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

Comparison of results obtained with different core analysis approaches in Tasks 3.2, 3.3 and 3.4

Comparative report that will describe the comparison of the different solution approaches obtained in the tasks 3.2, 3.3 and 3.4 for the different SMR-types.

Validation of subchannel codes with COSMOS-H and MOTEL experiments

This reports will describe the validation work done for subchannel codes using the test data of three facilities.

Validation of system TH codes with COSMOS-H, MOTEL and HWAT experiments

This deliverable sums up the validation studies to be done for system thermal hydraulic codes using the data of three test facilities

Analysis of SMART plant with coupled system code with subchannel code and intercomparing between codes

Analysis of SMART plant with coupled system TH and subchannel codes as well as their intercomparing.

Final comparison of system codes and multi-scale analysis for both selected designs

This deliverable is the final comparison of of the analysis using system codes and multi-scale analysis methods of the different SMR-designs.

Simulation of the ATF core transient using high-fidelity tools and intercomparison with results from T3.4 (non-ATF case)

In this deliverable, the main results obtained for the SMR core with ATF fuel will be described and discussed.

Project website

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

Safety analyses of NUSCALE reactor system traditional methods and intercomparing between codes

In this deliverable, the safety analyses of NUSCALE reactor system traditional methods and intercomparing between codes will be presented and discussed.

Validation of CFD codes with COSMOS-H, MOTEL and HWAT experiments

This report will describe the main results of the validation of the CFD codes using the test data of the three experimental facilities

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

Safety analyses of SMART reactor system using traditional methods and intercomparing between codes

This report will describe the safety analyses of SMART reactor system using traditional methods and intercomparing between codes.

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

Educational activities and related materials

This deliverable will sum up the educational activities and the respective materials use for it .

Project Newsletter 2

This deliverable summarizes the second Project Newsletter.

High-fidelity solutions for the transient scenarios in the four SMR cores and intercomparison between the codes when applicable

It describes the SMR analysis results using high-fidelity tools and methods including the intercomparisons.

Final comparison of system codes and multi-scale analysis

This deliverable will discuss and present the final comparison of system codes and multi-scale analysis.

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

Project Newsletter 3

This deliverable summarizes the third Project Newsletter.

Advanced low-order solutions for the transient scenarios in the four SMR cores and intercomparison between codes when applicable

This deliverable will describe the main results obtained for the low-order transport solvers obtained for the SMRs cores.

Publications

On the application of advanced modeling tools to the SLB analysis in NuScale. Part I: TRACE/PARCS, TRACE/PANTHER and ATHLET/DYN3D

Auteurs: Sanchez-Torrijos, J., Redondo-Valero, E., Queral, C., Cabellos, O., Meca, R., Petrásek, O., Diaz-Pesador, E., Kliem, S., Palmans, N., & Sanchez-Espinoza, V. H.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.8008040

The H2020 McSAFER Project: Analyses of boron dilution for the NuScale reactor

Auteurs: Bencik, M., Parera-Villacampa, O., Ammirabile, L., Queral, C., Sanchez-Torrijos, J., Diaz-Pescador, E., Jammot, V., & Sanchez-Espinoza, V. H.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.8009505

Thermal Hydraulic Experiments and Code Validation for LWR SMRs Within the European McSAFER Project: Overview of Activities and Current Status

Auteurs: Suikkanen, H., Telkkä, J., Kouhia, V., Garbriel, S., Albrecht, G., Heiler, W., Heineken, F., Sanchez-Espinoza, V. H., Li, H., Grishchenko, D., Bencik, M., Vysckocil, L., Dolecek, V., Queral, C., Fernandez-Cosials, K., Rueda-Villegas, L., & Schneidesch, C.
Publié dans: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2023
Éditeur: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
DOI: 10.5281/zenodo.10124881

M&C2023 - H2020 McSafer project: ATWS transient analyses of SMART reactor

Auteurs: N. Palmans, J.G. Etcheto, M. García, & V.H. Sanchez-Espinoza
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.8133940

SMR Experiments with the MOTEL Test Facility within the Euratom Project McSAFER

Auteurs: Telkkä, J., Suikkanen, H., Kotro, E., & Räsänen, A.
Publié dans: Nuclear Science and Technology Symposium (SYP2022), 2022
Éditeur: Nuclear Science and Technology Symposium (SYP2022)
DOI: 10.5281/zenodo.8043026

