Databases:

A. Journal articles

2025

A.1 B. Babcsány et al., 2025. Equilibrium state core calculations for an SCW-SMR concept using the Apros-SPNDYN coupled code system. EPJ N – Nuclear Sciences & Technologies, 11 (2025) 76

A.2 T. Varju et al., 2025. Coupled reactor physics and thermal-hydraulics analysis of an SCW-SMR reactor concept – Part I: Model development and demonstration. Annals of Nuclear Energy, 217, 111222 (2025)

A.3 T. Varju et al., 2025. Coupled reactor physics and thermal-hydraulics analysis of an SCW-SMR reactor concept – Part II: Improvement of the concept and sensitivity analyses. Annals of Nuclear Energy, 217, 111221 (2025)

2023

A.4 B. Babcsány et al., 2023. Results and lessons learned from the Generation IV SCWR-FQT comprehensive Monte Carlo computational benchmark. Annals of Nuclear Energy, 191, 109903 (2023)

A.5 Z.I. Böröczki, B. Babcsány, J.E. Maróti, M. Szieberth, 2023. On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Higher-Order Transport Calculations. Nuclear Science and Engineering, 197/8, pp. 1545-1563 (2023)

2022

A.6 B. Babcsány, I. Pós, Z.I. Böröczki, D.P. Kis, 2022. Hybrid finite-element-based numerical solution of the SP₃ equations – SP₃ solution of two- and three-dimensional VVER reactor problems. Annals of Nuclear Energy, 173 (2022)

2021

A.7 B. Babcsány, I. Pós, D.P. Kis, 2021. Hybrid finite-element-based numerical solution of the multi-group SP₃ equations and its application on hexagonal reactor problems. Annals of Nuclear Energy, 155 (2021)

A.8 A.Sz. Ványi, B. Babcsány, Z.I. Böröczki, A. Horváth, M. Hursin, M. Szieberth, Sz. Czifrus, 2021. Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor. Annals of Nuclear Energy, 155 (2021)

A.9 A. Aszódi, B. Babcsány, 2021. Site investigation in service of nuclear safety (in Hungarian). Magyar Tudomány, 182 (2021) 7

2020

A.10 B. Babcsány, D.P. Kis, 2020. Semi-analytical methods for SP₃ equations solver verification including third-order scattering anisotropy. Annals of Nuclear Energy, 148 (2020)

A.11 B. Babcsány, T. Bartók, D. P. Kis, 2020. Finite element solution of the time-dependent SP₃ equations using an implicit integration scheme. Kerntechnik, 85 (2020) 4; 292-300.

A.12 B. Babcsány, T. Hajas, P. Mészáros, 2020. Finite-element-based diffusion modeling of transient reactor physics processes (in Hungarian). Nukleon, XIII. (2020) 233

2017

A.13 T. Hajas, P. Pandazis, L. Lovász and B. Babcsány, 2017. New finite element-based modeling of reactor core support plate failure. Kerntechnik, 82 (2017) 6; 685-692.

2016

A.14 P. Pandazis, B. Babcsany, 2016. Numerical and experimental investigation of surface vortex formation in coolant reservoirs of reactor safety systems. Kerntechnik, 81 (2016) 5; 477-483.

2015

A.15 B. Babcsány, Sz. Czifrus, S. Fehér, 2015. Methodology and conclusions of activation calculations of WWER-440 type nuclear power plants. Nuclear Engineering and Design, Vol. 284., 228-237.

B. Conference papers

2025

B.1 Zs.J. Várkonyi et al., 2025. Coupled equilibrium state calculation for the SCW-SMR core concept with updated BoC core layout. In Proceedings of the European Nuclear Young Generation Forum (ENYGF’25), Zagreb, Croatia, 2-6 June 2025

B.2 A. Zsiros, T. Varju, B. Babcsány, 2025. Further development of the Apros-SPNDYN coupled thermohydraulic-reactor physics code system for transient calculations for the SCW-SMR core concept. In Proceedings of the European Nuclear Young Generation Forum (ENYGF’25), Zagreb, Croatia, 2-6 June 2025

B.3 T. Varju, Z. Bertesina, B. Babcsány, 2025. Coupling of Apros and SPNDYN to analyse the SCW-SMR concept within ECC-SMART. In Proceedings of the 11^th International Symposium on Supercritical Water-Cooled Reactors, pp. 173-185, Pisa, Italy, 3-5 February 2025

B.4 G. Illés, B. Babcsány, 2025. Hybrid finite element SP_N analysis of an SCW-SMR concept within the ECC-SMART project . In Proceedings of the 11^th International Symposium on Supercritical Water-Cooled Reactors, pp. 187-198, Pisa, Italy, 3-5 February 2025.

