Please join my meeting on your computer:
Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska (UZ3)
Departament Badań Układów Złożonych (DUZ)
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.
M. Dąbrowski, T. Kwiatkowski
The presentation is available upon the request.