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SASPAM-SA DELIVERABLES AND PUBLICATIONS
Deliverable list
Deliverable list
Finished deliverables published on Zenodo
- D1.1: Online project share point user manual Online project share point user manual | Zenodo (SEN)
- D1.2: Project Quality Plan Project Quality Plan | Zenodo (SEN)
- D1.3: Data Management Plan Data Management Plan | Zenodo (SEN)
- D1.4: Advisory Board Recommendation Advisory Board Recommendation | Zenodo (SEN)
- D1.5: End User Group Requests End User Group Requests | Zenodo (SEN)
- D2.1: Fuel inventory of the iPWR Design-1 and Design-2 Fuel inventory of the iPWR Design-1 and Design-2 | Zenodo (PU)
- iPWR input-deck and scenarios analyses, iPWR input-deck and scenarios analyses | Zenodo (PU)
- SASPAM-SA WP2: Reports of the partners – iPWR input-decks and scenarios analyses SASPAM-SA WP2: Reports of the partners – iPWR input-decks and scenarios analyses | Zenodo (SEN)
- SASPAM-SA WP2: iPWR scenarios analyses – Results of the partners SASPAM-SA WP2: iPWR scenarios analyses – Results of the partners | Zenodo (SEN)
- D2.3: Analyses of the employment of ATFs in iPWR scenario analyses SASPAM-SA WP2: Deliverable 2.3 Analyses of the employment of ATFs in iPWR scenario analyses | Zenodo (PU)
- SASPAM-SA WP2: Results of the partners – Analyses of the employment of ATFs in iPWR scenario analyses SASPAM-SA WP2: Results of the partners – Analyses of the employment of ATFs in iPWR scenario analyses | Zenodo (SEN)
- SASPAM-SA WP2: Reports of the partners – Analyses of the employment of ATFs in iPWR scenario analyses, SASPAM-SA WP2: Reports of the partners – Analyses of the employment of ATFs in iPWR scenario analyses | Zenodo (SEN)
- D4.1: IVMR Conservative Analyses IVMR Conservative Analyses | Zenodo (PU)
- D7.1: Communication, dissemination, exploitation action plan | Zenodo (SEN)
Draft deliverables
Publication list
Peer-reviewed publications, conference papers, technical dissemination activities and posters produced within the Horizon Euratom SASPAM-SA project.
Publication list
Journal and peer-reviewed papers
- G. Agnello, G. Grippo and F. Mascari,
“Thermal-hydraulic analysis and uncertainty quantification application of a DBA sequence in a generic iPWR using MELCOR code,”
Annals of Nuclear Energy, vol. 236, article 112398, 2026. - M. Principato, C. Ciurluini, F. Giannetti, L. Carénini and F. Fichot,
“Development of a 0D model for the investigation of in-vessel melt retention in integral pressurized water reactors,”
Nuclear Engineering and Design, vol. 452, article 114872, 2026. - T. Sevón,
“A nodalization study on modeling containment and reactor pool of an integral PWR,”
Annals of Nuclear Energy, vol. 226, article 111866, 2026. - J. Bittan, N. Bakouta, M. Di Giuli and A. M. Swaidan,
“Comparison between EDF MAAP5.04 and ASTECv3 codes on hypothetical severe accidents in an integral PWR,”
Nuclear Engineering and Design, article 114407, 2025. - L. E. Herranz, B. Poubeau, L. Chailan and F. Mascari,
“Looking ahead to severe accident research,”
EPJ Nuclear Sciences & Technologies, 2025. - M. Principato, F. Giannetti, M. Imperatori, M. D’Onorio, M. Garcia, L. E. Herranz, A. Bersano and F. Mascari,
“Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario,”
Nuclear Engineering and Design, vol. 437, article 114004, 2025. - R. Gencheva, P. Vryashkova and P. Groudev,
“Comparison of integral and stand-alone calculations of hypothetical severe accident in a generic LW-SMR with ASTEC code,”
IOP Conference Series: Earth and Environmental Science, vol. 1532, article 012022, 2025. - M. Malicki and T. Lind,
“MELCOR 2.2 iPWR LOCA-type accident analysis, Part II: BDBA,”
Nuclear Engineering and Design, vol. 430, article 113667, 2024. - M. Malicki, P. Darnowski and T. Lind,
“An iPWR MELCOR 2.2 study on the impact of the modeling parameters on the code performance and accident progression,”
Energies, vol. 17, no. 13, article 3279, 2024. - M. Malicki and T. Lind,
“MELCOR 2.2 iPWR LOCA-type accident analysis, Part I: Thermal-hydraulics,”
Nuclear Engineering and Design, vol. 428, article 113433, 2024.
