TY - JOUR AU - Varju, Tamás AU - Csige, András AU - Kiss, Attila AU - Filonov, V. AU - Filonova, Y. AU - Fedorov, D. AU - Pucciarelli, A. AU - Kassem, S. AU - Ambrosini, W. TI - Discussion and perspectives for improvements of heat transfer correlation capabilities for fluids at supercritical pressures JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 421 PY - 2024 PG - 23 SN - 0029-5493 DO - 10.1016/j.nucengdes.2024.113085 UR - https://m2.mtmt.hu/api/publication/34735228 ID - 34735228 N1 - Budapest University of Technology and Economics, Hungary IPP-Centre LLC, Ukraine Università di Pisa, Italy Export Date: 22 March 2024 CODEN: NEDEA Correspondence Address: Pucciarelli, A.; Università di PisaItaly; email: andrea.pucciarelli@unipi.it Funding details: Xi'an Eurasia University, EU Funding details: H2020 Euratom, 945234 Funding text 1: The work presented in this paper was performed in the frame of the EU ECC-SMART project (Joint European Canadian Chinese Development of Small Modular Reactor Technology). This project received funding from the Euratom research and training programme 2019–2020 under grant agreement no. 945234. LA - English DB - MTMT ER - TY - GEN AU - Orosz, Róbert AU - Varju, Tamás AU - Aranyosy, Ádám AU - V., Holl AU - Hajas, Tamás Zoltán AU - Aszódi, Attila TI - RELAP5, TRACE and APROS Model Benchmark for the IAEA SPE-4 Experiment PY - 2022 PG - 188 UR - https://m2.mtmt.hu/api/publication/33141001 ID - 33141001 LA - English DB - MTMT ER - TY - JOUR AU - Varju, Tamás AU - Orosz, Róbert AU - Aranyosy, Ádám AU - Holl, Viktor AU - Hajas, Tamás Zoltán AU - Aszódi, Attila TI - Sensitivity analysis of the IAEA SPE-2 small-break LOCA experiment with RELAP5, TRACE and APROS system codes JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 388 PY - 2022 PG - 21 SN - 0029-5493 DO - 10.1016/j.nucengdes.2021.111630 UR - https://m2.mtmt.hu/api/publication/32683975 ID - 32683975 N1 - Funding Agency and Grant Number: Ministry of Innovation and Technology of Hungary from the National Research, Development and Innovation Fund; Paks II; [BME-NVA-02] Funding text: The research reported in this paper is part of project no. BME-NVA-02, implemented with the support provided by the Ministry of Innovation and Technology of Hungary from the National Research, Development and Innovation Fund, financed under the TKP2021 funding scheme. Furthermore, the first part of the previous SPE-4 model development was carried out in the framework of a research project supported by Paks II. Nuclear Power Plant Ltd. and MVM ERBE. The authors want to thank J ' ozsef B ' an ' ati and R ' obert D ' aniel R ' adi for their valuable comments and proposals made during the development of the RELAP5 model. AB - The Hungarian PMK-2 test facility is a scaled-down model of the VVER-440/213 type pressurized water reactors of Paks NPP, on which several measurement series have been carried out since the 80s. One of these series include four Standard Problem Exercises (SPE), primarily small-break loss-of coolant accident (SBLOCA) transients, performed in cooperation with IAEA. New RELAP5, TRACE and APROS models have already been developed and a comparative analysis of the results has been published recently for the PMK SPE-4 experiment. In that SBLOCA scenario, no high-pressure injection system (HPIS) was available, but a secondary side bleed and feed operation has been performed during the transient. This paper is a continuation of the previous one and presents the required model modifications and the analysis of the second SPE. The initiating event, similarly to the SPE-4 experiment, is a 7.4% break located at the top of the downcomer, while the main differences are that one line of the HPIS is available and no secondary side feed and bleed operation is performed in this case. One of the main objectives of the experiment was to verify that these safety measures are enough to prevent core dry-out. In addition to the investigation of this question, a sensitivity study was also carried out with respect to selected parameters that might have a significant impact on the characteristic of the simulated processes. The assessment of the results has also been performed with two quantitative methods, namely the Fast Fourier Transform Based Method with Signal Mirroring (FFTBM-SM) and Stochastic Approximation Ratio Based Method (SARBM). LA - English DB - MTMT ER - TY - JOUR AU - Varju, Tamás AU - Aranyosy, Ádám AU - Orosz, Róbert AU - Holl, Viktor AU - Hajas, Tamás Zoltán AU - Aszódi, Attila TI - Analysis of the IAEA SPE-4 small-break LOCA experiment with RELAP5, TRACE and APROS system codes JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 377 PY - 2021 SN - 0029-5493 DO - 10.1016/j.nucengdes.2021.111109 UR - https://m2.mtmt.hu/api/publication/31936687 ID - 31936687 LA - English DB - MTMT ER - TY - CHAP AU - Fehér, Sándor AU - Czifrus, Szabolcs AU - Lőrincz, J. AU - Varju, Tamás AU - Aszódi, Attila AU - Csom, Gyula ED - Nagy, Balázs Vince ED - Murphy, Mike ED - Jarvinen, Hannu-Matti ED - Kálmán, Anikó TI - Development of nuclear power plant basic principle simulators as tools for nuclear engineering education T2 - Varietas delectat... Complexity is the new normality PB - European Society for Engineering Education (SEFI) CY - Brüsszel SN - 9782873520182 PY - 2020 SP - 380 EP - 389 PG - 10 UR - https://m2.mtmt.hu/api/publication/31618839 ID - 31618839 N1 - Export Date: 5 October 2020 Funding text 1: A plan for the renewal asw developed about a decade ago. Nevertheless, the actual ow rk aw s only started at the end of 5201 in frame of the Nati onal Nuclear Research Programme supported by the National Fund for Innovation and Development. The reneaw l is practi cally equivalent to fully replanning and recoding the program. AB - Our Institute has been developing PC-based nuclear power plant (NPP) basic principle simulators for over 30 years. The main goal of this development is to provide the nuclear engineering education at the university with tools capable to illustrate the fundamental physical processes going on in the primary and secondary circuit of an NPP. The simulators were integrated into our training courses in the last three decades. The firstly developed primary circuit basic principle simulator, PC2 is still the most often and most widespread used one despite the fact that it was written for old DOS operating system and thus nowadays is of restricted applicability. Therefore, the development of a new PC2+ simulator started in 2016 based on the training experience accumulated and with support of a national research grant. Its scope of simulation is practically the same as that of the old PC2 but it has various model extensions and new features. The graphical user interface (visualization/interaction) program module and the simulation model computing module are two separate programs (executable codes) which may run on a single or on two different computers as well. This feature of PC2+ allows for using it via internet and opens new possibilities both in classroom exercises and distant learning. © 2020 SEFI 47th Annual Conference: Varietas Delectat... Complexity is the New Normality, Proceedings. All rights reserved. LA - English DB - MTMT ER - TY - JOUR AU - Telkkä, Joonas AU - Ylönen, Arto AU - Hyvärinen, Juhani AU - Varju, Tamás TI - Estimation of velocity fields from the axial wire-mesh sensor data JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 336 PY - 2018 SP - 34 EP - 44 PG - 11 SN - 0029-5493 DO - 10.1016/j.nucengdes.2017.05.010 UR - https://m2.mtmt.hu/api/publication/31938146 ID - 31938146 LA - English DB - MTMT ER -