. Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel
  11. Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios
  12. Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code
  13. Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project
  14. The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status
  15. Preliminary Analysis of an Aged RPV Subjected to Station Blackout
  16. Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA
  17. Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA
  18. Thermal analysis of HI-STORM 100S dry cask with the MELCOR code
  19. Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB
  20. Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor
  21. ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants
  22. RELAP5/SIMMER-III code coupling development for PbLi-water interaction
  23. Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation
  24. Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes
  25. ECART analysis of the STARDUST dust resuspension tests with an obstacle presence
  26. ERMSAR-2017 conference of NUGENIA/SARNET on research on severe accidents in nuclear power plants
  27. Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes
  28. Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
  29. Implementation and validation of a resuspension model in MELCOR 1.8.6 for fusion applications
  30. A knowledge-based approach for the structural assessment of cultural heritage, a case study: La Sapienza Palace in Pisa
  31. Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA
  32. Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
  33. ERMSAR-2015 conference of SARNET in the frame of the NUGENIA Technical Area 2
  34. SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour
  35. Recent severe accident research synthesis of the major outcomes from the SARNET network
  36. LOCA Accident for the DEMO Helium Cooled Blanket
  37. Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803
  38. Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept
  39. ERMSAR 2013 conference of the SARNET network
  40. Generic Containment: Detailed comparison of containment simulations performed on plant scale
  41. Lesson learned from the SARNET wall condensation benchmarks
  42. Analysis of the influence of the heat transfer phenomena on the late phase of the ThAI Iod-12 test
  43. Thermal-hydraulic–iodine chemistry coupling: Insights gained from the SARNET benchmark on the THAI experiments Iod-11 and Iod-12
  44. Thermal hydraulic feasibility analysis of the IBED PHTS for ITER
  45. Spreading of Excellence in SARNET Network on Severe Accidents: The Education and Training Programme
  46. The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants
  47. Sprays in containment: Final results of the SARNET spray benchmark
  48. Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine
  49. Il “Rinascimento Nucleare” sarà trainato dalla globalizzazione economica?
  50. Analysis of an ex-vessel break in the ITER divertor cooling loop
  51. Dust mobilization experiments in the context of the fusion plants—STARDUST facility
  52. Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations
  53. Validation of a CFD Condensation Model Based on Heat and Mass Transfer Analogy by TOSQAN Facility ISP47 Test
  54. Validation of the ECART code for the safety analysis of fusion reactors
  55. Bases for dust mobilization modelling in the light of STARDUST experiments
  56. Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP)
  57. Ex-vessel break in ITER divertor cooling loop analysis with the ECART code
  58. Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project
  59. Heat and mass transfer models in LWR containment systems
  60. Environmental Source terms during a few Reference Accident Sequences (RAS) of NET/ITER plant