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 - Ponya, Petra AU - Csom, Gyula AU - Fehér, Sándor TI - Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel JF - JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE J2 - J NUCLEAR ENG RAD SCI VL - 6 PY - 2020 IS - 3 PG - 5 SN - 2332-8983 DO - 10.1115/1.4046354 UR - https://m2.mtmt.hu/api/publication/31449391 ID - 31449391 N1 - Export Date: 8 October 2020 Correspondence Address: Pónya, P.; Department of Nuclear Techniques, Institute of Nuclear Techniques, Budapest University of Technology and Economics, Muegyetem rkp. 9, R Bld., Hungary; email: petraponya@gmail.com AB - Fast neutron irradiation causes embrittlement of the reactor pressure vessel (RPV) material; therefore, it may end operation life before design lifetime. Well-known method to recuperate crystal lattice dislocations is annealing. In the current version of thorium fueled supercritical water-cooled reactor (SCWR) design proposed by the Institute of Nuclear Technology at Budapest University of Technology and Economics (BME NTI), the supercritical fluid flows upward between the core barrel and the inner surface of the RPV thereby, the coolant would keep the RPV's temperature at similar to 500 degrees C. This reverse coolant flow direction would decrease the embrittlement of RPV by constant annealing. To minimize the fast neutron flux increase, a relatively thin shielding connected to the inner surface of the barrel could be used. This presents fast neutron irradiation analysis, performed for different settings of the shielding to reduce fast neutron flux reaching the inner surface of RPV. LA - English DB - MTMT ER - TY - CHAP AU - Halász, Máté Gergely AU - Brolly, Áron Péter AU - Szieberth, Máté AU - Fehér, Sándor TI - Fuel cycle studies of Generation IV reactors with the SITON v2.0 code and the FITXS burn-up scheme T2 - Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17) PB - International Atomic Energy Agency (IAEA) SN - 9789201086181 T3 - Proceedings series/ International Atomic Energy Agency PY - 2018 PG - 10 UR - https://m2.mtmt.hu/api/publication/32796964 ID - 32796964 LA - English DB - MTMT ER - TY - JOUR AU - Halász, Máté Gergely AU - Szieberth, Máté AU - Fehér, Sándor TI - FITXS: A fast and flexible burn-up scheme based on the fitting of one-group cross-sections JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 104 PY - 2017 SP - 267 EP - 281 PG - 15 SN - 0306-4549 DO - 10.1016/j.anucene.2017.02.010 UR - https://m2.mtmt.hu/api/publication/3201111 ID - 3201111 LA - English DB - MTMT ER - TY - JOUR AU - Brolly, Áron Péter AU - Halász, Máté Gergely AU - Szieberth, Máté AU - Nagy, L AU - Fehér, Sándor TI - Physical model of the nuclear fuel cycle simulation code SITON JF - ANNALS OF NUCLEAR ENERGY J2 - ANN NUCL ENERGY VL - 99 PY - 2017 SP - 471 EP - 483 PG - 13 SN - 0306-4549 DO - 10.1016/j.anucene.2016.10.001 UR - https://m2.mtmt.hu/api/publication/3134362 ID - 3134362 LA - English DB - MTMT ER - TY - JOUR AU - German, Péter AU - Fehér, Sándor AU - Czifrus, Szabolcs AU - Yamaji, Bogdán TI - Analysis of heat source distribution in internal circulating surface heat transfer molten salt reactor JF - PROGRESS IN NUCLEAR ENERGY J2 - PROG NUCL ENERG VL - 92 PY - 2016 SP - 155 EP - 163 PG - 9 SN - 0149-1970 DO - 10.1016/j.pnucene.2016.07.018 UR - https://m2.mtmt.hu/api/publication/3120750 ID - 3120750 AB - The Molten Salt Reactor (MSR) is one of the Generation IV nuclear reactor concepts that were selected by the Generation IV International Forum in 2000. The concept is based on liquid fuel instead of solid fuel assemblies. Besides the advantages, there are several aspects of operation that can hinder the realization of this reactor concept. In this paper, the authors investigate the neutronics behaviour of a new sub-concept that offers solutions for many of the technical problems. The analysis was performed using the particle transport code MCNPX 2.7. The paper focuses on the short-term and steady state heat source distribution in the fuel salt and in the graphite moderator. Accordingly, neither burn-up effects nor reactivity transients are considered. The sensitivity of the effective multiplication factor on different geometrical and material parameters was studied. The results obtained indicate that the main region of heat deposition is in the internal and external channels of the graphite moderator. Only a few percent of the total heat power is released in the graphite moderator, where the gamma and neutron related heat deposition is on the same scale. The results also prove that the heat source distribution does not change drastically upon the actuation of the control rods. © 2016 Elsevier Ltd 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 - JOUR AU - Babcsány, Boglárka AU - Czifrus, Szabolcs AU - Fehér, Sándor TI - Methodology and conclusions of activation calculations of WWER-440 type nuclear power plants JF - NUCLEAR ENGINEERING AND DESIGN J2 - NUCL ENG DES VL - 284 PY - 2015 SP - 228 EP - 237 PG - 10 SN - 0029-5493 DO - 10.1016/j.nucengdes.2014.11.032 UR - https://m2.mtmt.hu/api/publication/2969965 ID - 2969965 LA - English DB - MTMT ER - TY - CONF AU - Áron, Brolly AU - Szieberth, Máté AU - Halász, Máté Gergely AU - Nagy, Lajos AU - Fehér, Sándor TI - Development and application of SITON, a new fuel cycle simulation code T2 - Actinide and fission product partitioning and transmutation PB - OECD Nuclear Energy Agency (NEA) C1 - Párizs PY - 2015 SP - 404 EP - 415 PG - 12 UR - https://m2.mtmt.hu/api/publication/2949545 ID - 2949545 LA - English DB - MTMT ER - TY - CHAP AU - Szieberth, Máté AU - Halász, Máté Gergely AU - Reiss, Tibor AU - Fehér, Sándor ED - S, Monti TI - FUEL CYCLE STUDIES ON MINOR ACTINIDE BURNING IN GAS COOLED FAST REACTORS T2 - Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) PB - International Atomic Energy Agency (IAEA) CY - Bécs SN - 9789201041142 PY - 2015 PG - 10 UR - https://m2.mtmt.hu/api/publication/2917806 ID - 2917806 LA - English DB - MTMT ER -