Open Access
| Issue |
EPJ Nuclear Sci. Technol.
Volume 11, 2025
European Nuclear Society PhD Award
|
|
|---|---|---|
| Article Number | 76 | |
| Number of page(s) | 28 | |
| DOI | https://doi.org/10.1051/epjn/2025072 | |
| Published online | 02 December 2025 | |
- I.L. Pioro, Handbook of Generation IV Nuclear Reactors, 1st edn. (Elsevier Ltd, 2016) [Google Scholar]
- D.T. Ingersoll, M.D. Carelli, Handbook of Small Modular Nuclear Reactors, 2nd ed. (Elsevier Ltd, 2021) [Google Scholar]
- ECC-SMART project webpage: https://cordis.europa.eu/project/id/945234, last visited: 20.01.2025 [Google Scholar]
- T. Schulenberg, I. Otic, Suggestion for design of a small modular SCWR, ISSCWR1-P019, in 10th International Symposium on SCWRs (ISSCWR-10), Prague, Czech Republic, March 15–19, 2021 [Google Scholar]
- J. Starflinger, T. Schulenberg, High Performance Light Water Reactor: Design and Analyses (KIT Scientific Publishing, 2012) [Google Scholar]
- Y. Oka, S. Koshizuka, Y. Ishiwatari, A. Yamaji, Super Light Water Reactors and Super Fast Reactors: Supercritical-Pressure Light Water Cooled Reactors (Springer, 2010) [Google Scholar]
- Apros webpage, https://www.apros.fi/, last visited: 23.01.2025 [Google Scholar]
- ANSYS CFX webpage, https://www.ansys.com/products/fluids/ansys-cfx, last visited: 23.01.2025 [Google Scholar]
- J. Leppänen et al., The Serpent Monte Carlo code: Status, development and applications in 2013, Ann. Nucl. Energy 82, 142 (2015), https://doi.org/10.1016/j.anucene.2014.08.024 [CrossRef] [Google Scholar]
- B. Babcsány, Ph.D. thesis, Development of a finite-element-based neutron physics code system for the solution of the simplified P3 approximation to the neutron transport equation Budapest University of Technology and Economics, Budapest, Hungary, 2021 [Google Scholar]
- T. Varju, A. Kiss, Cs. Antók, B. Babcsány, I. Boros, P. Mészáros, Z. Bertesina, Sz. Czifrus, Current results of BME NTI in the ECC-SMART project: Different analysis on the SCW-SMR, in Proc. of ICONE31 conference, Prague, Czech Republic, August 4–8, 2024, https://doi.org/10.1115/ICONE31-135760 [Google Scholar]
- T. Varju, B. Babcsány, P. Mészáros, Cs. Antók, Sz. Czifrus, Coupled reactor physics and thermal hydraulics analysis of an SCW-SMR reactor concept – Part I: Model development and demonstration, Ann. Nucl. Energy 217, 111222 (2025), https://doi.org/10.1016/j.anucene.2025.111222 [Google Scholar]
- T. Varju, Cs. Antók, P. Mészáros, B. Babcsány, Coupled reactor physics and thermal hydraulics analysis of an SCW-SMR reactor concept – Part II: Improvement of the concept and sensitivity analyses, Ann. Nucl. Energy 217, 111221 (2025), https://doi.org/10.1016/j.anucene.2025.111221 [Google Scholar]
- U. Le Tennier, G. Marleau, Neutronics-thermalhydraulics coupled analysis of Canadian SCWR based on DONJON5 and CATHENA, Nucl. Eng. Des. 426, 113346 (2024), https://doi.org/10.1016/j.nucengdes.2024.113346 [Google Scholar]
- A. Hébert, A User Guide for TRIVAC Version 5, Technical Report, IGE–369, Polytechnique Montréal Technological University, 2023, http://merlin.polymtl.ca/downloads/IGE369.pdf [Google Scholar]
- D.W. Hummel, Ph.D. thesis, Coupled Neutronic-Thermalhydraulic Transient Behaviour of a PT-SCWR Reactor, McMaster University, Hamilton, Canada, 2015 [Google Scholar]
- Cs. Maráczy, A. Keresztúri, I. Trosztel, Gy. Hegyi, Safety analysis of reactivity initiated accidents in a HPLWR reactor by the coupled ATHLET-KIKO3D code, Prog. Nucl. Energy 52, 190 (2010), https://doi.org/10.1016/j.pnucene.2009.06.005 [Google Scholar]
- Gy. Hegyi, A. Kereszturi, Cs. Maráczy, I. Trosztel, Reactivity Initiated Accident Analysis of the HPLWR Three Pass Core with Ascending Gap Flow Using the KIKO 3 D-ATHLET Code, in International Conference Nuclear Energy for New Europe, Portorož, Slovenia, September 6–9, 2010, https://arhiv.djs.si/proc/port2010/pdf/505.pdf [Google Scholar]
