TY - JOUR AU - Čerba, Štefan AU - Haščík, Ján AU - Lüley, Jakub AU - Vrban, Branislav AU - Radulović, Vladimir AU - Jazbec, Anže AU - Snoj, Luka AU - Sklenka, Ľubomír AU - Miglierini, Marcel AU - Czifrus, Szabolcs AU - Tormási, Attila AU - Cagnazzo, Marcella AU - Böck, Helmuth AU - Villa, Mario TI - Education methods of the European nuclear experimental educational platform JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 420 PY - 2024 PG - 11 SN - 0029-5493 DO - 10.1016/j.nucengdes.2024.112973 UR - https://m2.mtmt.hu/api/publication/34579996 ID - 34579996 N1 - Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, Slovak University of Technology in Bratislava, Ilkovičova 3, Bratislava, 841 04, Slovakia Jožef Stefan Institute, Jamova cesta 39, Ljubljana, 1000, Slovenia Department of Nuclear Reactors, Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague, v Holešovičkách 2, Prague, 180 00, Czech Republic Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rakpart 9, Budapest, 1111, Hungary TRIGA Center Atominsititut, Vienna University of Technology, Stadionallee 2, Vienna, 1020, Austria Export Date: 4 March 2024 CODEN: NEDEA Correspondence Address: Cerba; Institute of Nuclear and Physical Engineering, Ilkovičova 3, Slovakia Funding details: 847555, NFRP-2018-7 Funding text 1: The project received funding from the EURATOM Research and Training programme Horizon H2020 , under the topic NFRP-2018-7: “Availability and use of research infrastructures for education, training, and competence building” under the grant agreement no. 847555. LA - English DB - MTMT ER - TY - JOUR AU - Babcsány, Boglárka AU - Giusti, V. AU - Moise, A. AU - Mészáros, Péter AU - Czifrus, Szabolcs AU - Chow, J.C. TI - Results and lessons learned from the Generation IV SCWR-FQT comprehensive Monte Carlo computational benchmark JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 191 PY - 2023 SN - 0306-4549 DO - 10.1016/j.anucene.2023.109903 UR - https://m2.mtmt.hu/api/publication/33939702 ID - 33939702 N1 - Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rakpart 9., Budapest, 1111, Hungary Department of Civil and Industrial Engineering, Pisa University, Largo Lucio Lazzarino 2, Pisa, I-56126, Italy Institute for Nuclear Research Pitesti, Campului Str., Nr. 1, POB 78, Arges, Mioveni, 115400, Romania Canadian Nuclear Laboratories Chalk River, 286 Plant Road, Chalk River, Ontario, K0J 1J0, Canada Export Date: 1 June 2023 CODEN: ANEND Correspondence Address: Babcsány, B.; Institute of Nuclear Techniques, Műegyetem rakpart 9., Hungary; email: boglarka.babcsany@reak.bme.hu AB - 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. LA - English DB - MTMT ER - TY - JOUR AU - Ványi, András Szabolcs AU - Hursin, M. AU - Czifrus, Szabolcs TI - Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 194 PY - 2023 SN - 0306-4549 DO - 10.1016/j.anucene.2023.110072 UR - https://m2.mtmt.hu/api/publication/34104422 ID - 34104422 N1 - Export Date: 29 August 2023 CODEN: ANEND Correspondence Address: Ványi, A.S.; Institute of Nuclear Techniques, Műegyetem rkp. 3., Hungary; email: vanyi.andras@reak.bme.hu LA - English DB - MTMT ER - TY - JOUR AU - Ványi, András Szabolcs AU - Hursin, M. AU - Aszódi, Attila AU - Adorján, László AU - Biró, Bence AU - Magyar, Boglárka AU - Mészáros, Péter AU - Bozsó, Tamás Miklós AU - Czifrus, Szabolcs TI - Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 189 PY - 2023 SN - 0306-4549 DO - 10.1016/j.anucene.2023.109839 UR - https://m2.mtmt.hu/api/publication/33748176 ID - 33748176 LA - English DB - MTMT ER - TY - JOUR AU - Pónya, P. AU - Czifrus, Szabolcs AU - Bozsó, Tamás Miklós TI - Core optimization of UO2 fuelled ALLEGRO reactor JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 178 PY - 2022 PG - 15 SN - 0306-4549 DO - 10.1016/j.anucene.2022.109374 UR - https://m2.mtmt.hu/api/publication/33091251 ID - 33091251 N1 - Budapest University of Technology and Economics, Budapest, Hungary Centre for Energy Research, Budapest, Hungary Export Date: 13 September 2022 CODEN: ANEND Correspondence Address: Pónya, P.; Institute of Nuclear Techniques, 1111 Budapest, Műegyetem rkp. 3., Hungary; email: petraponya@gmail.com LA - English DB - MTMT ER - TY - JOUR AU - Ványi, András Szabolcs AU - Hursin, M. AU - Czifrus, Szabolcs TI - Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 174 PY - 2022 PG - 11 SN - 0306-4549 DO - 10.1016/j.anucene.2022.109147 UR - https://m2.mtmt.hu/api/publication/33080582 ID - 33080582 N1 - Funding Agency and Grant Number: Euratom research and training programme [945041] Funding text: This project has received funding from the Euratom research and training programme 2019-2020 under grant agreement No 945041. AB - 