TY - JOUR AU - Antók, Csenge AU - Czifrus, Szabolcs AU - Giusti, Valerio TI - Neutronic calculations for preliminary core design of SCW-SMR JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 209 PY - 2024 PG - 15 SN - 0306-4549 DO - 10.1016/j.anucene.2024.110805 UR - https://m2.mtmt.hu/api/publication/35172363 ID - 35172363 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 Export Date: 16 August 2024 CODEN: ANEND Correspondence Address: Antók, C.; Institute of Nuclear Techniques, Műegyetem rakpart 9., Hungary; email: antok@reak.bme.hu Funding details: 945234 Funding text 1: The research presented in this paper was carried out in the framework of the Horizon2020 project ECC-SMART (Joint) European Canadian Chinese development of Small Modular Reactor Technology under grant agreement No 945234. The authors are grateful for the data and information provided by Prof. Thomas Schulenberg and Ivan Otic (KIT). We would also like to thank Bogl\\u00E1rka Babcs\\u00E1ny for her cooperation and ideas in the project. Funding text 2: The research presented in this paper was carried out in the framework of the Horizon2020 project ECC-SMART (Joint) European Canadian Chinese development of Small Modular Reactor Technology under grant agreement No 945234. AB - Serpent 2 particle transport code is used to develop the pre-conceptual neutronic design of the Supercritical Water Cooled SMR. After initial criticality and burnup calculations, the starting core design of (Schulenberg and Otic, 2021) is improved using predetermined criteria, such as burnup cycle length and power distribution, while also considering operational safety. In order to achieve higher reserve reactivity, several modifications are considered, including the introduction of alternative structural materials and fuel assembly wall type, moderation improvement by adjustment of moderator temperature and fuel assembly gap width, and selection of a suitable enrichment map. As a result of the introduced modifications, the burnup cycle length is increased to 26 months and an acceptable core power distribution is achieved. The improved core design can be used for further investigations, such as coupled calculations using neutronic and thermal–hydraulic codes and examinations targeting reactivity control during burnup. © 2024 The Author(s) LA - English DB - MTMT ER - 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. AB - This paper presents the educational methods of the European Nuclear Experimental Educational Platform (ENEEP), an open platform continuing the legacy of the H2020 ENEEP project. It offers a brief overview of the current state of education, training, and vocational education in the European Union, emphasising the imperative for a skilled and competent workforce in the future. Subsequent sections outline the objectives, timeline, and structure of the ENEEP project. The most important part is the description of educational methods developed within the project to deliver high-quality tailored courses. Specific attention is given to a series of demonstration courses, wherein the efficacy of these methods was systematically measured and evaluated. The final part of the paper outlines the vision of the ENEEP association its standing in the international educational and training community and highlights key activities planned for the upcoming period. LA - English DB - MTMT ER - TY - JOUR AU - Pónya, Petra AU - Ding, C. AU - Czifrus, Szabolcs AU - Shwageraus, E. TI - Evaluation of reflector design of ALLEGRO refractory core JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 206 PY - 2024 PG - 13 SN - 0306-4549 DO - 10.1016/j.anucene.2024.110602 UR - https://m2.mtmt.hu/api/publication/35217914 ID - 35217914 N1 - CODEN: ANEND LA - English DB - MTMT ER - TY - JOUR AU - Babcsány, Boglárka AU - Giusti, Valerio AU - Moise, Andreea AU - Mészáros, Péter AU - Czifrus, Szabolcs AU - Chow, Jimmy 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 PG - 19 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 PG - 15 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 AB - This paper presents nuclear reactor transient measurements with thermal feedback and corresponding coupled neutronic–thermohydraulic simulations performed for the natural circulation cooled Training Reactor of Budapest University of Technology and Economics. During the experiments, the outlet temperatures of several fuel assemblies were measured with thermocouples, while the reactor power was simultaneously logged by an ex-core neutron detector. The numerical simulations were carried out with the internally coupled TRACE/Point Kinetics and TRACE/PARCS code systems. The parameterised group constant library of the PARCS neutronic model, as well as the reactivity coefficients of the Point Kinetic model, were generated by the Serpent 2 Monte Carlo code. In the former case, special attention was given to the applied diffusion coefficients. The 3D/1D TRACE calculation model was prepared with the SNAP graphical interface. It was shown that after applying the necessary corrections, related to the peculiar natural circulation flow and reactor parameters, the measurement and both simulation results showed good agreement in terms of peak nominal power and average assembly outlet temperature. Although several anomalies are presented and modelling details that need improvement are highlighted, this study suggests that the used code systems could be appropriate tools to reproduce and analyse transients performed in small-core, high-leakage, natural circulation cooled pool-type reactors. 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 PG - 12 SN - 0306-4549 DO - 10.1016/j.anucene.2023.109839 UR - https://m2.mtmt.hu/api/publication/33748176 ID - 33748176 N1 - Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rkp. 3., Budapest, H-1111, Hungary École Polytechnique Fédérale de Lausanne, Laboratory for Reactor Physics and Systems Behaviour, Lausanne, 1015, Switzerland Paul Scherrer Institut, Nukleare Energie und Sicherheit PSI Villigen 5232, Switzerland Cited By :2 Export Date: 11 June 2024 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 - DATA AU - Czifrus, Szabolcs AU - Bozsó, Tamás Miklós TI - KKÁT Kiszállító épületben betárolandó nem erőművi eredetű kiégett fűtőelemköteg tároló konténer mértékadó műszaki jellemzőinek meghatározása, BME-NTI-985/2022 PY - 2022 UR - https://m2.mtmt.hu/api/publication/34913924 ID - 34913924 LA - Hungarian 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 - DATA AU - Zsolnay, Éva AU - Czifrus, Szabolcs AU - Kis, Dániel Péter AU - Horváth, András TI - REAKTORDOZIMETRIA - Paksi Atomerőmű 2. számú reaktorblokk, reaktortartály felügyeleti pozíció, 8 éven át (28.-34. számú reaktorkampány során) besugárzott neutronmonitorok (UHEP2 Mintafűzér) válaszának kiértékelése, BME-NTI-989/2022 PY - 2022 UR - https://m2.mtmt.hu/api/publication/34913953 ID - 34913953 LA - Hungarian DB - MTMT ER -