@article{MTMT:31668707,
	title = {Solution of the VVER-1000 full core calculation benchmark by the KARATE code system},
	url = {https://m2.mtmt.hu/api/publication/31668707},
	author = {Temesvári, Emese and Hegyi, György and Hordósy, Gábor and Maráczy, Csaba},
	doi = {10.3139/124.200009},
	journal-iso = {KERNTECHNIK},
	journal = {KERNTECHNIK},
	volume = {85},
	unique-id = {31668707},
	issn = {0932-3902},
	year = {2020},
	eissn = {2195-8580},
	pages = {245-249}
}

@inproceedings{MTMT:31178119,
	title = {Solution of the VVER-1000 Full Core Calculation Benchmark by the KARATE Code System},
	url = {https://m2.mtmt.hu/api/publication/31178119},
	author = {Temesvári, Emese and Hegyi, György and Hordósy, Gábor and Maráczy, Csaba},
	booktitle = {Proceedings of the twenty-ninth Symposium of AER},
	unique-id = {31178119},
	year = {2019},
	pages = {77-88}
}

@inproceedings{MTMT:34824606,
	title = {Verification of an indigenous code system for calculation of WER-1200 (AES-2006) reactor},
	url = {https://m2.mtmt.hu/api/publication/34824606},
	author = {Temesvári, Emese and Brolly, Áron Péter and Hegyi, György and Hordósy, Gábor and Maráczy, Csaba},
	booktitle = {Reactor Physics Paving the Way Towards More Efficient Systems: International Conference on Physics of Reactors, PHYSOR 2018},
	volume = {Part F168384-2},
	unique-id = {34824606},
	abstract = {The AES-2006 (VVER-1200) is the new, Generation III Russian reactor, which is planned to be built in Hungary As it is developed from the earlier approved design model, there are several common features between the original and the new designs The main developments are the cycle length which can achieve 500 full power days meanwhile the probability of severe damage to the core for all operating regimes must be less than 10-7 1/yr In fact, reactor core cycle length depends mainly on the arrangement of different fuel assemblies with the type and concentration of poisons and cluster regulating system used inside the core Any improvements in these factors will increase the reactor cycle length and will also increase the average fuel burnup which will finally lead to enhanced economic performance Investigation of core improvements made for the new Russian reactor VVER-1200, has been done by the vendors, however appropriate indigenous calculation tools are advantages for the users, too In Hungary four VVER-440 Units work from the 1980 s As in-core fuel management of these reactors used to be performed by indigenous code system (Karate-440) which was developed in Hungary for VVER reactors about twenty years ago and used continuously, its development seems to be reasonable It was appropriate to create the new code complex Karate-1200 starting from the methods currently used very effectively for VVER-440 reactors This paper briefly summarizes the improvements of the code system and the properties of the possible fuel types can be applied to the AES-2006 reactor The new assemblies are modeled by using both the solvers of the Karate-1200 code system and MCNP respectively (author)},
	year = {2018},
	pages = {1159-1170}
}

@article{MTMT:3315948,
	title = {SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data},
	url = {https://m2.mtmt.hu/api/publication/3315948},
	author = {Michel-Sendis, F and Gauld, I and Martinez, JS and Alejano, C and Bossant, M and Boulanger, D and Cabellos, O and Chrapciak, V and Conde, J and Fast, I and Gren, M and Govers, K and Gysemans, M and Hannstein, V and Havlůj, F and Hennebach, M and Hordósy, Gábor and Ilas, G and Kilger, R and Mills, R and Mountford, D and Ortego, P and Radulescu, G and Rahimi, M and Ranta-Aho, A and Rantamäki, K and Ruprecht, B and Soppera, N and Stuke, M and Suyama, K and Tittelbach, S and Tore, C and Winckel, SV and Vasiliev, A and Watanabe, T and Yamamoto, T and Yamamoto, T},
	doi = {10.1016/j.anucene.2017.07.022},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {110},
	unique-id = {3315948},
	issn = {0306-4549},
	year = {2017},
	eissn = {1873-2100},
	pages = {779-788}
}