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/). LA - English DB - MTMT ER - TY - CHAP AU - Ványi, András Szabolcs AU - Mathieu, Hursin AU - Czifrus, Szabolcs ED - Cizelj, L ED - Tekavcic, M TI - Investigation of Recently Introduced Diffusion Coefficient Generation Methods T2 - 30th International Conference Nuclear Energy for New Europe (NENE 2021) PB - Nuclear Society of Slovenia CY - Ljubljana SN - 9789616207515 PY - 2021 PG - 8 UR - https://m2.mtmt.hu/api/publication/32693578 ID - 32693578 AB - 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. LA - English DB - MTMT ER - TY - JOUR AU - Ványi, András Szabolcs AU - Babcsány, Boglárka AU - Böröczki, Zoltán István AU - Horváth, András AU - M., Hursin AU - Szieberth, Máté AU - Czifrus, Szabolcs TI - Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 155 PY - 2021 SN - 0306-4549 DO - 10.1016/j.anucene.2021.108144 UR - https://m2.mtmt.hu/api/publication/31882167 ID - 31882167 LA - English DB - MTMT ER - TY - JOUR AU - Krykova, M AU - Schulenberg, T AU - Ruzickova, MA AU - Saez-Maderuelo, A AU - Otic, I AU - Czifrus, Szabolcs AU - Cizelj, L AU - Pavel, GL TI - European Research Program on Supercritical Water-Cooled Reactor JF - JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE J2 - J NUCLEAR ENG RAD SCI VL - 7 PY - 2021 IS - 2 PG - 5 SN - 2332-8983 DO - 10.1115/1.4048901 UR - https://m2.mtmt.hu/api/publication/31959409 ID - 31959409 N1 - Research and Development Section, Centrum vyzkumu Rez, Husinec – Rez, 250 68, Czech Republic Institute for Applied Thermofluidics, Karlsruhe Institute of Technology, Karlsruhe, 761 31, Germany Department of Power Engineering, University of Chemistry and Technology, Prague, 166 28, Czech Republic Technology Departement, Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Madrid, 280 40, Spain Institute of Nuclear Techniques, Budapesti Muszaki es Gazdasagtudomanyi, Egyetem, Budapest, 1111, Hungary Reactor Engineering Department, Institut Jozef Stefan, Ljubljana, 1000, Slovenia Secretariat Office, European Nuclear Education Network, Brussels, 1000, Belgium Export Date: 15 November 2021 Funding details: European Commission, EC Funding details: German-Israeli Foundation for Scientific Research and Development, GIF Funding text 1: 2.3 ECC-SMART. The ECC-SMART project is oriented toward assessing the feasibility and identification of safety features of an intrinsically and passively safe supercritical water-cooled small modular reactor (SCW-SMR), taking into account specific knowledge gaps related to the future licensing process— especially the assessment of the constructional materials with special attention to the influence of irradiation, validation of engineering simulation tools like system-, subchannel-, and computational fluid dynamics codes, core design as well as the licensing process itself. The content of the project is supported by significant international platforms. The SCWR is one of the Generation IV (Gen IV) systems proposed by the GIF, the Nuclear Generation II & III Alliance (NUGENIA, currently the Sustainable Nuclear Energy Technology Platform—SNETP) supported the E-SMART (original EU initiative) in 2016 by NUGENIA label and the proposal was supported by European Energy research Alliance Joint Program of Nuclear Materials (EERA JPNM) in 2019, as well. Funding text 2: Keywords: supercritical water-cooled reactor, small modular reactor, research program summary, projects supported by European Commission LA - English DB - MTMT ER - TY - JOUR AU - Radulovic, Vladimir AU - Jazbec, Anze AU - Snoj, Luka AU - Hascik, Jan AU - Vrban, Branislav AU - Cerba, Stefan AU - Luley, Jakub AU - Osusky, Filip AU - Sklenka, L'ubomir AU - Miglierini, Marcel AU - Novak, Ondrej AU - Bock, Helmuth AU - Cagnazzo, Marcella AU - Villa, Mario AU - Czifrus, Szabolcs AU - Tormási, Attila TI - The European Nuclear Experimental Educational Platform - ENEEP: Progress, Prospects and Remote Education Capabilities JF - EPJ WEB OF CONFERENCES J2 - EPJ WEB CONF VL - 253 PY - 2021 PG - 7 SN - 2101-6275 DO - 10.1051/epjconf/202125310002 UR - https://m2.mtmt.hu/api/publication/32831462 ID - 32831462 N1 - Funding Agency and Grant Number: European Union [847555]; University of Uppsala; Aix-Marseille University; University of Ljubljana Funding text: The ENEEP project has received funding from the European Union's Horizon 2020 research and innovation programme under grant agreement No. 847555. The JSI would like to acknowledge the support from the University of Uppsala, University of Ljubljana and the Aix-Marseille University in the performance of remote education activities. AB - 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. LA - English DB - MTMT ER -