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Featured researches published by Sándor Fehér.


Transport Theory and Statistical Physics | 2007

Effect of fuel mixing phenomena on the kinetic behavior of molten salt reactors

J. Kópházi; G. Légrádi; S. Czifrus; Sándor Fehér

This paper deals with the significance of the effects of fuel mixing phenomena on the kinetic behavior of molten salt reactors. The point kinetic system of equations is applied with 1‐D resolution of the precursor equations. Dispersion is modeled by including diffusion into the precursor equations and by assuming perfect mixing in certain parts of the primary circuit of the reactor. Results are presented on the oscillating behavior of the reactor and the influence of fuel mixing phenomena on the amplitude of the accillations.


international youth conference on energy | 2013

Fuel cycle studies on the uranium utilization efficiency and minor actinide burning in gas cooled fast reactors

Máté Halász; Máté Szieberth; Sándor Fehér; T. Reiss

The gas cooled fast reactor (GFR) is a Generation IV reactor type considered as an alternative fast neutron reactor design aimed to improve the sustainability of nuclear energy by improved uranium utilization efficiency and opportunities for minor actinide burning.The following paper presents fuel cycle studies performed at the Budapest University of Technology and Economics for the assessment of the transmutational capabilities of the 2400 MWth GFR design in the framework of the GoFastR project. Based on the results of numerous (few thousand) core calculations, multidimensional regression method was used to develop a fast and flexible burnup calculation scheme which can be easily integrated into fuel cycle simulations. The burnup model was applied for the analysis of fuel cycle scenarios including a mixed fleet of GFRs and conventional LWRs. The equilibrium and transitional state properties of different recycling options were investigated in order to examine fuel utilization and trasmutational capabilites.


10th International Conference on Nuclear Engineering, Volume 4 | 2002

A Novel Molten Salt Reactor Concept to Implement the Multi-Step Time-Scheduled Transmutation Strategy

Gyula Csom; Sándor Fehér; Máté Szieberth

Nowadays the molten salt reactor (MSR) concept seems to revive as one of the most promising systems for the realization of transmutation. In the molten salt reactors and subcritical systems the fuel and material to be transmuted circulate dissolved in some molten salt. The main advantage of this reactor type is the possibility of the continuous feed and reprocessing of the fuel. In the present paper a novel molten salt reactor concept is introduced and its transmutational capabilities are studied. The goal is the development of a transmutational technique along with a device implementing it, which yield higher transmutational efficiencies than that of the known procedures and thus results in radioactive waste whose load on the environment is reduced both in magnitude and time length. The procedure is the multi-step time-scheduled transmutation, in which transformation is done in several consecutive steps of different neutron flux and spectrum. In the new MSR concept, named “multi-region” MSR (MRMSR), the primary circuit is made up of a few separate loops, in which salt-fuel mixtures of different compositions are circulated. The loop sections constituting the core region are only neutronically and thermally coupled. This new concept makes possible the utilization of the spatial dependence of spectrum as well as the advantageous features of liquid fuel such as the possibility of continuous chemical processing etc. In order to compare a “conventional” MSR and a proposed MRMSR in terms of efficiency, preliminary calculational results are shown. Further calculations in order to find the optimal implementation of this new concept and to emphasize its other advantageous features are going on.Copyright


Progress in Nuclear Energy | 2015

Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor

Zoltán Perkó; Sandro Pelloni; Konstantin Mikityuk; Jiri Křepel; Máté Szieberth; Girardin Gaëtan; Branislav Vrban; Jakub Lüley; Štefan Čerba; Máté Halász; Sándor Fehér; Tibor Reiss; Jan Leen Kloosterman; Richard Stainsby; Christian Poette


Archive | 2002

Method of and apparatus for transmuting radioactive waste

Gyula Csom; Attila Aszódi; Sándor Fehér; Máté Szieberth


Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment | 2012

Secondary charged particle activation method for measuring the tritium production rate in the breeding blankets of a fusion reactor

I. Rovni; Máté Szieberth; Sándor Fehér


Nuclear Engineering and Design | 2012

MOX fuel effects on the isotope inventory in LWRs

Sándor Fehér; T. Reiss; A. Wirth


Fusion Engineering and Design | 2011

A proposed method for foil set qualification for multiple foil activation measurements in the TBMs

I. Rovni; Máté Szieberth; Sándor Fehér; A. Klix


Annals of Nuclear Energy | 2017

Physical model of the nuclear fuel cycle simulation code SITON

Á. Brolly; Máté Halász; Máté Szieberth; L. Nagy; Sándor Fehér


Annals of Nuclear Energy | 2017

FITXS: A fast and flexible burn-up scheme based on the fitting of one-group cross-sections

Máté Halász; Máté Szieberth; Sándor Fehér

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Máté Szieberth

Budapest University of Technology and Economics

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Gyula Csom

Budapest University of Technology and Economics

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Máté Halász

Budapest University of Technology and Economics

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I. Rovni

Budapest University of Technology and Economics

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Szabolcs Czifrus

Budapest University of Technology and Economics

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Jan Leen Kloosterman

Delft University of Technology

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Attila Aszódi

Budapest University of Technology and Economics

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Zoltán Perkó

Delft University of Technology

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A. Keresztúri

Hungarian Academy of Sciences

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A. Wirth

Semmelweis University

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