All Stories

  1. Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components

    Article • Nuclear Engineering and Design, March 2025, Elsevier

    Prof. Sandro Paci

  2. Major Achievements of the EC MUSA Project

    Article • Nuclear Technology, January 2025, Taylor & Francis

    Prof. Sandro Paci

  3. The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel

    Article • Energies, January 2025, MDPI AG

    Prof. Sandro Paci

  4. On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions

    Article • Nuclear Engineering and Design, April 2024, Elsevier

    Prof. Sandro Paci

  5. Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project

    Article • Annals of Nuclear Energy, February 2024, Elsevier

    Prof. Sandro Paci

  6. Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies.

    Article • Journal of Physics Conference Series, January 2024, Institute of Physics Publishing

    Prof. Sandro Paci

  7. Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application.

    Article • Journal of Physics Conference Series, January 2024, Institute of Physics Publishing

    Prof. Sandro Paci

  8. Preliminary Thermo-Mechanical Characterization of Cement-Based Materials for LLW Immobilization

    Article • October 2023, ASME International

    Prof. Sandro Paci

  9. Current status of MELCOR 2.2 for fusion safety analyses

    Article • Fusion Engineering and Design, September 2023, Elsevier

    Prof. Sandro Paci

  10. ERMSAR-2022 conference “Severe accident research: Eleven years after the Fukushima accident”

    Article • Annals of Nuclear Energy, September 2023, Elsevier

    Prof. Sandro Paci

  11. Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs

    Article • Nuclear Engineering and Design, June 2023, Elsevier

    Prof. Sandro Paci

  12. Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5

    Article • Fusion Engineering and Design, May 2023, Elsevier

    Prof. Sandro Paci

  13. Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

    Article • Energies, February 2022, MDPI AG

    Prof. Sandro Paci

  14. 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

    Article • Applied Sciences, December 2021, MDPI AG

    Prof. Sandro Paci

  15. Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code

    Article • Applied Sciences, December 2021, MDPI AG

    Prof. Sandro Paci

  16. Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

    Article • August 2021, ASME International

    Prof. Sandro Paci

  17. The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status

    Article • Energies, July 2021, MDPI AG

    Prof. Sandro Paci

  18. Preliminary Analysis of an Aged RPV Subjected to Station Blackout

    Article • Energies, July 2021, MDPI AG

    Prof. Sandro Paci

  19. Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA

    Article • Fusion Engineering and Design, July 2021, Elsevier

    Prof. Sandro Paci

  20. Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA

    Article • Fusion Engineering and Design, April 2021, Elsevier

    Prof. Sandro Paci

  21. Thermal analysis of HI-STORM 100S dry cask with the MELCOR code

    Article • Journal of Physics Conference Series, April 2021, Institute of Physics Publishing

    Prof. Sandro Paci

  22. Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB

    Article • Fusion Engineering and Design, November 2020, Elsevier

    Prof. Sandro Paci

  23. Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

    Article • August 2020, ASME International

    Prof. Sandro Paci

  24. ERMSAR 2019 conference of NUGENIA TA2/SARNET on research on severe accidents in nuclear power plants

    Article • Annals of Nuclear Energy, May 2020, Elsevier

    Prof. Sandro Paci

  25. RELAP5/SIMMER-III code coupling development for PbLi-water interaction

    Article • Fusion Engineering and Design, April 2020, Elsevier

    Prof. Sandro Paci

  26. Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation

    Article • Fusion Engineering and Design, March 2020, Elsevier

    Prof. Sandro Paci

  27. Standalone Containment Analysis of Four Phébus Tests with the ASTEC and the MELCOR Codes

    Article • Science and Technology of Nuclear Installations, January 2019, Hindawi Publishing Corporation

    Prof. Sandro Paci

  28. ECART analysis of the STARDUST dust resuspension tests with an obstacle presence

    Article • Fusion Engineering and Design, October 2018, Elsevier

    Prof. Sandro Paci

  29. ERMSAR-2017 conference of NUGENIA/SARNET on research on severe accidents in nuclear power plants

    Article • Annals of Nuclear Energy, August 2018, Elsevier

    Prof. Sandro Paci

  30. Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

    Article • Journal of Nuclear Engineering and Radiation Science, March 2018, ASME International

    Prof. Sandro Paci

  31. Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test

    Article • Heliyon, March 2018, Elsevier

    Prof. Sandro Paci

  32. Implementation and validation of a resuspension model in MELCOR 1.8.6 for fusion applications

    Article • Fusion Engineering and Design, November 2017, Elsevier

    Prof. Sandro Paci

  33. A knowledge-based approach for the structural assessment of cultural heritage, a case study: La Sapienza Palace in Pisa

    Article • Bulletin of Earthquake Engineering, May 2017, Springer Science + Business Media

    Prof. Sandro Paci

  34. Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA

    Article • EPJ Nuclear Sciences & Technologies, January 2017, EDP Sciences

    Prof. Sandro Paci

  35. Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test

    Article • Science and Technology of Nuclear Installations, January 2017, Hindawi Publishing Corporation