Analysis of a Main Steam Line Break accident in the NuScale reactor by means of the coupled codes TRACE/PARCS

Auteurs: Redondo-Valero, E., Queral, C., & Sanchez-Torrijos, J.
Publié dans: International Youth Nuclear Congress (IYNC 2022), 2022
Éditeur: International Youth Nuclear Congress (IYNC 2022)
DOI: 10.5281/zenodo.8007622

The H2020 McSAFER Project: Experimental and Analytical Investigations for the Safety Evaluation of Water-Cooled SMRs

Auteurs: Sanchez E., V. H., Gabriel, S., Suikkanen, H., Valtavirta, V., Bencik, M., Queral, C., Kliem, S., Cochet, S., Smith, P., Van Uffelen, P., Seidl, M., Grishchenko, D., & Lestani, H.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.1092734

Boron dilution sequence analysis in NuScale SMR with asymmetrical feedwater injection using TRACE

Auteurs: Sanchez-Torrijos, J., & Queral, C.
Publié dans: International Youth Nuclear Congress (IYNC 2022), 2022
Éditeur: International Youth Nuclear Congress (IYNC 2022)
DOI: 10.5281/zenodo.8007402

M&C2023 - Study of SMART Steam Line Break with the coupled codes TRACE-PARCS and TRACE-PANTHER

Auteurs: J.G. Etcheto, V.H. Sanchez-Espinoza, N. Palmans, & D. De Meyer
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023)
DOI: 10.5281/zenodo.8153340

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

High-Fidelity and State-of-the-Art Multi-Physics Computational Tools for Analyzing a CAREM-like SMR Core in a Full Power State

Auteurs: Huaccho, G., Mercatali, L., Sanchez E., V. H., Lestani, H., & Dalinger, M.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.10927411

Steam Line Break Analysis in NuScale SMR with the Coupled System Code ATHLET-DYN3D in the Framework of the EU H2020 McSAFER

Auteurs: Diaz Pescador, E., Jobst, M., Grahn, A., & Kliem, S.
Publié dans: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2023
Éditeur: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
DOI: 10.13182/nureth20-40596

Study of Anticipated Transient Without Scram with the Coupled code TRACE-SubChanFlow for the SMART Small Modular Reactor

Auteurs: Zhang, K., J.G. Etcheto, & V.H. Sanchez-Espinoza
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.10803404

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

Coupled Analyses of Steam Line Break for Integral PWR

Auteurs: Ikonen, J.-P.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.10925363

A Super-Homogenisation(SPH)-based Pin-wise Cross-Section (XS) Optimization Scheme for PARCS Development, Verification, and First Application to a Small Modular Reactor (SMR)

Auteurs: Zhang, K.
Publié dans: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), 2023
Éditeur: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023)
DOI: 10.5281/zenodo.10803608

Helical Coil Steam Generator Experiments with the MOTEL SMR Test Facility in the EU-McSAFER Project

Auteurs: Telkkä, J., Suikkanen, H., Räsänen, A., Kotro, E., & Hyvärinen, J
Publié dans: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2023
Éditeur: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
DOI: 10.5281/zenodo.10141726

Boron Dilution Analysis in NuScale using TRACE and TRACE/SCF codes

Auteurs: Sanchez-Torrijos, J., & Queral, C.
Publié dans: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2023
Éditeur: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
DOI: 10.5281/zenodo.8008124

Simulation of the boron dilution sequence in NuScale SMR using 1D and 3D modeling approaches in TRACE

Auteurs: Queral, C., & Sanchez-Torrijos, J.
Publié dans: 30th International Conference on Nuclear Engineering (ICONE-30), 2023
Éditeur: 30th International Conference on Nuclear Engineering (ICONE-30)
DOI: 10.5281/zenodo.8007981

Steam Line Break sequence analysis in NuScale using TRACE/PARCS

Auteurs: Queral, C., Redondo-Valero, E., Sanchez-Torrijos, J., & Cabellos, O.
Publié dans: 47th Annual Meeting of the Spanish Nuclear Society (SNE), 2022
Éditeur: 47th Annual Meeting of the Spanish Nuclear Society (SNE)
DOI: 10.5281/zenodo.8007374

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

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