@article{MTMT:34579996, title = {Education methods of the European nuclear experimental educational platform}, url = {https://m2.mtmt.hu/api/publication/34579996}, author = {Čerba, Štefan and Haščík, Ján and Lüley, Jakub and Vrban, Branislav and Radulović, Vladimir and Jazbec, Anže and Snoj, Luka and Sklenka, Ľubomír and Miglierini, Marcel and Czifrus, Szabolcs and Tormási, Attila and Cagnazzo, Marcella and Böck, Helmuth and Villa, Mario}, doi = {10.1016/j.nucengdes.2024.112973}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {420}, unique-id = {34579996}, issn = {0029-5493}, year = {2024}, eissn = {1872-759X}, orcid-numbers = {Čerba, Štefan/0000-0002-4065-3976} } @article{MTMT:33939702, title = {Results and lessons learned from the Generation IV SCWR-FQT comprehensive Monte Carlo computational benchmark}, url = {https://m2.mtmt.hu/api/publication/33939702}, author = {Babcsány, Boglárka and Giusti, V. and Moise, A. and Mészáros, Péter and Czifrus, Szabolcs and Chow, J.C.}, doi = {10.1016/j.anucene.2023.109903}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {191}, unique-id = {33939702}, issn = {0306-4549}, abstract = {A joint European Canadian Chinese development of a supercritical water-cooled small modular reactor technology has been in progress since September 2020 in the framework of a Horizon 2020 project called ECC-SMART. A specific work package has been dedicated to studying the design-and safety-related neutronic parameters and reactor physics behavior of the SCW-SMR to support the pre-conceptual design process. Three Monte Carlo codes, viz., MCNP, OpenMC, and Serpent, were selected for pre-conceptual design applications and code-to-code comparison within the Gen-IV SCWR-FQT reactor physics computational benchmark. The effective multiplication factor, the axial power distribution within the fuel, the axial three-group neutron flux distribution, and the spatial distribution of the energy deposition due to neutron and photon interactions were determined. In this paper, results and lessons learned from this study are presented, and useful considerations are summarized to provide guidance in obtaining consistent results among the three Monte Carlo codes.}, keywords = {Monte Carlo; SCWR; SMR; Fuel Qualification Test}, year = {2023}, eissn = {1873-2100} } @article{MTMT:34104422, title = {Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor}, url = {https://m2.mtmt.hu/api/publication/34104422}, author = {Ványi, András Szabolcs and Hursin, M. and Czifrus, Szabolcs}, doi = {10.1016/j.anucene.2023.110072}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {194}, unique-id = {34104422}, issn = {0306-4549}, year = {2023}, eissn = {1873-2100} } @article{MTMT:33748176, title = {Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor}, url = {https://m2.mtmt.hu/api/publication/33748176}, author = {Ványi, András Szabolcs and Hursin, M. and Aszódi, Attila and Adorján, László and Biró, Bence and Magyar, Boglárka and Mészáros, Péter and Bozsó, Tamás Miklós and Czifrus, Szabolcs}, doi = {10.1016/j.anucene.2023.109839}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {189}, unique-id = {33748176}, issn = {0306-4549}, year = {2023}, eissn = {1873-2100}, orcid-numbers = {Hursin, M./0000-0002-1308-4464; Adorján, László/0000-0002-5515-4651; Magyar, Boglárka/0000-0002-0746-0160} } @article{MTMT:33091251, title = {Core optimization of UO2 fuelled ALLEGRO reactor}, url = {https://m2.mtmt.hu/api/publication/33091251}, author = {Pónya, P. and Czifrus, Szabolcs and Bozsó, Tamás Miklós}, doi = {10.1016/j.anucene.2022.109374}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {178}, unique-id = {33091251}, issn = {0306-4549}, year = {2022}, eissn = {1873-2100} } @article{MTMT:33080582, title = {Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors}, url = {https://m2.mtmt.hu/api/publication/33080582}, author = {Ványi, András Szabolcs and Hursin, M. and Czifrus, Szabolcs}, doi = {10.1016/j.anucene.2022.109147}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {174}, unique-id = {33080582}, issn = {0306-4549}, abstract = {Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power reactor design, safety calculations and plant cycle simulations. The large-size, small-leakage property of these reactor cores and the appropriately generated and applied auxiliary parameters (such as albedos, discontinuity factors etc.) provide a calculation environment, where diffusion theory is fairly accurate, giving the industry the ultimate advantage of fast neutronic computation. Recently, several efforts have been made to extend this methodology to small-core, high-leakage research reactors, in which the validity of diffusion theory is not straightforward. In this paper, the appropriate generation of the diffusion coefficients and their effect on the overall performance of the simulations are investigated in light of recent developments. For the numerical analysis, the two-dimensional DIMPLE benchmarks and the BME TR core benchmark problems were chosen. Group constants were generated with the Serpent 2 Monte Carlo code, while nodal diffusion calculations were carried out with the PARCS code. The results were assessed in terms of multiplication factor, assembly level power and two-group flux distributions. (c) 2022 The Author(s). Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).