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pro vyhledávání: '"Máté Halász"'
Autor:
Máté Halász, M. Szieberth
Publikováno v:
Annals of Nuclear Energy. 121:429-445
This paper presents mathematical models of the nuclide transmutation and decay chains based on discrete-time and continuous-time Markov chains. The models describe the transmutation chains of individual atoms as stochastic processes, and can provide
Autor:
Máté Halász, M. Szieberth
Publikováno v:
Kerntechnik. 83:319-324
Gen-IV fast reactors are envisaged to operate in closed fuel cycles due to their ability to breed their fuel from fertile feed and burn minor actinides produced by themselves or thermal reactors in the nuclear park. The optimization of such fuel cycl
Publikováno v:
Annals of Nuclear Energy. 104:267-281
The closure of the nuclear fuel cycle is currently envisaged with the deployment of Generation IV fast reactors which are able to generate their fuel from fertile 238 U or 232 Th, and also burn minor actinides arising from legacy wastes and thermal r
Publikováno v:
Annals of Nuclear Energy. 99:471-483
Finding answers to main challenges of nuclear energy, like resource utilisation or waste minimisation, calls for transient fuel cycle modelling. This motivation led to the development of SITON v2.0 a dynamic, discrete facilities/discrete materials an
Publikováno v:
Annals of Nuclear Energy. 149:107752
Dynamic Monte Carlo (DMC) simulation of realistic nuclear reactors requires powerful variance reduction methods for even a few seconds of real time calculations. State-of-the-art numerical methods deal with the dynamic nature of the problem via succe
Publikováno v:
Osváth, S, Vajda, N, Molnar, Z, Kovacs-Szeles, E, Braun, M & Halasz, M 2017, ' Determination of 93 Zr in nuclear power plant wastes ', Journal of Radioanalytical and Nuclear Chemistry, vol. 314, no. 1, pp. 31-38 . https://doi.org/10.1007/s10967-017-5382-z
A radioanalytical method for separation and determination of 125Sb has been developed. This method is based on retention of fluoric complexes of antimony on anion exchange resin and γ-ray spectrometry. Using this method, 70(±17) % recovery was achi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ca1cbcc82ea4714a7fe61d17ccd20626
https://orbit.dtu.dk/en/publications/2547954f-9a9f-48e1-9ae7-1328454be0da
https://orbit.dtu.dk/en/publications/2547954f-9a9f-48e1-9ae7-1328454be0da
Publikováno v:
2013 4th International Youth Conference on Energy (IYCE).
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 ac