- M. Seppälä, Neutronic and Thermal-hydraulic Modelling of High Performance Light Water Reactor, Paper No. 124, in International Youth Nuclear Congress, Interlaken, Switzerland, 20–26 September, 2008, https://inis.iaea.org/records/4kjx5-dgw08/files/40048082.pdf?download=1 [Google Scholar]
- C. Geuzaine, J.-F. Remacle, Gmsh: A three-dimensional finite element mesh generator with built-in pre- and post-processing facilities, Int. J. Numer. Meth. Eng. 79, 1309 (2009), https://doi.org/10.1002/nme.2579 [CrossRef] [Google Scholar]
- Z. Bertesina, MSc thesis, Coupled thermal hydraulics and neutron physics analysis of an SCW-SMR reactor concept, Budapest University of Technology and Economics, Budapest, Hungary, 2023 [Google Scholar]
- T. Varju, Z. Bertesina, B. Babcsány, Coupling of Apros and SPNDYN to analyse the SCW-SMR concept within ECC-SMART, ISSCWR11-P007, in 11th International Symposium on SCWRs (ISSCWR-11), Pisa, Italy, February 3–5, 2025, https://doi.org/10.12871/9791256081332 [Google Scholar]
- T. Schulenberg, I. Otic, Concept of a small modular SCWR with horizontal fuel assemblies, J. Nucl. Eng. Radiat. Sci. 8, 031104 (2022), https://doi.org/10.1115/1.4052191 [Google Scholar]
- Zs.J. Várkonyi, Coupled equilibrium state calculation for the SCW-SMR core concept with updated BoC core layout, in Students’ Scientific Conference, Competition Essay (in Hungarian), University of Technology and Economics, Budapest, Hungary, 2024 [Google Scholar]
- J. Kurki, M. Seppälä, Thermal Hydraulic Transient Analysis of the High Performance Light Water Reactor Using APROS and SMABRE, SMiRT 20 – Division X, Paper 3164, in 20th International Conference on Structural Mechanics in Reactor Technology, Espoo, Finland, August 9–14, 2009, https://www.apros.fi/wp-content/uploads/sites/27/2020/09/59-SMiRT20_HPLWR_paper_2009.pdf [Google Scholar]
- M. Andreani, D. Bittermann, Ph. Marsault, O. Antoni, A. Keresztúri, M. Schlagenhaufer, A. Manera, M. Seppäla, J. Kurki, Evaluation of a preliminary safety concept for the HPLWR, Prog. Nucl. Energy 55, 68 (2009), https://doi.org/10.1016/j.pnucene.2011.11.004 [Google Scholar]
- O. Chaaraoui, A. Pucciarelli, W. Ambrosini, I. Otic, T. Schulenberg, C. Allison, Z. Fu, Customising a system code for the analysis of the thermal-hydraulic behavior of a supercritical pressure light water small modular reactor, in Proceedings of the 31st International Conference on Nuclear Engineering, Prague, Czech Republic, August 4–8, 2024, https://doi.org/10.1115/ICONE31-135160 [Google Scholar]
- T. Varju, A. Csige, A. Kiss, V. Filonov, Y. Filonova, D. Fedorov, A. Pucciarelli, S. Kassem, W. Ambrosini, Discussion and perspectives for improvements of heat transfer correlation capabilities for fluids at supercritical pressures, Nucl. Eng. Des. 421, 113085 (2024), https://doi.org/10.1016/j.nucengdes.2024.113085 [Google Scholar]
- A.A. Bishop, R.O. Sandberg, L.S. Tong, Forced convection heat transfer to water near critical temperatures and super-critical pressures, A.I.Ch.E.-I.Chem.E. Symp. Ser. 2, 77 (1965) [Google Scholar]
- A. Kiss, L. Adorján, Comparison of CFD analysis results of horizontal flow in SCW-SMR fuel assembly with and without wrapped wire spacers, ISSCWR11-P089, in 11th International Symposium on SCWRs (ISSCWR-11), Pisa, Italy, February 3–5, 2025, https://doi.org/10.12871/9791256081332 [Google Scholar]
- A. Kiss, B. Kiss, Discussing CFD analysis of horizontal and vertical upward flow under supercritical conditions, ISSCWR11-P021, in 11th International Symposium on SCWRs (ISSCWR-11), Pisa, Italy, February 3–5, 2025, https://doi.org/10.12871/9791256081332 [Google Scholar]
- Cs. Antók, Sz. Czifrus, V. Giusti, Neutronic calculations for preliminary core design of SCW-SMR, Ann. Nucl. Energy 209, 110805 (2024), https://doi.org/10.1016/j.anucene.2024.110805 [Google Scholar]
- P. Mészáros, MSc thesis, Reactor physics and thermal hydraulics analysis of the SCW-SMR conceptual design with the Serpent 2 and Apros codes (in Hungarian), Budapest University of Technology and Economics, Budapest, Hungary, 2023 [Google Scholar]
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