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 - Böröczki, Zoltán István AU - Babcsány, Boglárka AU - Maróti, János Endre AU - Szieberth, Máté TI - On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Higher-Order Transport Calculations JF - NUCLEAR SCIENCE AND ENGINEERING J2 - NUCL SCI ENG VL - 197 PY - 2023 IS - 8 SP - 1545 EP - 1563 PG - 19 SN - 0029-5639 DO - 10.1080/00295639.2023.2167469 UR - https://m2.mtmt.hu/api/publication/33723519 ID - 33723519 LA - English DB - MTMT ER - TY - CONF AU - Babcsány, Boglárka AU - Giusti, Valerio AU - Moise, Andreea AU - Chow, J.C. TI - Comparative Analysis of Energy Deposition Modes Available in Serpent 2 Within the Framework of the Supercritical Water Reactor - Fuel Qualification Test Reactor Physics Benchmark T2 - International Conference on Physics of Reactors 2022 (PHYSOR 2022) PB - American Nuclear Society (ANS) C1 - Pittsburgh (PA) PY - 2022 SP - 2102 EP - 2111 PG - 10 UR - https://m2.mtmt.hu/api/publication/32909817 ID - 32909817 LA - English DB - MTMT ER - TY - CONF AU - Babcsány, Boglárka AU - Böröczki, Zoltán István AU - Maróti, János Endre AU - Szieberth, Máté TI - On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Few-Group Transport Calculations T2 - International Conference on Physics of Reactors 2022 (PHYSOR 2022) PB - American Nuclear Society (ANS) C1 - Pittsburgh (PA) PY - 2022 SP - 254 EP - 263 PG - 10 UR - https://m2.mtmt.hu/api/publication/32909803 ID - 32909803 LA - English DB - MTMT ER - TY - JOUR AU - Babcsány, Boglárka AU - Pós, István AU - Böröczki, Zoltán István AU - Kis, Dániel Péter TI - Hybrid finite-element-based numerical solution of the SP3 equations – SP3 solution of two- and three-dimensional VVER reactor problems JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 173 PY - 2022 PG - 19 SN - 0306-4549 DO - 10.1016/j.anucene.2022.109117 UR - https://m2.mtmt.hu/api/publication/32788841 ID - 32788841 N1 - Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rakpart 9., Budapest, 1111, Hungary Reactor Physics Department, Paks Nuclear Power Plant, P.O. Box 71., Paks, 7030, Hungary Export Date: 19 May 2022 CODEN: ANEND Correspondence Address: Babcsány, B.; Institute of Nuclear Techniques, Műegyetem rakpart 9., Hungary; email: boglarka.babcsany@reak.bme.hu AB - As a follow-up to the paper previously published by the authors detailing the hybrid finite element (HYBFEM) solution of the SP3 equations, in this paper, besides a semi-analytical solver verification with an analysis on the applied source fitting polynomial order, three-dimensional VVER-440, and VVER-1000 benchmarks are reproduced with the continuous Galerkin (CGFEM) and HYBFEM SP3 modules of the SPNDYN code. The effect of the applied axial nodalisation and radial element order on the calculation results is discussed. The HYBFEM solver extended with a discontinuity factor (DCF) calculation module based on Serpent 2 output parameters is verified on a two-dimensional VVER-1000 benchmark. The SPNDYN CGFEM and HYBFEM results show very good agreement. We also verify that by introducing DCFs in SP3 calculations, the reference transport solution can be reproduced with high accuracy. We highlight the effect of using scalar flux weighted linearly anisotropic scattering matrices in higher-order transport calculations. LA - English DB - MTMT ER - TY - THES AU - Babcsány, Boglárka TI - Development of a finite-element-based reactor physics code system for the solution of the simplified P3 approximation to the neutron transport equation PB - Budapesti Műszaki és Gazdaságtudományi Egyetem PY - 2022 SP - 177 UR - https://m2.mtmt.hu/api/publication/32707657 ID - 32707657 LA - English DB - MTMT ER - TY - JOUR AU - Aszódi, Attila AU - Babcsány, Boglárka TI - A telephelyvizsgálat a nukleáris biztonság szolgálatában JF - MAGYAR TUDOMÁNY J2 - MAGYAR TUDOMÁNY VL - 182 PY - 2021 IS - 7 SP - 865 EP - 883 PG - 19 SN - 0025-0325 DO - 10.1556/2065.182.2021.7.2 UR - https://m2.mtmt.hu/api/publication/32120420 ID - 32120420 LA - Hungarian 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 - Babcsány, Boglárka AU - Pós, István AU - Kis, Dániel Péter TI - Hybrid finite-element-based numerical solution of the multi-group SP3 equations and its application on hexagonal reactor problems JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 155 PY - 2021 PG - 13 SN - 0306-4549 DO - 10.1016/j.anucene.2021.108148 UR - https://m2.mtmt.hu/api/publication/31852673 ID - 31852673 N1 - Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rakpart 9., Budapest, 1111, Hungary Reactor Physics Department, Paks Nuclear Power Plant, P.O. Box 71., Paks, 7030, Hungary Cited By :2 Export Date: 16 June 2022 CODEN: ANEND Correspondence Address: Babcsány, B.; Institute of Nuclear Techniques, Műegyetem rakpart 9., Hungary; email: boglarka.babcsany@reak.bme.hu Funding details: Nemzeti Kutatási Fejlesztési és Innovációs Hivatal, NKFIH Funding text 1: The research reported in this paper and carried out at the Budapest University of Technology and Economics was supported by the “TKP2020, National Challenges Program” of the National Research Development and Innovation Office (BME NC TKP2020). Ms. B. Babcsány would like to thank the Reactor Physics Department of the Paks Nuclear Power Plant for their continuous support. Finally, the authors would like to acknowledge the reviewers for their in-depth work and valuable suggestions. AB - The C-PORCA reactor physics code of the Paks Nuclear Power Plant performs three-dimensional, two-group diffusion calculations applying parametrized group constants generated by the HELIOS code. To improve the accuracy of the calculations, the C-PORCA code was extended with a simplified spherical harmonics module. This paper presents the applied finite-element-based solution algorithm of the SP3 equations in response matrix formalism. Radially primal mixed-hybrid finite element method is used for response matrix calculation with the inclusion of Lagrange multipliers to enforce nodal balance on each element. The axial solution is analytically performed connecting the axial and radial directions through radial leakage with transverse integration. Coupling between the adjacent volumetric elements is performed with node-to-node axial and radial partial current-like moment iterations, that enables the application of SP3 discontinuity factors and the parallelization of the calculation process. The accuracy of the SP3 solution algorithm is demonstrated on academic benchmark and VVER-440 core calculations. LA - English DB - MTMT ER - TY - JOUR AU - Babcsány, Boglárka AU - Bartók, T. AU - Kis, Dániel Péter TI - Finite element solution of the time-dependent SP 3 equations using an implicit integration scheme JF - KERNTECHNIK J2 - KERNTECHNIK VL - 85 PY - 2020 IS - 4 SP - 292 EP - 300 PG - 9 SN - 0932-3902 DO - 10.3139/124.200004 UR - https://m2.mtmt.hu/api/publication/31615584 ID - 31615584 LA - English DB - MTMT ER -