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@INPROCEEDINGS{Gabrielli:1038867,
      author       = {Gabrielli, F. and Mascari, F. and Bersano, A. and Maccari,
                      P. and Ederli, S. and Cazado, M. E. and Sanchez-Espinoza, V.
                      H. and Di Giuli, M. and Bittan, J. and Bakouta, N. and
                      Malicki, M. and Lind, T. and Makarenko, M. and Yesipenko,
                      Yu. and Zhabin, O. and Gumenyuk, D. and Kelm, Stephan and
                      Reinecke, Ernst-Arndt and Vázquez-Rodríguez, Carlos and
                      Koch, M. K. and Krieger, J. and Stahlberg, G. and Jankowski,
                      T. and Garcia Martin, M. and Herranz, L. E. and Bentaib, A.
                      and Carenini, L. and de la Rosa Blul, J.-C. and Papera
                      Villacampa, O. and Kaliatka, A. and Valincius, M. and
                      Constantin, M. and Giannetti, F. and Sevon, T. and Groudev,
                      P. and Reinke, N.},
      title        = {{A}nalysis of postulated severe accidents in generic
                      integral {PWR} small modular reactors in the frame of the
                      {H}orizon {EURATOM} {SASPAM}-{SA} project},
      reportid     = {FZJ-2025-01683},
      year         = {2024},
      abstract     = {Currently, there is a growing interest in Europe in the
                      deployment of Small Modular Reactors (SMRs). One family of
                      SMR,the Integral Pressurised Water Reactor (iPWR), is ready
                      to be licensed as a new build. Despite the reinforcement of
                      the firstthree levels of the Defence-in-Depth (DiD), a sound
                      demonstration of iPWR ability to address Severe Accidents
                      (SA) andhandle offsite protecting countermeasures in case of
                      radiological releases should be carried out (DiD Levels 4
                      and 5). In thiscontext, the HORIZON-EUROPE project ‘Safety
                      Analysis of SMR with PAssive Mitigation strategies - Severe
                      Accidents’(SASPAM-SA), coordinated by ENEA and launched in
                      2022, aims at at investigating the applicability and
                      transfer of thecurrent reactor safety knowledge and know-how
                      for large Light Water Reactors (LWR) to iPWRs, in the view
                      of theEuropean licencing needs related to SA and Emergency
                      Planning Zone (EPZ) analyses.Elements not addressed in other
                      on-going iPWR initiatives are the pillars of the project: a)
                      identification and analysis ofpostulated SA scenarios; b)
                      identifying the RPV and containment conditions
                      characterizing iPWR SA scenarios that mightdiffer from
                      large-LWRs; c) investigating existing experimental database
                      for iPWRs and additional needs; c) capability ofEuropean and
                      non-European (but widely used in Europe) codes for SA and
                      radiological impact on-/off- site analyses iniPWRs.For
                      maximizing knowledge transferability and project impact, two
                      generic iPWR concepts are considered: ‘Design-1’ (60MWe)
                      with a submerged containment; ‘Design-2’ (300 MWe)
                      employing several passive systems and a dry
                      containment.These two iPWR designs incorporate the main
                      design features of the most promising designs ready for
                      deployment in theEuropean market.This paper focuses on the
                      activities of the ‘Input deck development and hypothetical
                      SA scenarios assessment’ WorkingPackage (WP) 2,
                      coordinated by KIT. It aims at assessing generic, but
                      representative, SA and CFD codes’ input decks,analyzing
                      the iPWRs’ behaviour in hypothetical SA conditions, and
                      investigating the codes’ capability to simulate the
                      dominantphenomena driving the scenarios. A set of Design
                      Basis Accident (DBA) and SA scenarios are postulated and
                      analysed. Itshould be noted that since no Probability Safety
                      Assessment (PS) considerations are done in the project
                      (generic designs areconsidered), the SA scenarios are
                      analysed in terms of severity and not of probability to
                      occur. Major outcomes will be theboundary conditions
                      influencing accident management strategies, like In-Vessel
                      Melt Retention and Filtered ContainmentVenting, and
                      quantitative bases to estimate EPZs.In the paper, the
                      results of the analyses of postulated DBA and SA scenarios
                      in both iPWR designs performed by means of SA(AC2, ASTEC,
                      MELCOR, MAAP, EDF-MAAP) and CFD (containmentFOAM, Ansys CFX)
                      codes are discussed. Thepreliminary results have shown that
                      SA codes (AC2, ASTEC, MELCOR, MAAP) can reproduce the main
                      thermal-hydraulicsand in-vessel degradation phenomena during
                      the scenarios, showing consistent values and trends in the
                      primary variables ofthe sequences analysed, i.e. main events
                      timing, hydrogen mass production, and corium mass.},
      month         = {May},
      date          = {2024-05-13},
      organization  = {ERMSAR2024, Stockholm (Sweden), 13 May
                       2024 - 16 May 2024},
      cin          = {IET-4},
      cid          = {I:(DE-Juel1)IET-4-20191129},
      pnm          = {1422 - Beyond Design Basis Accidents and Emergency
                      Management (POF4-142)},
      pid          = {G:(DE-HGF)POF4-1422},
      typ          = {PUB:(DE-HGF)1},
      url          = {https://juser.fz-juelich.de/record/1038867},
}