    Prof. Sandro Paci

  36. ERMSAR-2015 conference of SARNET in the frame of the NUGENIA Technical Area 2

    Article • Annals of Nuclear Energy, July 2016, Elsevier

    Prof. Sandro Paci

  37. SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour

    Article • Annals of Nuclear Energy, July 2016, Elsevier

    Prof. Sandro Paci

  38. Recent severe accident research synthesis of the major outcomes from the SARNET network

    Article • Nuclear Engineering and Design, September 2015, Elsevier

    Prof. Sandro Paci

  39. LOCA Accident for the DEMO Helium Cooled Blanket

    Article • Fusion Science & Technology, July 2015, American Nuclear Society (ANS)

    Prof. Sandro Paci

  40. Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803

    Article • Annals of Nuclear Energy, March 2015, Elsevier

    Prof. Sandro Paci

  41. Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept

    Article • Science and Technology of Nuclear Installations, January 2015, Hindawi Publishing Corporation

    Prof. Sandro Paci

  42. ERMSAR 2013 conference of the SARNET network

    Article • Annals of Nuclear Energy, December 2014, Elsevier

    Prof. Sandro Paci

  43. Generic Containment: Detailed comparison of containment simulations performed on plant scale

    Article • Annals of Nuclear Energy, December 2014, Elsevier

    Prof. Sandro Paci

  44. Lesson learned from the SARNET wall condensation benchmarks

    Article • Annals of Nuclear Energy, December 2014, Elsevier

    Prof. Sandro Paci

  45. Analysis of the influence of the heat transfer phenomena on the late phase of the ThAI Iod-12 test

    Article • Journal of Physics Conference Series, November 2014, Institute of Physics Publishing

    Prof. Sandro Paci

  46. Thermal-hydraulic–iodine chemistry coupling: Insights gained from the SARNET benchmark on the THAI experiments Iod-11 and Iod-12

    Article • Nuclear Engineering and Design, December 2013, Elsevier

    Prof. Sandro Paci, Gunther Weber

  47. Thermal hydraulic feasibility analysis of the IBED PHTS for ITER

    Article • Fusion Engineering and Design, October 2013, Elsevier

    Prof. Sandro Paci

  48. Spreading of Excellence in SARNET Network on Severe Accidents: The Education and Training Programme

    Article • Science and Technology of Nuclear Installations, January 2012, Hindawi Publishing Corporation

    Prof. Sandro Paci

  49. The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants

    Article • Science and Technology of Nuclear Installations, January 2012, Hindawi Publishing Corporation

    Prof. Sandro Paci

  50. Sprays in containment: Final results of the SARNET spray benchmark

    Article • Nuclear Engineering and Design, June 2011, Elsevier

    Prof. Sandro Paci

  51. Experimental and numerical analysis of the air inflow technique for dust removal from the vacuum vessel of a tokamak machine

    Article • Fusion Engineering and Design, January 2008, Elsevier

    Prof. Sandro Paci

  52. Il “Rinascimento Nucleare” sarà trainato dalla globalizzazione economica?

    Article • January 2007, Springer Science + Business Media

    Prof. Sandro Paci

  53. Analysis of an ex-vessel break in the ITER divertor cooling loop

    Article • Fusion Engineering and Design, August 2006, Elsevier

    Prof. Sandro Paci

  54. Dust mobilization experiments in the context of the fusion plants—STARDUST facility

    Article • Fusion Engineering and Design, February 2006, Elsevier

    Prof. Sandro Paci

  55. Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

    Article • January 2006, ASME International

    Prof. Sandro Paci

  56. Validation of a CFD Condensation Model Based on Heat and Mass Transfer Analogy by TOSQAN Facility ISP47 Test

    Article • January 2006, ASME International

    Prof. Sandro Paci

  57. Validation of the ECART code for the safety analysis of fusion reactors

    Article • Fusion Engineering and Design, November 2005, Elsevier

    Prof. Sandro Paci

  58. Bases for dust mobilization modelling in the light of STARDUST experiments

    Article • Nuclear Engineering and Design, May 2005, Elsevier

    Prof. Sandro Paci

  59. Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP)

    Article • Nuclear Engineering and Design, February 2005, Elsevier

    Prof. Sandro Paci

  60. Ex-vessel break in ITER divertor cooling loop analysis with the ECART code

    Article • Fusion Engineering and Design, September 2003, Elsevier

    Prof. Sandro Paci

  61. Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project

    Article • Nuclear Engineering and Design, April 2003, Elsevier

    Prof. Sandro Paci

  62. Heat and mass transfer models in LWR containment systems

    Article • Nuclear Engineering and Design, February 2001, Elsevier

    Prof. Sandro Paci

  63. Environmental Source terms during a few Reference Accident Sequences (RAS) of NET/ITER plant

    Article • Journal of Fusion Energy, June 1993, Springer Science + Business Media

    Prof. Sandro Paci