TY - JOUR AU - Temesvári, Emese AU - Hegyi, György AU - Hordósy, Gábor AU - Maráczy, Csaba TI - Solution of the VVER-1000 full core calculation benchmark by the KARATE code system JF - KERNTECHNIK J2 - KERNTECHNIK VL - 85 PY - 2020 IS - 4 SP - 245 EP - 249 PG - 5 SN - 0932-3902 DO - 10.3139/124.200009 UR - https://m2.mtmt.hu/api/publication/31668707 ID - 31668707 LA - English DB - MTMT ER - TY - CHAP AU - Temesvári, Emese AU - Hegyi, György AU - Hordósy, Gábor AU - Maráczy, Csaba ED - Anon, A TI - Solution of the VVER-1000 Full Core Calculation Benchmark by the KARATE Code System T2 - Proceedings of the twenty-ninth Symposium of AER PB - Energiatudományi Kutatóközpont CY - Budapest SN - 9789637351327 PY - 2019 SP - 77 EP - 88 PG - 12 UR - https://m2.mtmt.hu/api/publication/31178119 ID - 31178119 LA - English DB - MTMT ER - TY - CHAP AU - Temesvári, Emese AU - Brolly, Áron Péter AU - Hegyi, György AU - Hordósy, Gábor AU - Maráczy, Csaba ED - Anon, A TI - Verification of an indigenous code system for calculation of WER-1200 (AES-2006) reactor T2 - Reactor Physics Paving the Way Towards More Efficient Systems: International Conference on Physics of Reactors, PHYSOR 2018 VL - Part F168384-2 PB - Curran Associates CY - Red Hook (NY) SN - 9781713808510 PY - 2018 SP - 1159 EP - 1170 PG - 12 UR - https://m2.mtmt.hu/api/publication/34824606 ID - 34824606 AB - 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) LA - English DB - MTMT ER - TY - JOUR AU - Michel-Sendis, F AU - Gauld, I AU - Martinez, JS AU - Alejano, C AU - Bossant, M AU - Boulanger, D AU - Cabellos, O AU - Chrapciak, V AU - Conde, J AU - Fast, I AU - Gren, M AU - Govers, K AU - Gysemans, M AU - Hannstein, V AU - Havlůj, F AU - Hennebach, M AU - Hordósy, Gábor AU - Ilas, G AU - Kilger, R AU - Mills, R AU - Mountford, D AU - Ortego, P AU - Radulescu, G AU - Rahimi, M AU - Ranta-Aho, A AU - Rantamäki, K AU - Ruprecht, B AU - Soppera, N AU - Stuke, M AU - Suyama, K AU - Tittelbach, S AU - Tore, C AU - Winckel, SV AU - Vasiliev, A AU - Watanabe, T AU - Yamamoto, T AU - Yamamoto, T TI - SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 110 PY - 2017 SP - 779 EP - 788 PG - 10 SN - 0306-4549 DO - 10.1016/j.anucene.2017.07.022 UR - https://m2.mtmt.hu/api/publication/3315948 ID - 3315948 LA - English DB - MTMT ER - TY - CHAP AU - Hegyi, György AU - Hordósy, Gábor AU - Keresztúri, András AU - Maráczy, Csaba AU - Panka, István AU - Temesvári, Emese ED - Vidovszky, István TI - Comprehensive solution of teh "MIDICORE" Benchmark by the KARATE and MCNP code system T2 - Proceedings of the twenty-sixth Symposium of AER PB - MTA Energiatudományi Kutatóközpont CY - Budapest SN - 9789637351266 PY - 2016 SP - 85 EP - 96 PG - 12 UR - https://m2.mtmt.hu/api/publication/3181885 ID - 3181885 LA - English DB - MTMT ER - TY - JOUR AU - Hordósy, Gábor AU - Hegyi, György AU - Keresztúri, András AU - Maráczy, Csaba AU - Temesvári, Emese AU - Zsolnay, Éva TI - Pressure Vessel Fluence Calculations for the Hungarian VVER-440 Units for the Power Uprate and the Llifetime Extension JF - EPJ WEB OF CONFERENCES J2 - EPJ WEB CONF VL - 106 PY - 2016 PG - 8 SN - 2101-6275 DO - 10.1051/epjconf/201610602011 UR - https://m2.mtmt.hu/api/publication/3123338 ID - 3123338 AB - 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. LA - English DB - MTMT ER - TY - JOUR AU - Zsolnay, Éva AU - Czifrus, Szabolcs AU - Fehér, Sándor AU - Hordósy, Gábor AU - Keresztúri, András AU - Kresz, N AU - Oszvald, F TI - Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP JF - EPJ WEB OF CONFERENCES J2 - EPJ WEB CONF VL - 106 PY - 2016 PG - 9 SN - 9782759819294 SN - 2101-6275 DO - 10.1051/epjconf/201610602010 UR - https://m2.mtmt.hu/api/publication/3120735 ID - 3120735 LA - English DB - MTMT ER - TY - CHAP AU - Hegyi, György AU - Hordósy, Gábor AU - Maráczy, Csaba AU - Temesvári, Emese ED - Jencic, I TI - Evaluation of the Full Core VVER-440 Benchmarks Using the KARATE and MCNP Code Systems T2 - 24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015) PB - Nuclear Society of Slovenia CY - Ljubljana SN - 9789616207386 T3 - 24th International Conference on Nuclear Energy for New Europe (NENE) PB - Nuclear Society of Slovenia PY - 2015 PG - 11 UR - https://m2.mtmt.hu/api/publication/27188015 ID - 27188015 LA - English DB - MTMT ER - TY - CHAP AU - Hegyi, György AU - Hordósy, Gábor AU - Maráczy, Csaba AU - Temesvári, Emese ED - Jenčič, Igor TI - Evaluation of theFullCore VVER-440 BenchmarksUsingthe KARATE and MCNP Code Systems T2 - NENE2015 Symposium PB - Nuclear Society of Slovenia CY - Portoroz SN - 9789616207386 PY - 2015 UR - https://m2.mtmt.hu/api/publication/3019809 ID - 3019809 LA - English DB - MTMT ER - TY - CHAP AU - Temesvári, Emese AU - Maráczy, Csaba AU - Hegyi, György AU - Hordósy, Gábor AU - Molnár, Attila ED - Anon, null TI - HPLWR Fine Mesh Core Analysis T2 - The 7th International Symposium on Supercritical-Water-Cooled Reactors (ISSCWR-7) PB - VTT Technical Research Centre of Finland CY - Helsinki SN - 9789513882891 PY - 2015 SP - 141 EP - 151 PG - 11 UR - https://m2.mtmt.hu/api/publication/3019653 ID - 3019653 LA - English DB - MTMT ER -