@article{MTMT:34568144, title = {PIV measurements for VVER pressurized water reactor rod bundle geometries including spacer grids for CFD model validations}, url = {https://m2.mtmt.hu/api/publication/34568144}, author = {Orosz, Gergely Imre and Kacz, Dániel and Magyar, Boglárka and Aszódi, Attila}, doi = {10.1016/j.nucengdes.2024.112938}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {419}, unique-id = {34568144}, issn = {0029-5493}, abstract = {A PIV (Particle Image Velocimetry) test facility called PIROUETTE (PIv ROd bUndlE Test faciliTy at bmE) has been built at BME (Budapest University of Technology and Economics) NTI (Institute of Nuclear Techniques). The facility is capable of investigating of flow processes under isothermal conditions with different type triangular lattice seven-rod bundles. The currently investigated rod bundle is featuring spacer grids and hydraulic conditions related to the VVER-1000 and VVER-1200 fuel assemblies. This small bundle of 7 rods is a geometrically accurate representation of a piece of the real reactor's fuel bundle, including the spacer grids. These spacer grids were 3D printed from a special type of plastic for the PIV experiments in order to reproduce the real geometry inside the assemblies as accurately as possible. The effect of the spacer grids with vanes (which are located on the spacer grid belt section) was investigated using different test grid configurations. The measurements aimed to capture high resolution flow fields inside the rod bundle with MIR (Matching Index of Refraction), in order to enable the flow measurements even within the bundle, where usually the flow field is not visible. For this purpose, the geometry was manufactured using special transparent materials. The detailed, high resolution experimental data could be used for CFD (Computational Fluid Dynamics) benchmarking and code validation, and therefore can serve the further safe and reliable operation of these reactors. The results include velocity field, velocity standard deviations (RMS), Reynolds stress and turbulent kinetic energy distributions extracted from the measured data. The attachments include the 3D model of the experimental geometry, measured velocity distributions and other parameters along various monitor lines. © 2024 The Author(s)}, keywords = {KINETICS; IMAGE VELOCIMETRY; GEOMETRY; Refractive index; Reynolds number; Kinetic energy; Computational fluid dynamics; flow visualization; Pressurized water reactors; Velocity measurement; particle image velocimetry; particle image velocimetry; Flow fields; Velocity distribution; Test facilities; 3D printing; Fuel assembly; Fuel assembly; Velocimeters; index of refraction; Matching index; CFD modell validation; Matching index of refraction; PIROUETTE system; VVER-1200 reactor; Computational fluid dynamic modell validation; Matching index of refraction; Particle images; PIROUETTE system; VVER-1200 reactor}, year = {2024}, eissn = {1872-759X}, orcid-numbers = {Kacz, Dániel/0000-0002-6217-0481} } @mastersthesis{MTMT:34080273, title = {Investigations of thermal hydraulics of ALLEGRO fuel assemblies}, url = {https://m2.mtmt.hu/api/publication/34080273}, author = {Orosz, Gergely Imre}, publisher = {Budapest University of Technology and Economics}, unique-id = {34080273}, year = {2023} } @article{MTMT:33330202, title = {ALLEGRO Gas cooled Fast Reactor Rod Bundle investigations with CFD and PIV method}, url = {https://m2.mtmt.hu/api/publication/33330202}, author = {Orosz, Gergely Imre and Magyar, Boglárka and Szerbák, D. and Kacz, Dániel and Aszódi, Attila}, doi = {10.1016/j.nucengdes.2022.112062}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {400}, unique-id = {33330202}, issn = {0029-5493}, year = {2022}, eissn = {1872-759X}, orcid-numbers = {Kacz, Dániel/0000-0002-6217-0481} } @{MTMT:32736622, title = {Preliminary Thesis on the First Part of the ALLEGRO CFD Benchmark Exercise. ALLEGRO CFD BENCHMARK: PART 1: Flow Straightener Benchmark Description}, url = {https://m2.mtmt.hu/api/publication/32736622}, author = {Orosz, Gergely Imre and Mathias, Peireti and Magyar, Boglárka and Szerbák, Dániel and Kacz, Dániel and Kiss, Béla and Zsíros, Gábor and Aszódi, Attila}, unique-id = {32736622}, year = {2022}, orcid-numbers = {Kacz, Dániel/0000-0002-6217-0481} } @article{MTMT:32156575, title = {CFD modelling of mixing vane spacer grids for ALLEGRO relevant gas cooled reactor fuel geometry}, url = {https://m2.mtmt.hu/api/publication/32156575}, author = {Orosz, Gergely Imre and Aszódi, Attila}, doi = {10.1016/j.anucene.2021.108628}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {164}, unique-id = {32156575}, issn = {0306-4549}, year = {2021}, eissn = {1873-2100} } @article{MTMT:31911673, title = {Detailed thermal modelling of the ALLEGRO ceramic assembly}, url = {https://m2.mtmt.hu/api/publication/31911673}, author = {Orosz, Gergely Imre and Tóth, Sándor and Aszódi, Attila}, doi = {10.1016/j.nucengdes.2021.111127}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {376}, unique-id = {31911673}, issn = {0029-5493}, year = {2021}, eissn = {1872-759X} } @article{MTMT:31707649, title = {Simulations for L-STAR experimental gas-cooled system}, url = {https://m2.mtmt.hu/api/publication/31707649}, author = {Orosz, Gergely Imre and Tóth, Sándor and Aszódi, Attila}, doi = {10.3139/124.200017}, journal-iso = {KERNTECHNIK}, journal = {KERNTECHNIK}, volume = {85}, unique-id = {31707649}, issn = {0932-3902}, abstract = {Turbulent heat transfer through gas-cooled systems is a key factor for the improvements of the gas-cooled fast reactors. Within the FP7 European projects GoFastR (European Gas Cooled Fast Reactor) [1] and THINS (Thermal-hydraulics of Innovative Nuclear Systems) [2], numerical tools for the simulation of the thermal-hydraulics of next generation reactor systems were developed, applied and validated for innovative coolants. One of their objects was the L-STAR (Luft - STab, Abstandshalter, Rauheiten) facility, which has been designed and erected at the Karlsruhe Institute of Technology to study turbulent flow behaviour and its heat transfer enhancement characteristics in gas-cooled annular channels under a wide range of conditions. The test section consists of a hexagonal cross-section channel with an inner electrical rod heater placed coaxially. This design represents the flow domain around a single fuel rod in a future GFR. In this paper experimental results of the fluid flow with uniform heat release conditions for the smooth heater rod are considered. Design of the facility allows using various values of heating power and fluid mass flow rates depending on the chosen scenario. The purpose of this study is to create CFD models for the L-STAR facility, which are capable of reproducing the results of reference measurements. The other aim is to find an applicable turbulence model for the GFR relevant cases. Steady-state simulations are performed for selected cases. We also present mesh, structural element and turbulence model sensitivity studies during this work. With these model results it becomes possible to validate our CFD models to be applicable for the ALLEGRO gas-cooled reactor fuel assemblies.}, year = {2020}, eissn = {2195-8580}, pages = {326-335} } @inbook{MTMT:30973684, title = {CFD CALCULATIONS FOR L-STAR EXPERIMENTAL GAS COOLED SYSTEM}, url = {https://m2.mtmt.hu/api/publication/30973684}, author = {Orosz, Gergely Imre and Tóth, Sándor and Aszódi, Attila}, booktitle = {Proceedings of the twenty-ninth Symposium of AER}, unique-id = {30973684}, abstract = {Turbulent heat transfer through gas cooled systems is a key factor for the improvements of the Gas cooled Fast Reactors (GFR). Within the FP7 European project THINS (Thermal Hydraulics of Innovative Nuclear Systems), experimental and numerical tools for investigations of the thermal hydraulics of next generation rector systems were developed, applied and validated for innovative coolants. One of the tools is the L-STAR facility, which has been designed and erected at the Karlsruhe Institute of Technology (KIT) to study turbulent flow behaviour and heat transfer enhancement characteristics in gas cooled annular channels under a wide range of conditions. The test section consists of an annular hexagonal cross section channel with an inner electrical heater rod element, placed concentrically within the test section. This design represents the flow domain around a single fuel rod in a future GFR. In this paper simulation results for the fluid flow at uniform heat release conditions for the smooth heater rod are presented. Application of the facility allows using various values of heating power of the heated rod and fluid mass flow depending on the chosen scenario. The purpose of this study is to create CFD (Computational Fluid Dynamics) models for the L-STAR that are capable of reproducing the results of reference measurements. The calculations were carried out with ANSYS CFX 17 code. All simulations were performed as steady-state calculations. Mesh, structural element and turbulence model sensitivity studies were also performed during this work. With these model results it becomes possible to validate other CFD models to be applied for the ALLEGRO experimental gas cooled reactor fuel assemblies.}, year = {2019}, pages = {465-476} } @article{MTMT:33802982, title = {Az ALLEGRO kerámia kazetta hőmérséklet-eloszlásának egyenletesebbé tétele}, url = {https://m2.mtmt.hu/api/publication/33802982}, author = {Orosz, Gergely Imre and Tóth, Sándor}, journal-iso = {NUKLEON}, journal = {NUKLEON}, volume = {11}, unique-id = {33802982}, issn = {1789-9613}, year = {2018}, pages = {1-4} } @article{MTMT:3393070, title = {Thermal hydraulic investigations of ALLEGRO ceramic fuel assemblies}, url = {https://m2.mtmt.hu/api/publication/3393070}, author = {Orosz, Gergely Imre and Tóth, Sándor}, doi = {10.1016/j.anucene.2018.06.006}, journal-iso = {ANN NUCL ENERGY}, journal = {ANNALS OF NUCLEAR ENERGY}, volume = {120}, unique-id = {3393070}, issn = {0306-4549}, year = {2018}, eissn = {1873-2100}, pages = {570-580} }