Publications
The McSAFER project is dedicated to sharing its publications, media and results. This page contains information on publications related to the McSAFER project. Additionally, we will publish a regular newsletter to keep you up to date with the progress of the project.
Publications
All publications related to the McSAFER project can be found in the McSAFER community in the ZENODO repository.
- Sanchez-Espinoza, V. H., Gabriel, S., Suikkanen, H., Telkkä, J., Valtavirta, V., Bencik, M., Kliem, S., Queral, C., Farda, A., Abéguilé, F., Smith, P., Van Uffelen, P., Ammirabile, L., Seidl, M., Schneidesch, C., Grishchenko, D., & Lestani, H. (2021). The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status. Energies, 14(19). DOI
- Sanchez-Torrijos, J., Queral, C., Magan, J., Hegoburu, P., Aramayo, C., Zanocco, P., & Gimenez, M. (2021, Mai 27). TRACE applications to Small Modular Reactors. Zenodo. DOI
- Sanchez-Torrijos, J., & Queral, C. (2021, September 29). Boron dilution sequence analysis in NuScale SMR usingTRACE. European Nuclear Young Generation Forum (ENYGF’21), Tarragona, Spain. DOI
- Sanchez-Torrijos, J., Queral, C., & Magan, J. (2021, Oktober 22). Analysis of Boron Dilution sequence in a NuScale Power Module using TRACE. 46th Annual Meeting of the Spanish Nuclear Society (SNE), Granada,Spain. DOI
- Sanchez-Espinoza, V. H., Suikkanen, H., Valtavirta, V., Bencik, M., & Queral, C. (2022, Februar 2). H2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors. Zenodo. DOI
- Queral, C., Redondo-Valero, E., Sanchez-Torrijos, J., & Cabellos, O. (2022, September 30). Steam Line Break sequence analysis in NuScale using TRACE/PARCS. 47th Annual Meeting of the Spanish Nuclear Society (SNE), Cartagena, Spain. DOI
- Telkkä, J., Suikkanen, H., Kotro, E., & Räsänen, A. (2022, November 1). SMR Experiments with the MOTEL Test Facility within the Euratom Project McSAFER. Nuclear Science and Technology Symposium (SYP2022), Helsinki, Finland. DOI
- Queral, C. (2022, November 4). The H2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors. Annual meeting of Mexican Nuclear Society (SNM), Veracruz, México. Zenodo. DOI
- Sanchez-Torrijos, J., & Queral, C. (2022, Dezember 2). Boron dilution sequence analysis in NuScale SMR with asymmetrical feedwater injection using TRACE. International Youth Nuclear Congress (IYNC 2022), Koriyama, Japan. DOI
- Redondo-Valero, E., Queral, C., & Sanchez-Torrijos, J. (2022, Dezember 2). Analysis of a Main Steam Line Break accident in the NuScale reactor by means of the coupled codes TRACE/PARCS. International Youth Nuclear Congress (IYNC 2022), Koriyama, Japan. DOI
- Telkkä, J., Suikkanen, H., Räsänen, A., Kotro, E., & Hyvärinen, J. Helical Coil Steam Generator Experiments with the MOTEL SMR Test Facility in the EU-McSAFER Project. Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) 2023, 1662–1675. DOI
- 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. Thermal Hydraulic Experiments and Code Validation for LWR SMRs Within the European McSAFER Project: Overview of Activities and Current Status. Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) 2023, 2388–2401. DOI
- Sanchez-Torrijos, J., Aragon, P., Queral, C., Feria, F., Schubert, A., & Van Uffelen, P. (2023). A review on the thermo-mechanical modelling needs in system codes. Nuclear Engineering and Design, 406, 13. DOI
- Queral, C., & Sanchez-Torrijos, J. (2023, Mai 26). Simulation of the boron dilution sequence in NuScale SMR using 1D and 3D modeling approaches in TRACE. 30th International Conference on Nuclear Engineering (ICONE-30), Kyoto, Japan. DOI
- Redondo-Valero, E., Queral, C., Sanchez-Torrijos, J., Canal, D., & Magan, J. (2023, Mai 26). Thermal-Hydraulic analysis of accidental sequences in NuScale and SMR experimental facilities. Zenodo. DOI
- J.G. Etcheto, V.H. Sanchez-Espinoza, N. Palmans, & D. De Meyer. (2023, August 9). M&C2023 – Study of SMART Steam Line Break with the coupled codes TRACE-PARCS and TRACE-PANTHER. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2023), Niagara Falls, Canada. DOI
- N. Palmans, J.G. Etcheto, M. García, & V.H. Sanchez-Espinoza. (2023, August 15). M&C2023 – H2020 McSafer project: ATWS transient analyses of SMART reactor. DOI
- Bencik, M., Parera-Villacampa, O., Ammirabile, L., Queral, C., Sanchez-Torrijos, J., Diaz-Pescador, E., Jammot, V., & Sanchez-Espinoza, V. H. (2023, August 16). The H2020 McSAFER Project: Analyses of boron dilution for the NuScale reactor. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada. DOI
- 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. (2023, August 16). On the application of advanced modeling tools to the SLB analysis in NuScale. Part I: TRACE/PARCS, TRACE/PANTHER and ATHLET/DYN3D. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada. DOI
- Sanchez-Torrijos, J., & Queral, C. (2023, August 25). Boron Dilution Analysis in NuScale using TRACE and TRACE/SCF codes. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), Washington D.C., USA. DOI
Trainings course
In order to support education in the field of SMR, safety analysis and multi-physics simulations the McSAFER consortium organised three educational trainings courses.
1st Trainings Course: „SMR LWR technologies“
2nd Trainings Course: „SMR neutronics and thermal hydraulics“
3rd Trainings Course (MOOC)
The McSAFER consortium offers a special training course on multi-physics analysis of water-cooled SMR-transients.
- Part 1: Project overview
- Part 2: Overcooling transient description in a CAREM-like SMR
- Part 3: F-SMR scenario description
- Part 4: The K-SMR SMART-based core and the associated REA scenario
- Part 5: NuScale reactor overview
- Part 6: Multi-physics evaluation of pin-level safety criteria
- Part 7a: Fuel performance at single rod and reactor core level
- Part 7b: Nodal diffusion with pin power reconstruction
- Part 8: Pin level transport
- Part 9: An introduction to Monte Carlo neutron transport
- Part 10: Subchannel level thermal hydraulics
- Part 11: Overcooling transient in CAREM-like SMR
- Part 12: F-SMR results
- Part 13: K-SMR/REA transient analysis
- Part 14: Results of NuScale modelling
Deliverables
Our public deliverables are available via the McSAFER community in Zenodo.
- D3.3: Advanced transient heat deposition models for Ants nodal solver including dynamic decay heat
- D3.4: State-of-the art solutions for the transient scenarios in the four SMR codes and intercomparison between codes when applicable
- D3.7: Advanced transient heat deposition models for Serpent including dynamic decay heat
- D4.1: Analysis of SMART plant with 1D system code and intercomparing bewteen codes
- D4.2: Analysis of NuScale plant with 1D system code and intercomparing bewteen codes
- D6.2: Project website
- D6.3: Project corporate identity and communication tools
- D6.5: Report on trainings course
- D6.6: Project newsletter 1