Conference papers and proceedings
Conferences are listed chronologically. The paper title links to Zenodo whenever a project record is available; otherwise it links to the publisher, proceedings or official conference resource.
NURETH-20 — 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
- M. Malicki, P. Darnowski and T. Lind, “The iPWR MELCOR 2.2 Parametric Sensitivity Analysis.” DOI: 10.13182/NURETH20-40213.
- F. Giannetti et al., “Analyses of the MELCOR capability to simulate integral PWR using passive systems.” DOI: 10.13182/NURETH20-42294.
ERMSAR 2024 — 11th European Review Meeting on Severe Accident Research
- M. Principato et al., “In-Vessel Melt Retention 0D Model for Integral Pressurized Water Reactors.”
- T. Lind et al., “SASPAM-SA: Assessment of the relevance and applicability of existing experimental databases to iPWR.”
- F. Gabrielli et al., “Analysis of Postulated Severe Accidents in Generic Integral PWR Small Modular Reactors in the Frame of the Horizon Euratom SASPAM-SA Project.”
- M. Malicki, P. Darnowski and T. Lind, “An iPWR MELCOR 2.2 Study on the Impact of the Modeling Parameters on the Code Performance and Accident Progression.”
- C. Vázquez-Rodríguez, K. J. X. Sturm, A. George and S. Kelm, “Development of a LW-SMR Dry Containment Model with containmentFOAM.”
- G. Grippo et al., “Comparison of a DBA Sequence in a Generic iPWR between MELCOR and ASTEC Codes.”
- G. Agnello et al., “Application of the Probabilistic Method to Propagate Input Uncertainty on a DBA Sequence in a Generic iPWR.”
KERNTECHNIK 2024
- J. Krieger, G. T. Stahlberg and M. K. Koch, “Analysis of a Postulated Severe Accident in a Generic Small Modular Reactor Using AC².”
NUTHOS-14 — 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety
- J. Bittan and N. Bakouta, “Comparison Between EDF MAAP5.04 and ASTECv3 Codes on Hypothetical Severe Accidents in an Integral PWR,” pp. 1643–1654.
- G. T. Stahlberg, J. Krieger and M. K. Koch, “Analyses of an Integral Pressurized Water Reactor During Postulated Accident Conditions Using the System Code Package AC²,” pp. 1658–1668.
G4SR-5 — Fifth International Conference on Generation IV and Small Reactors
- C. Vázquez-Rodríguez and S. Kelm, “Development of containmentFOAM towards LW-SMR analyses,” Proceedings of the Canadian Nuclear Society, 2024.
50th Annual Meeting of the Spanish Nuclear Society (SNE)
- M. Garcia and T. Lugo, “The Effect of Passive Safety Systems in a Generic iPWR Design.”
- M. Garcia, T. Lugo and L. E. Herranz, “Severe Accidents in Small Modular Reactors: The Role of Pool Scrubbing in a Generic iPWR.”
IAEA International Conference on Small Modular Reactors and their Applications
- F. Mascari et al., “Horizon Euratom SASPAM-SA Project: Main Ideas and First Outcomes.”
MECOM 2024 — XL Argentine Congress of Computational Mechanics
- M. E. Cazado, F. Gabrielli and V. H. Sánchez Espinoza, “Analysis of Accident Scenarios in a Generic Natural Circulation Small Modular Reactor with the ASTEC Code in the Framework of the SASPAM-SA Project.”