@inproceedings{MTMT:3181885,
	title = {Comprehensive solution of teh "MIDICORE" Benchmark by the KARATE and MCNP code system},
	url = {https://m2.mtmt.hu/api/publication/3181885},
	author = {Hegyi, György and Hordósy, Gábor and Keresztúri, András and Maráczy, Csaba and Panka, István and Temesvári, Emese},
	booktitle = {Proceedings of the twenty-sixth Symposium of AER},
	unique-id = {3181885},
	year = {2016},
	pages = {85-96}
}

@article{MTMT:3123338,
	title = {Pressure Vessel Fluence Calculations for the Hungarian VVER-440 Units for the Power Uprate and the Llifetime Extension},
	url = {https://m2.mtmt.hu/api/publication/3123338},
	author = {Hordósy, Gábor and Hegyi, György and Keresztúri, András and Maráczy, Csaba and Temesvári, Emese and Zsolnay, Éva},
	doi = {10.1051/epjconf/201610602011},
	journal-iso = {EPJ WEB CONF},
	journal = {EPJ WEB OF CONFERENCES},
	volume = {106},
	unique-id = {3123338},
	issn = {2101-6275},
	abstract = {A major project was launched at Paks NPP, Hungary, to investigate the possibility of lifetime extension up to 60 years. At the same time, new fuel types with higher enrichment and containing pins with gadolinium have been introduced. Due to these plans, the radiation load of the pressure vessel was evaluated up to 60 years irradiation, taking into account the past and planned future cycles. The computational procedure, elaborated and validated earlier for the fast flux calculation in the pressure vessel was modified for the new fuel types. The neutron source at the core boundaries was taken from core design calculations and the neutron transport from the source to and through the pressure vessel was followed by Monte Carlo calculations. A number of calculations were performed to adequately follow the change of the neutron source. The paper details this procedure, the used Monte Carlo model, the influence of the different reloading schemes on the radiation load and the calculated results.},
	year = {2016},
	eissn = {2100-014X}
}

@article{MTMT:3120735,
	title = {Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP},
	url = {https://m2.mtmt.hu/api/publication/3120735},
	isbn = {9782759819294},
	author = {Zsolnay, Éva and Czifrus, Szabolcs and Fehér, Sándor and Hordósy, Gábor and Keresztúri, András and Kresz, N and Oszvald, F},
	doi = {10.1051/epjconf/201610602010},
	journal-iso = {EPJ WEB CONF},
	journal = {EPJ WEB OF CONFERENCES},
	volume = {106},
	unique-id = {3120735},
	issn = {2101-6275},
	year = {2016},
	eissn = {2100-014X}
}

@inproceedings{MTMT:27188015,
	title = {Evaluation of the Full Core VVER-440 Benchmarks Using the KARATE and MCNP Code Systems},
	url = {https://m2.mtmt.hu/api/publication/27188015},
	author = {Hegyi, György and Hordósy, Gábor and Maráczy, Csaba and Temesvári, Emese},
	booktitle = {24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015)},
	publisher = {Nuclear Society of Slovenia},
	unique-id = {27188015},
	year = {2015}
}

@inproceedings{MTMT:3019809,
	title = {Evaluation of theFullCore VVER-440 BenchmarksUsingthe KARATE and MCNP Code Systems},
	url = {https://m2.mtmt.hu/api/publication/3019809},
	author = {Hegyi, György and Hordósy, Gábor and Maráczy, Csaba and Temesvári, Emese},
	booktitle = {NENE2015 Symposium},
	unique-id = {3019809},
	year = {2015}
}

@inproceedings{MTMT:3019653,
	title = {HPLWR Fine Mesh Core Analysis},
	url = {https://m2.mtmt.hu/api/publication/3019653},
	author = {Temesvári, Emese and Maráczy, Csaba and Hegyi, György and Hordósy, Gábor and Molnár, Attila},
	booktitle = {The 7th International Symposium on Supercritical-Water-Cooled Reactors (ISSCWR-7)},
	unique-id = {3019653},
	year = {2015},
	pages = {141-151}
}