High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors

Livrables

Analysis of NUSCALE plant with 1D system code and intercomparing between codes

This deliverable will discuss the main results obtained for the NuSCALE SMR plant using different 1D system TH codes and it will perform a code to code comparison

Project Newsletter 1

This deliverable summarizes the first Project Newsletter

Project website

This deliverable will summarizes the functionalities of the public website of the project

Advanced transient heat deposition models for Ants nodal solver including dynamic decay heat

In this report the models to take into account heat deposition in solver such as ANTS will be described

State-of-the-art solutions for the transients scenarios in the four SMR cores and intercomparison between codes when applicable

in this report the main results of the core analysis using different methods will be described and compared to each other

Advanced transient heat deposition models for Serpent including dynamic decay heat

In this deliverable the models for heat deposition during transients for Serpent including the dynamic decay heat model will be explained and presented

Report on training course

In this deliverable the material developed for the training courses will be collected and described

Project Corporate identity and communication tools

In this deliverable the elements of the corporate identity and communication tools of the project will be described

Analysis of SMART plant with 1D system code and intercomparing between codes

In this deliverable the results of the simulation of the SMART plant applying different 1D system codes and their intercomparisons will be discussed and presented

Publications

Analysis of Boron Dilution sequence in a NuScale Power Module using TRACE

Auteurs: Sanchez-Torrijos, Jorge; Queral, Cesar; Magan, Javier
Publié dans: 46th Annual Meeting of the Spanish Nuclear Society (SNE), 2021
Éditeur: 46th Annual Meeting of the Spanish Nuclear Society (SNE),
DOI: 10.5281/zenodo.6125111

Boron dilution sequence analysis in NuScale SMR usingTRACE

Auteurs: Sanchez-Torrijos, Jorge; Queral, Cesar
Publié dans: Proceedings of the European Nuclear Young Generation Forum (ENYGF'21), 2021
Éditeur: European Nuclear Young Generation Forum (ENYGF'21)
DOI: 10.5281/zenodo.6124619

Definition of the neutronics benchmark of the NuScale-like core

Auteurs: Fridman, E., Bilodid, Y., & Valtavirta, V.
Publié dans: Nuclear Engineering and Technology, Numéro Vol 55, Numéro 10, 2023, ISSN 1738-5733
Éditeur: Korean Nuclear Society
DOI: 10.1016/j.net.2023.06.029

A review on the thermo-mechanical modelling needs in system codes

Auteurs: Sanchez-Torrijos, J., Aragon, P., Queral, C., Feria, F., Schubert, A., & Van Uffelen, P.
Publié dans: Nuclear Engineering and Design, Numéro Vol 406, 2023, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112243

Multiscale analysis of the boron dilution sequence in the NuScale reactor using TRACE and SUBCHANFLOW

Auteurs: Sanchez-Torrijos, J., Zhang, K., Queral, C., Imke, U., & Sanchez-Espinoza, V. H.
Publié dans: Nuclear Engineering and Design, Numéro Vol 415, 2023, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112708

Spanish research related to SMRs projects

Auteurs: C. Queral, E. Redondo-Valero, J. Sanchez-Torrijos, D. Canal, G. Jiménez, S. Larriba, D. Cuervo, O. Cabellos, L.F. Durán-Vinuesa, L.E. Herranz, M. García, V. Martinez-Quiroga, J. Freixa, T. Barrachina, R. Miro, E. Pérez-Rodríguez, M.T. Dominguez Bautista, O. Larrosa, C. Hueso-Ordoñez, I. Gonzalez-Sevillano, J.A. Ruiz-Martin
Publié dans: Nuclear Engineering and Design, Numéro Vol 417, 2024, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112818

Detail CFD simulation of the integrated reactor pressure vessel of SMART

Auteurs: Michael Böttcher, Victor Sanchez-Espinoza
Publié dans: Progress in Nuclear Energy, Numéro Vol 164, 2023, ISSN 0149-1970
Éditeur: Elsevier BV
DOI: 10.1016/j.pnucene.2023.104854

Creating the foundations for safe nuclear power in Finland – Thermal hydraulics, safety analyses, safety justification methods research at the LUT University, 2000–2023

Auteurs: Hyvärinen, J., Riikonen, V., Telkkä, J., Hujala, E., Kouhia, V., Puustinen, M., Patel, G., Pyy, L., Vihavainen, J., Suikkanen, H., & Rintala, V.
Publié dans: Nuclear Engineering and Design, Numéro Vol 419, 2024, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2024.112935

Multiphysics modeling of a reactivity insertion transient at different fidelity levels in support to the safety assessment of a SMART-like small modular reactor

Auteurs: Mercatali L, Huaccho G and Sanchez-Espinoza V-H
Publié dans: Frontiers in Energy Research, Numéro Vol 11, 2023, ISSN 2296-598X
Éditeur: Frontiers Media SA
DOI: 10.3389/fenrg.2023.1130554

Advanced numerical simulation and modeling for reactor safety – contributions from the CORTEX, McSAFER, and METIS projects

Auteurs: Christophe Demazière, Victor Hugo Sanchez-Espinoza, & Irmela Zentner
Publié dans: EPJ Nuclear Sci. Technol, Numéro Vol 8, 2022, ISSN 2491-9292
Éditeur: EDP Science
DOI: 10.1051/epjn/2022026

The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status

Auteurs: Victor Hugo Sanchez-Espinoza, Stephan Gabriel,Heikki Suikkanen Joonas Telkkä Ville Valtavirta , Marek Bencik, Sören Kliem, Cesar Queral, Anthime Farda, Florian Abéguilé, Paul Smith, Paul Van Uffelen , Luca Ammirabile, Marcus Seidl, Christophe Schneidesch, Dmitry Grishchenko and Hector Lestani
Publié dans: Energies, Numéro Volume 14 Numéro 19 10.3390/en14196348, 2021, ISSN 1996-1073
Éditeur: Multidisciplinary Digital Publishing Institute (MDPI)
DOI: 10.3390/en14196348

Livrables

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