Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

The paper investigates the influence of the used thermal-hydraulic approximations on the coupled calculations of gas-cooled fast reactor design (hereby GFR 2400). The NESTLE code is used as coupled simulation tool and solves the multigroup neutron diffusion equation by the finite difference method t...

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Veröffentlicht in:	Journal of nuclear engineering and radiation science 2022-10, Vol.8 (4)
Hauptverfasser:	Osuský, Filip, Vrban, Branislav, Čerba, Štefan, Lüley, Jakub, Nečas, Vladimír
Format:	Artikel
Sprache:	eng
Online-Zugang:	Volltext
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