@article{MTMT:32901980,
	title = {Impact of fresh fuel loading management in fuel cycle simulators: A functionality isolation test},
	url = {https://m2.mtmt.hu/api/publication/32901980},
	author = {Thiolliere, N. and Doligez, X. and Halász, Máté Gergely and Krivtchik, G. and Merino, I and Mouginot, B. and Skarbeli, A. V and Hernandez-Solis, A. and Alvarez-Velarde, F. and Courtin, F. and Druenne, H. and Ernoult, M. and Huff, K. and Szieberth, Máté and Vermeeren, B. and Wilson, P.},
	doi = {10.1016/j.nucengdes.2022.111748},
	journal-iso = {NUCL ENG DES},
	journal = {NUCLEAR ENGINEERING AND DESIGN},
	volume = {392},
	unique-id = {32901980},
	issn = {0029-5493},
	abstract = {Fuel cycle simulator development started many years ago by several research and engineering institutions or consulting firms for a wide range of applications. To improve confidence in the results, institutions may be tempted to increase the complexity of their software even if this complexity might not be necessary. On the other hand, some simulators may be used outside their range of validity when used in very specific applications. The FIT (Functionality Isolation Test) project is an international effort devoted to improve the confidence in the data produced by fuel cycle simulation tools. The scientific goal is to determine the optimum level of detail a fuel cycle simulator needs according to the type of study and the required confidence level. The project relies on a wide variety of fuel cycle simulators with a large range of complexity levels. The FIT project consists of isolating the impact of one targeted functionality on fuel cycle simulations. The impact of the functionality is assessed using a set of simple basic exercises specifically designed for this purpose, called "functionality isolation. " The present work focuses on the impact on simulation results of using a fuel loading model (a relation that links the stock isotopic composition with the fresh fuel fabrication according to the reactor requirements) or a fixed fraction approach (the fresh fuel fissile fraction is fixed and does not depend on the stock isotopic composition). The paper first presents the FIT project. The exercise design is described and results show that using a fuel loading model approach has an important impact on fuel cycle outputs under certain conditions that are described. This result is reinforced by the fact that all fuel cycle simulators used in this exercise provide similar conclusions.},
	keywords = {Pressurized water reactors; scenario; Sodium fast reactors; Fuel Cycle Simulators; Fuel Loading Models},
	year = {2022},
	eissn = {1872-759X},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@article{MTMT:31598114,
	title = {Population-based variance reduction for dynamic Monte Carlo},
	url = {https://m2.mtmt.hu/api/publication/31598114},
	author = {Légrády, Dávid and Halász, Máté Gergely and Kópházi, József and Molnár, Balázs and Tolnai, Gábor},
	doi = {10.1016/j.anucene.2020.107752},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {149},
	unique-id = {31598114},
	issn = {0306-4549},
	year = {2020},
	eissn = {1873-2100},
	orcid-numbers = {Molnár, Balázs/0000-0003-0029-3176}
}

@article{MTMT:31320569,
	title = {Negyedik generációs reaktorokat tartalmazó üzemanyagciklusok vizsgálata},
	url = {https://m2.mtmt.hu/api/publication/31320569},
	author = {Halász, Máté Gergely and Szieberth, Máté},
	journal-iso = {NUKLEON},
	journal = {NUKLEON},
	volume = {13},
	unique-id = {31320569},
	issn = {1789-9613},
	year = {2020},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@inproceedings{MTMT:32796964,
	title = {Fuel cycle studies of Generation IV reactors with the SITON v2.0 code and the FITXS burn-up scheme},
	url = {https://m2.mtmt.hu/api/publication/32796964},
	author = {Halász, Máté Gergely and Brolly, Áron Péter and Szieberth, Máté and Fehér, Sándor},
	booktitle = {Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)},
	unique-id = {32796964},
	year = {2018},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@mastersthesis{MTMT:31345585,
	title = {Development of a fast burn-up method and investigation of transmutation in Generation IV fast reactors},
	url = {https://m2.mtmt.hu/api/publication/31345585},
	author = {Halász, Máté Gergely},
	publisher = {Budapest University of Technology and Economics},
	unique-id = {31345585},
	year = {2018}
}

@article{MTMT:3423382,
	title = {Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors},
	url = {https://m2.mtmt.hu/api/publication/3423382},
	author = {Halász, Máté Gergely and Szieberth, Máté},
	doi = {10.3139/124.110906},
	journal-iso = {KERNTECHNIK},
	journal = {KERNTECHNIK},
	volume = {83},
	unique-id = {3423382},
	issn = {0932-3902},
	year = {2018},
	eissn = {2195-8580},
	pages = {319-324},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@article{MTMT:3406217,
	title = {Markov chain models of nuclear transmutation: Part I – Theory},
	url = {https://m2.mtmt.hu/api/publication/3406217},
	author = {Halász, Máté Gergely and Szieberth, Máté},
	doi = {10.1016/j.anucene.2018.07.010},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {121},
	unique-id = {3406217},
	issn = {0306-4549},
	year = {2018},
	eissn = {1873-2100},
	pages = {429-445},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@article{MTMT:3314742,
	title = {Determination of Zr-93 in nuclear power plant wastes},
	url = {https://m2.mtmt.hu/api/publication/3314742},
	author = {Osváth, Szabolcs and Vajda, Nóra and Molnar, Z and Kovács-Széles, Éva and Braun, Mihály and Halász, Máté Gergely},
	doi = {10.1007/s10967-017-5382-z},
	journal-iso = {J RADIOANAL NUCL CHEM},
	journal = {JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY},
	volume = {314},
	unique-id = {3314742},
	issn = {0236-5731},
	year = {2017},
	eissn = {1588-2780},
	pages = {31-38},
	orcid-numbers = {Osváth, Szabolcs/0000-0002-5241-5895}
}

@article{MTMT:3201111,
	title = {FITXS: A fast and flexible burn-up scheme based on the fitting of one-group cross-sections},
	url = {https://m2.mtmt.hu/api/publication/3201111},
	author = {Halász, Máté Gergely and Szieberth, Máté and Fehér, Sándor},
	doi = {10.1016/j.anucene.2017.02.010},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {104},
	unique-id = {3201111},
	issn = {0306-4549},
	keywords = {Breeding; Fuel cycle; transmutation; Gas-cooled Fast Reactor; Burn-up; Cross-section parametrization},
	year = {2017},
	eissn = {1873-2100},
	pages = {267-281},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@article{MTMT:3134362,
	title = {Physical model of the nuclear fuel cycle simulation code SITON},
	url = {https://m2.mtmt.hu/api/publication/3134362},
	author = {Brolly, Áron Péter and Halász, Máté Gergely and Szieberth, Máté and Nagy, L and Fehér, Sándor},
	doi = {10.1016/j.anucene.2016.10.001},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {99},
	unique-id = {3134362},
	issn = {0306-4549},
	year = {2017},
	eissn = {1873-2100},
	pages = {471-483},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}