Presenters: Afaque Shams1 and Tomasz Kwiatkowski2
Co-authors2: Adam Padee, Piotr Wasiuk, Tobiasz Jarosiewicz, Sławomir Potempski
Patron of the project: prof. dr. hab. Mariusz Dąbrowski
1Nuclear Research and Consultancy Group (NRG)
2National Centre for Nuclear Research (NCBJ)
Dual Fluid Reactor (DFR) is a novel concept of a reactor which is operating in temperature amounts to 1300oC. DFR need high temperature resistant materials that retain their mechanical properties and withstand corrosion processes under a large neutron flux. Good construction materials for DFR are hard ceramics (such as Silicon Carbide, Zirconium Carbide and Titanium Carbide).
For a long period of time Probabilistic Safety Assessment (PSA) for Nuclear Power Plants were performed using Fault Tree (FT) and Event Tree (ET) technique. This technique has its pros and cons as any other currently used methodology. After Fukushima Daiichi accident problem with addressing multiple hazards had arrived and many scientists are trying to address it with new approaches for example Bayesian techniques.
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 others designs.