ICONE32 — 32nd International Conference on Nuclear Engineering
- G. Acharya, D. Grishchenko and P. Kudinov, “Investigation of Severe Accident Progression in Integral PWR SMRs.”
NURETH-21 — 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics
- G. Acharya et al., “Investigation of Source Term During Severe Accidents in Integral PWR SMRs.”
- E. Cilia, L. Tempesta, G. Grippo, M. Savini and F. Mascari, “Application of the REPAS Methodology to Analyse the Reliability of the EHRS in the Decay Heat Removal Strategy for an SMR.”
- J. Bittan and N. Bakouta, “Comparison between EDF MAAP5.04 and EPRI MAAP6 Codes on Hypothetical Severe Accidents in an Integral PWR.”
- M. E. Cazado, Z. Jimenez Balbuena and V. H. Sánchez, “Impact of Advanced Technology Fuel Cladding Materials on the Progression of Severe Accidents in a Generic Natural Circulation iPWR.”
ERMSAR 2026 — 12th European Review Meeting on Severe Accident Research
- M. E. Cazado, F. Gabrielli et al., “Analysis of Postulated Design Basis Accidents in Generic Integral PWR Small Modular Reactors: Outcomes on Integral Codes’ Modelling Capabilities from the Horizon Euratom SASPAM-SA Project.”
- F. Gabrielli et al., “Analysis of Postulated Severe Accidents in Generic Integral PWR Small Modular Reactors: Outcomes on Integral Codes’ Modelling Capabilities from the Horizon Euratom SASPAM-SA Project.”
- T. Lind et al., “SASPAM-SA: Assessment of Existing Experimental Data in WP3.”
- M. Malicki and T. Lind, “Gas Phase Iodine Release from iPWR Pool and Dispersion in the Atmosphere.”
- T. Hollands, J. Bittan and F. Giannetti, “SASPAM-SA WP5: Source Term Estimation of Generic SMR Designs.”
- M. Principato, G. Marta and F. Giannetti, “MELCOR DEC-B Transient Analysis in a Generic Integral Pressurized Water Reactor.”
- M. Principato et al., “W-STORM Sensitivity and Uncertainty Analysis for In-Vessel Retention in Integral Pressurized Water Reactors.”
- M. Ilvonen et al., “Assessment of Emergency Planning Zone for iPWRs within the Horizon Euratom SASPAM-SA Project.”
- M. E. Cazado et al., “Evaluation of Hypothetical Severe Accident Progression with ATF Cladding in Generic Integral PWR Designs in the Frame of the SASPAM-SA Project.”
- L. E. Herranz et al., “Pool Scrubbing in Water-Cooled SMRs: Scenarios, Peculiarities and Challenges.”
- C. Vázquez-Rodríguez, “Severe Accident Analysis of SASPAM-SA Design II LW-SMR Dry Containment Using containmentFOAM.”
- S. Brumm, “Investigation of In-Vessel Melt Retention by a Stand-Alone Lower Plenum Model of Integral-PWR Design #1 in the SASPAM-SA Project, Using the ASTECv3 Code.”
- M. Valinčius et al., “Stand-Alone Analysis and Evaluation of Uncertainties of IVMR in SMR Using the AC² Code.”
- G. Agnello et al., “Severe Accident Analysis in a Generic iPWR and Uncertainty Quantification of the Results.”
- M. Savini, G. Agnello et al., “Comparative Analysis of Containment Behavior in a Generic iPWR Design under Postulated BDBA Conditions Using ASTEC v3.1.2 and MELCOR v2.2 Codes.”
Dissemination
Project-organized dissemination and training
International Workshop on SMR Safety for a Sustainable Short-term Deployment
- Workshop scope, agenda and practical information.
- Complete presentation archive.
- F. Mascari, A. Bentaib and F. Giannetti, eds., “Proceedings of the International Workshop on SMR Safety for a Sustainable Short-term Deployment.”