2024

B.5 T. Varju et al., 2024. Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR. In Proceedings of the 31^st International Conference on Nuclear Engineering, Volume 4, ICONE31-135760, V004T04A058, 11 p., Prague, Czech Republic, 4-8 August 2024

2022

B.6 B. Babcsány, V. Giusti, A. Moise, J. C. Chow, 2022. Comparative Analysis of Energy Deposition Modes Available in Serpent 2 Within the Framework of the SCWR-FQT Reactor Physics Benchmark. In Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022), Pittsburgh, PA, USA, 15-20 May 2022

B.7 B. Babcsány, Z. I. Böröczki, J. E. Maróti, M. Szieberth, 2022. On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Few-Group Transport Calculations. In Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022), Pittsburgh, PA, USA, 15-20 May 2022

2019

B.8 B. Babcsány, T. Bartók, D. P. Kis, 2019. Finite element solution of the time-dependent SP₃ equations using an implicit integration scheme. In Proceedings of 29^th Symposium of AER on VVER Reactor Physics and Reactor Safety, Energoland, Mochovce NPP, Slovakia, 14-18 October 2019.

2015

B.9 B. Babcsány, S. Fehér, I. Pós, T. Parkó, 2015. Hybdrid Finite Element Solution of the Simplified P₃ equations. In Proceedings of 25^rd Symposium of AER on VVER Reactor Physics and Reactor Safety, Balatongyörök, Hungary, 13-16 October 2015.

2013

B.10 B. Babcsány, Sz. Czifrus, S. Fehér, 2013. Methodologies for the determination of the activation of steel components and concrete structures of WWER-440 type nuclear power plants. In Proceedings of 23^rd Symposium of AER on VVER Reactor Physics and Reactor Safety, Štrbskê Pleso, Slovakia, 30 September – 4 October 2013.

B.11 B. Babcsány, 2013. Is the new German energy policy sustainable? In Proceedings of 4^th International Youth Conference on Energy (IYCE 2013), Siófok, Hungary, 6-8 June 2013, IEEE Xplore Digital Library.

C. Research reports

2024

C.1 B. Babcsány: Comprehensive testing of the SP₃ routine implemented into the C-PORCA program – Part II.. BME-NTI-1023/2024. (in Hungarian)

2023

C.2 B. Babcsány: Comprehensive testing of the SP₃ routine implemented into the C-PORCA program – Part I. BME-NTI-1013/2023. (in Hungarian)

2021

C.3 ECC-SMART WP4, 2021: D4.1: Neutron physics code selection results. BME-NTI-976/2021.

C.4 A. Aszódi et al.: Expert review of the listed, fuel-related subchapters of the Preliminary Safety Analysis Report (PSAR). BME-NTI-964/2021. (in Hungarian)

2019

C.5 B. Babcsány: Two-dimensional SP₃ modelling of the VVER-440 core. BME-NTI-908/2019. (in Hungarian)

2018

C.6 B. Babcsány, M. Halász: Analysing the possibilities for increasing the accuracy of the SP₃-method integrated into the C-PORCA program. BME-NTI-864/2018. (in Hungarian)

2017

C.7 B. Babcsány, S. Fehér: Developing the accuracy of the SP₃-method integrated into the C-PORCA program by taking into account anisotropic neutron scattering. BME-NTI-826/2017. (in Hungarian)

2014

C.8 S. Fehér, B. Babcsány: Further development of the HELIOS – C-PORCA code system with a module capable of the reactor physical characterisation of irregular geometric configurations, Part III. Testing and verification of the developed SP₃-method. BME-NTI-706/2014. (in Hungarian)

C.9 M. Szieberth, L. Nagy, B. Babcsány: Involvement in the evaluation of measurements conducted on the VENUS-F subcritical facility using neutron noise methods. BME-NTI-693/2014. (in Hungarian)

C.10 I. Boros et al. (co-author): Lessons learnt from the Fukushima accident on a national and international level – Summary of the emergency preparedness practices. BME-NTI-670/2014. (in Hungarian

2013

C.11 Sz. Czifrus, B. Babcsány: Analyses and calculations concerning the graphite applied in the BME Training Reactor. BME-NTI-632/2013. (in Hungarian)

C.12 Sz. Czifrus, S. Fehér, B. Babcsány: Determination of the activity of the steel components and shielding concrete structures of the Armenian Nuclear Power Plant. BME-NTI-609/2013.

D. Other documents

2019

D.1 IAEA Safety Report (co-author): Methodologies for Assessing the Induced Activation Source Term for Use in Decommissioning Applications. Safety Reports Series No. 95. Published in 2019.

E. Theses

2022

E.1 Development of a finite-element-based reactor physics code system for the solution of the simplified P₃ approximation to the neutron transport equation. PhD thesis, Budapest University of Technology and Economics

 2014

E.2 Evaluation of neutron noise measurements performed on a subcritical system and comparison of the results with simulations. Master thesis, Budapest University of Technology and Economics

2013

E.3 MCNP simulation of reactivity measurements with pulsed neutron source on the BME Training Reactor. Bachelor thesis, Budapest University of Technology and Economics