PhD4Gen seminar 07.04.2020

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Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska (UZ3)
Departament Badań Układów Złożonych (DUZ)

Wtorek: 07.04.2020

Tomasz Hanusek
Modelling of circulating fuel reactors based on the Molten Salt Reactor Experiment


One of the most crucial point of a nuclear reactor’s safety is behaviour during severe transient and withstand them. This is even more important in case of new concepts of reactors, especially when LWR’s (Light Water Reactors) regulations have to be modified to be appropriate for other designs, like for molten salt reactor experiment (MSRE).

For that purpose TRACE (TRAC/RELAP Advanced Computational Engine) – NRC (Nuclear Regulatory Commission) flagship code, and Serpent 2, were chosen.

I will present results of the transient simulations for MSRE based on the calculation in these 2 codes.


Serdecznie zapraszamy,
M. Dąbrowski, T. Kwiatkowski

The presentation is available upon the request.