}, keywords = {DIFFUSION; diffusion coefficient; Reactor physics; Small-core; High-leakage; Transport cross section}, year = {2022}, eissn = {1873-2100} } @inproceedings{MTMT:32693578, title = {Investigation of Recently Introduced Diffusion Coefficient Generation Methods}, url = {https://m2.mtmt.hu/api/publication/32693578}, author = {Ványi, András Szabolcs and Mathieu, Hursin and Czifrus, Szabolcs}, booktitle = {30th International Conference Nuclear Energy for New Europe (NENE 2021)}, unique-id = {32693578}, abstract = {The multigroup diffusion theory is one of the most widely used methods for deterministic reactor core calculations. In this approach the angular dependence of the neutron flux and the scattering kernel is expanded with spherical harmonics to the P 1 order. The P 1 scattering matrix is then used to generate a scalar quantity for each energy group, the group diffusion coefficient. As the entire linearly anisotropic angular dependence is represented in the group diffusion coefficients, the accuracy of the diffusion calculations highly depends on how those coefficients are determined. Recently, two approaches were introduced by researchers of the Massachusetts Institute of Technology to produce accurate diffusion coefficients using Monte Carlo codes: the Neutron Leakage Correction method [1] and the Cumulative Migration Method [2]. After providing a brief overview of the methods, a parametric study is carried out in this paper where the performance of those approaches in terms of power distribution and multiplication factor of the associated diffusion calculations is assessed. For this purpose, 1D and 2D models based on the specifications of the DIMPLE benchmark [3] are used. The Monte Carlo simulations for group constant generation and reference calculations were carried out by the Serpent 2 code, while the deterministic calculations were performed by the PARCS nodal diffusion code.}, keywords = {environmental studies}, year = {2021} } @article{MTMT:31882167, title = {Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor}, url = {https://m2.mtmt.hu/api/publication/31882167}, author = {Ványi, András Szabolcs and Babcsány, Boglárka and Böröczki, Zoltán István and Horváth, András and M., Hursin and Szieberth, Máté and Czifrus, Szabolcs}, doi = {10.1016/j.anucene.2021.108144}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {155}, unique-id = {31882167}, issn = {0306-4549}, year = {2021}, eissn = {1873-2100}, orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352} } @article{MTMT:31959409, title = {European Research Program on Supercritical Water-Cooled Reactor}, url = {https://m2.mtmt.hu/api/publication/31959409}, author = {Krykova, M and Schulenberg, T and Ruzickova, MA and Saez-Maderuelo, A and Otic, I and Czifrus, Szabolcs and Cizelj, L and Pavel, GL}, doi = {10.1115/1.4048901}, journal-iso = {J NUCLEAR ENG RAD SCI}, journal = {JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE}, volume = {7}, unique-id = {31959409}, issn = {2332-8983}, year = {2021}, eissn = {2332-8975} } @article{MTMT:32831462, title = {The European Nuclear Experimental Educational Platform - ENEEP: Progress, Prospects and Remote Education Capabilities}, url = {https://m2.mtmt.hu/api/publication/32831462}, author = {Radulovic, Vladimir and Jazbec, Anze and Snoj, Luka and Hascik, Jan and Vrban, Branislav and Cerba, Stefan and Luley, Jakub and Osusky, Filip and Sklenka, L'ubomir and Miglierini, Marcel and Novak, Ondrej and Bock, Helmuth and Cagnazzo, Marcella and Villa, Mario and Czifrus, Szabolcs and Tormási, Attila}, doi = {10.1051/epjconf/202125310002}, journal-iso = {EPJ WEB CONF}, journal = {EPJ WEB OF CONFERENCES}, volume = {253}, unique-id = {32831462}, issn = {2101-6275}, abstract = {The European Nuclear Experimental Educational Platform - ENEEP is currently being established by five European educational and research organizations in the framework of a Horizon 2020 project, initiated in 2019. The ENEEP partner institutions are the Jozef Stefan Institute (JSI, Slovenia), the Slovak University of Technology in Bratislava (STU, Slovak Republic), the Czech Technical University in Prague (CTU, Czech Republic), Technische Universitat Wien (TU Wien, Austria) and the Budapest University of Technology and Economics (BME, Hungary). ENEEP is intended as an open educational platform, offering experimental hands-on education activities at the ENEEP partner facilities. ENEEP education activities will be offered in different formats (group and individual) and are targeted at university students at all educational levels and young professionals in the nuclear field. This paper gives an overview of the ENEEP project activities and the progress achieved thus far, highlighting the experimental capabilities which will be offered. In the first implementation phase, ENEEP will be based on a comprehensive set of experiments comprising the basics in Reactor Physics and Nuclear Engineering curricula, as well as more specific experiments focusing on particular aspects investigated phenomena, types and working principles of detectors, etc. Subsequently, novel education activities will be introduced and implemented in ENEEP, following scientific development in nuclear science and technology and nuclear instrumentation detectors, stemming from research activities. Attention will be devoted to the development and optimization of remote education capabilities at the ENEEP partner institutions, of particular relevance during the current Covid-19 pandemic, which is responsible for major changes in education activities worldwide.}, keywords = {Experimental Education activities; Nuclear Science and Technology}, year = {2021}, eissn = {2100-014X} }