@article{MTMT:34890709,
	title = {Analysis of a PSB-VVER small break LOCA experiment with APROS and TRACE system codes},
	url = {https://m2.mtmt.hu/api/publication/34890709},
	author = {Varju, Tamás and Orosz, Róbert and Kardos, Boldizsár and Biró, Bence and Aszódi, Attila},
	doi = {10.1016/j.anucene.2024.110662},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {206},
	unique-id = {34890709},
	issn = {0306-4549},
	year = {2024},
	eissn = {1873-2100},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}

@techreport{MTMT:34865770,
	title = {RELAP5, TRACE and APROS Model Benchmark for the IAEA SPE-2 Experiment},
	url = {https://m2.mtmt.hu/api/publication/34865770},
	author = {Orosz, Róbert and Varju, Tamás and Aranyosy, Ádám and Holl, Viktor and Hajas, Tamás Zoltán and Aszódi, Attila},
	unique-id = {34865770},
	year = {2024},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}

@article{MTMT:34735228,
	title = {Discussion and perspectives for improvements of heat transfer correlation capabilities for fluids at supercritical pressures},
	url = {https://m2.mtmt.hu/api/publication/34735228},
	author = {Varju, Tamás and Csige, András and Kiss, Attila and Filonov, V. and Filonova, Y. and Fedorov, D. and Pucciarelli, A. and Kassem, S. and Ambrosini, W.},
	doi = {10.1016/j.nucengdes.2024.113085},
	journal-iso = {NUCL ENG DES},
	journal = {NUCLEAR ENGINEERING AND DESIGN},
	volume = {421},
	unique-id = {34735228},
	issn = {0029-5493},
	year = {2024},
	eissn = {1872-759X},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867; Kiss, Attila/0000-0002-8600-2300}
}

@techreport{MTMT:33141001,
	title = {RELAP5, TRACE and APROS Model Benchmark for the IAEA SPE-4 Experiment},
	url = {https://m2.mtmt.hu/api/publication/33141001},
	author = {Orosz, Róbert and Varju, Tamás and Aranyosy, Ádám and V., Holl and Hajas, Tamás Zoltán and Aszódi, Attila},
	unique-id = {33141001},
	year = {2022},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}

@article{MTMT:32683975,
	title = {Sensitivity analysis of the IAEA SPE-2 small-break LOCA experiment with RELAP5, TRACE and APROS system codes},
	url = {https://m2.mtmt.hu/api/publication/32683975},
	author = {Varju, Tamás and Orosz, Róbert and Aranyosy, Ádám and Holl, Viktor and Hajas, Tamás Zoltán and Aszódi, Attila},
	doi = {10.1016/j.nucengdes.2021.111630},
	journal-iso = {NUCL ENG DES},
	journal = {NUCLEAR ENGINEERING AND DESIGN},
	volume = {388},
	unique-id = {32683975},
	issn = {0029-5493},
	abstract = {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).},
	year = {2022},
	eissn = {1872-759X},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}

@{MTMT:34912884,
	title = {A VVER-1200 3+ generációs blokkokkal kapcsolatban a BME NTI-nél végzett tudományos munka és egyes nemzetközi felülvizsgálatok megállapításai alapján összeállított tipikus és lehetséges eltérések helyzetének vizsgálata a létesítési-engedélykérelem részeként benyújtott EBJ-ben és az azt megalapozó dokumentációban, BME-NTI-953/2021},
	url = {https://m2.mtmt.hu/api/publication/34912884},
	author = {Czifrus, Szabolcs and Aszódi, Attila and Boros, Ildikó and Csige, András and Kiss, Béla and Szalóki, Imre and Szieberth, Máté and Varju, Tamás},
	unique-id = {34912884},
	year = {2021},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352; Varju, Tamás/0000-0002-2969-1867}
}

@article{MTMT:31936687,
	title = {Analysis of the IAEA SPE-4 small-break LOCA experiment with RELAP5, TRACE and APROS system codes},
	url = {https://m2.mtmt.hu/api/publication/31936687},
	author = {Varju, Tamás and Aranyosy, Ádám and Orosz, Róbert and Holl, Viktor and Hajas, Tamás Zoltán and Aszódi, Attila},
	doi = {10.1016/j.nucengdes.2021.111109},
	journal-iso = {NUCL ENG DES},
	journal = {NUCLEAR ENGINEERING AND DESIGN},
	volume = {377},
	unique-id = {31936687},
	issn = {0029-5493},
	year = {2021},
	eissn = {1872-759X},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867; Aranyosy, Ádám/0000-0002-6699-8219; Aszódi, Attila/0000-0002-4618-1076}
}

@inproceedings{MTMT:31618839,
	title = {Development of nuclear power plant basic principle simulators as tools for nuclear engineering education},
	url = {https://m2.mtmt.hu/api/publication/31618839},
	author = {Fehér, Sándor and Czifrus, Szabolcs and Lőrincz, J. and Varju, Tamás and Aszódi, Attila and Csom, Gyula},
	booktitle = {Varietas delectat... Complexity is the new normality},
	unique-id = {31618839},
	abstract = {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.},
	keywords = {Nuclear power plants; Nuclear energy; Graphical user interfaces; Simulators; Distance education; Nuclear fuels; Engineering education; Simulation model; circuit simulation; Thermal hydraulics; Thermal hydraulics; Reactor physics; Reactor physics; Primary circuits; Nuclear power plant simulator; Primary circuit; Distant learning; Power plant simulator; Secondary circuit; Training experiences},
	year = {2020},
	pages = {380-389},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}

@article{MTMT:31938146,
	title = {Estimation of velocity fields from the axial wire-mesh sensor data},
	url = {https://m2.mtmt.hu/api/publication/31938146},
	author = {Telkkä, Joonas and Ylönen, Arto and Hyvärinen, Juhani and Varju, Tamás},
	doi = {10.1016/j.nucengdes.2017.05.010},
	journal-iso = {NUCL ENG DES},
	journal = {NUCLEAR ENGINEERING AND DESIGN},
	volume = {336},
	unique-id = {31938146},
	issn = {0029-5493},
	year = {2018},
	eissn = {1872-759X},
	pages = {34-44},
	orcid-numbers = {Varju, Tamás/0000-0002-2969-1867}
}