Numerical Assessment of Nuclear Cogeneration Transients with SMRs Using CATHARE 3–MODELICA Coupling

Alessandro De Angelis (), Nicolas Alpy, Paolo Olita, Calogera Lombardo and Walter Ambrosini ()
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Alessandro De Angelis: Department of Civil and Industrial Engineering (DICI), University of Pisa, 56126 Pisa, Italy
Nicolas Alpy: Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), CEA Cadarache, 13115 Saint-Paul-lès-Durance, France
Paolo Olita: Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), CEA Cadarache, 13115 Saint-Paul-lès-Durance, France
Calogera Lombardo: Agenzia Nazionale per le Nuove Tecnologie, l’Energia e lo Sviluppo Economico Sostenibile (ENEA), Dipartimento Nucleare (NUC-ENER), 40121 Bologna, Italy
Walter Ambrosini: Department of Civil and Industrial Engineering (DICI), University of Pisa, 56126 Pisa, Italy

Energies, 2025, vol. 18, issue 10, 1-25

Abstract: To achieve the decarbonisation goal by 2050, nuclear energy can be a useful element for the future energy mix, complementing intermittent renewable sources. Additionally, heat from the core can be used for cogeneration, aiding the decarbonisation of several energy sectors. In this context, Small Modular Reactors (SMRs) are being studied when introduced in Nuclear–Renewable Hybrid Energy Systems for cogeneration applications. However, nuclear cogeneration with SMRs is still an emerging area of study, requiring careful considerations regarding technical, safety, and economic aspects. European research initiatives, such as the TANDEM project, are exploring the integration of light–water SMRs into hybrid systems. This paper investigates the impact of cogeneration transients on the primary system of an SMR using a novel coupling approach. For this scope, the thermal–hydraulic system code CATHARE 3 and the dynamic modelling language MODELICA are adopted. Three transient scenarios were analysed: cogeneration transitions, core power variations, and thermal load rejection. The results achieved provide insights about the robustness of the numerical coupling and the primary system response to cogeneration-induced transients. As a matter of fact, the analysis shows that the reactor system is mildly influenced by cogeneration changes, and the findings suggest future improvements for both the coupling methodology and modelling assumptions.

Keywords: SMRs; hybrid energy systems; code coupling; CATHARE 3; MODELICA; FMI; nuclear safety (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2025
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