1st SASPAM-SA Training on LWR-SMR Safety
Technical presentations, stakeholder events and outreach
The list below consolidates the project spreadsheet and the official SASPAM-SA event record. Repeated presentations are retained when they were delivered to different audiences.
2023 Project presentations and stakeholder engagement
- M. Malicki, “Severe Accident Activities at PSI, Including Analysis of iPWR,” CSARP 2023.
- Project participation in the Euratom Coordinators’ Hub Day, 14 March 2023.
- TANDEM/SASPAM-SA presentation at SNETP Forum 2023, Gothenburg, Sweden, 16 May 2023.
- SASPAM-SA presentation at “New Trends of Nuclear Reactors: Small Modular Reactors — Experience of Leading Countries and Developers,” Vilnius, Lithuania, 15 June 2023.
- SASPAM-SA presentation at the IPRESCA meeting, Frankfurt, Germany, 5–6 July 2023.
- SASPAM-SA presentation at the R2CA Summer School, Bologna, Italy, 4–6 July 2023.
- Project contribution to the NURETH-20 panel “Beyond Design Basis Accidents in Advanced Reactors: Opportunities and Challenges,” Washington, D.C., USA, 20–25 August 2023.
- SASPAM-SA presentation at the OECD/NEA WGAMA meeting, Paris, France, 11–13 September 2023.
- Project presentation at Enlit Europe, Paris, France, 28–30 November 2023.
- Project presentation at the 5th meeting of IAEA CRP I31033, “Advancing the State of Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water-Cooled Reactors.”
- “U.S. NRC Topics of Interest for Experimental Research for Water-Cooled Reactors — Euratom Research-Funded Projects Focusing on LW-SMR Safety,” online meeting, 20 December 2023.
2024 Technical dissemination
- 15th European MELCOR and MACCS User Group Meeting, Rome, Italy, 15–18 April 2024:
- F. Mascari, “ENEA Activities in the Field of Severe Accidents by Using MELCOR Code.”
- F. Giannetti, “Analysis of the MELCOR Capability to Simulate Passive Systems in Integral PWR.”
- M. Principato, “Analyses of Severe Accident Sequences in an Integral PWR with Passive Systems.”
- G. Grippo, “Comparison of a DBA Sequence in a Generic iPWR between MELCOR and ASTEC Codes.”
- CSARP 2024:
- F. Mascari, “ENEA Activities in the Field of Severe Accidents.”
- F. Mascari, “SASPAM-SA (Safety Analyses of SMR with Passive Mitigation Strategies — Severe Accident) Horizon Euratom Project.”
- M. Savini, G. Grippo et al., “Analyses of DBA and Several BDBA Sequences in a Generic iPWR with MELCOR 2.2 Code,” 41st UIT International Heat Transfer Conference, Naples, Italy, 19–21 June 2024.
- F. Mascari, “International Program Supporting Safe Deployment of Small Modular Reactors,” keynote presentation, NUTHOS-14, Vancouver, Canada, 25–28 August 2024.
- F. Mascari, “SASPAM-SA — Current Status,” IAEA Interregional Workshop on Experimental Testing and Validation for Design and Safety Analysis Computer Codes for Small Modular Reactors.
- F. Mascari and E. Cilia, “Reliability Assessment of Passive Safety Systems Using REPAS,” IAEA Technical Meeting on Progress in the Performance Assessment and Regulation of Passive Safety Systems in Advanced Nuclear Power Plant Designs.
- F. Mascari, “Horizon Euratom SASPAM-SA: Main Ideas and First Outcomes,” IAEA International Conference on Small Modular Reactors and their Applications, Vienna, Austria, 21–25 October 2024.
- F. Giannetti, “I nuovi reattori nucleari di piccola taglia, sicuri e sostenibili,” public-outreach article.
2025 Technical dissemination
- 16th European MELCOR User Group Meeting, Brno, Czech Republic, 7–11 April 2025:
- G. Grippo, “Application of the REPAS Methodology to Analyse the Reliability of the EHRS in the Decay Heat Removal Strategy for an SMR.”
- E. Cilia, “Analysis of DBA and Different BDBA Scenarios in a Generic iPWR-Type Reactor.”
- T. Sevón, “Lessons Learned and Challenges Identified in Modelling Integral PWRs in the EU SASPAM-SA Project.”
- F. Mascari, “Horizon Euratom SASPAM-SA Project: Main Ideas and First Outcomes.”
- F. Mascari, “Contribution to Plenary IV: Research and Innovation Supporting Safety, Security and Safeguards,” FISA-EURADWASTE 2025 & SNETP Forum, Warsaw, Poland, 12–16 May 2025.
- G. Grippo, “Code-to-Code Comparison of a DBA Sequence in a Generic iPWR: TRACE vs. MELCOR and ASTEC Results,” CAMP 2025.
- F. Mascari, “Severe Accident Computer Codes,” Short Course on Severe Accident Phenomenology, Forschungszentrum Jülich.
- CSARP-MCAP 2025, Bethesda, Maryland, USA, 2–6 June 2025:
- T. Sevón, “A Nodalization Study of a Submerged SMR Containment with MELCOR.”
- F. Gabrielli, “Analysis of Postulated Severe Accidents in Generic Integral PWR Small Modular Reactors in the Frame of the Horizon Euratom SASPAM-SA Project.”
- F. Mascari, “Horizon Euratom SASPAM-SA Project: Main Ideas and First Outcomes.”
- F. Mascari, “ENEA Activities in the Field of Severe Accidents.”
- F. Mascari, “Applicability and Transfer of the Existing Severe-Accident Experimental Database for iPWR Assessment.”
- G. Grippo, “Code-to-Code Comparison of a DBA Sequence in a Generic iPWR: TRACE vs. MELCOR and ASTEC Results.”
- G. Grippo, “Application of the REPAS Methodology to Analyse the Reliability of the EHRS in the Decay Heat Removal Strategy for an SMR.”
- F. Mascari, “Horizon Euratom SASPAM-SA Project: Main Ideas and First Outcomes,” ISReCTHA-2 Meeting, Politecnico di Milano, Lecco, Italy, 28–30 July 2025.
- F. Mascari, “European Program Supporting Safe Deployment of Small Modular Reactors,” NURETH-21, Busan, Republic of Korea, 31 August–5 September 2025.
- F. Mascari, “Research and Development of Light-Water SMRs,” Viennese Nuclear Symposium.
- 12th ASTEC Users’ Club Meeting, ASNR, Fontenay-aux-Roses, France, 12–14 November 2025:
- F. Mascari, “Horizon Euratom SASPAM-SA Project: Main Ideas and First Outcomes.”
- F. Mascari, “ENEA Activities with ASTEC.”
- M. Cazado, “ASTEC Application to iPWR: Air Ingress and H₂ Behaviour.”
- P. Groudev et al., “Use of ASTEC at INRNE-BAS.”
- M. Di Giuli, “ASTEC Activities in Tractebel.”
- L. Carénini and F. Fichot, “Outcomes from Recent R&D Activities on IVR for ASTEC Physical Models.”
- S. Brumm, “Recent JRC Work with ASTEC on In-Vessel Melt Retention in SMRs.”
- F. Mascari, “Reliability Assessment of Passive Safety Systems,” Workshop on SMR Safety Assessment: From Challenges to Achievements.
Posters
- F. Mascari, “SASPAM-SA — Enlit Europe 2023 poster,” Enlit Europe 2023, Paris, France, November 28–30, 2023.
- F. Mascari, “SASPAM-SA — SNETP Forum 2024 poster,” SNETP Forum 2024, Rome, Italy, April 17–19, 2024.
- F. Giannetti, “SASPAM-SA — Enlit Europe 2024 poster,” Enlit Europe 2024, Milan, Italy, October 22–24, 2024.