Topic: Design of an experimental test section for the energy conversion system of a Surface Nuclear Reactor based on the AMTEC technology
Where: Bologna
Details: One of the key systems of an SNR is the one in charge of converting the thermal energy coming from the core into electrical ...
Pubblicato il: 20 dicembre 2025
Topic: Improvement of the semi-analytical model for evaluating the fuel-cladding contact pressure in the TEMIDE thermomechanics code
Where: Bologna
Details: Fuel-cladding contact pressure is one of the fundamental parameters used to verify the tightness of a fuel rod throughout its operational ...
Pubblicato il: 20 dicembre 2025
Topic: Mechanical design and characterization of the optimal core configuration during the launch phase of a Surface Nuclear Reactor for Moon exploration
Where: Bologna
Details: Differently to standard nuclear reactors for terrestrial applications, Surface Nuclear Reactors (SNRs) experience a peculiar ...
Pubblicato il: 20 dicembre 2025
Topic: Extension of the TEMIDE thermomechanical code to cases with fuel in the form of Uranium nitride or mixed Uranium-Plutonium nitride
Where: Bologna
Details: The activity requires finding models and correlations applicable to nitride fuels and integrate them into the TEMIDE code to enable their ...
Pubblicato il: 20 dicembre 2025
Topic: Thermal design and analysis of the shielding and reactivity control systems of a Surface Nuclear Reactor
Where: Bologna
Details: The component experiencing the hottest temperature in the power production area of an SNR is the core. While the majority of the energy is deposited in the fuel ...
Pubblicato il: 20 dicembre 2025
Topic: Coupling of the TIFONE subchannel code with the ANTEO subchannel code by means of a data exchange in MED format
Where: Bologna
Details: The development of this tool would allow the study of the thermal-hydraulics of a reactor core by coupling the ANTEO sub-channel code, used to study the ...
Pubblicato il: 20 dicembre 2025
Topic: Comparison of OpenFOAM thermo-hydraulic simulations with experimental data available in the literature
Where: Bologna
Details: The activity aims to study and validate turbulence models by comparing data obtained from numerical simulations with data available in the literature regarding the ...
Pubblicato il: 20 dicembre 2025
Topic: Creation of a module to enable the inclusion of thermo-hydraulic feedback in the ERANOS neutron computing suite
Where: Bologna
Details: Typically, neutronics calculations are performed assuming a uniform distribution of coolant and fuel temperatures throughout the core. However, since reactivity ...
Pubblicato il: 20 dicembre 2025
Topic: Thermal design of the transfer flask used for the core reload operations of the ALFRED lead-cooled reactor
Where: Bologna
Details: For reloading the ALFRED reactor, it is planned to use a lead-filled container, into which the assemblies can be transferred so that the residual heat still generated ...
Pubblicato il: 20 dicembre 2025
Topic: Neutronic design and characterization of the optimal core configuration during the launch phase of a Surface Nuclear Reactor for Moon exploration
Where: Bologna
Details: Differently to standard nuclear reactors for terrestrial applications, Surface Nuclear Reactors (SNRs) experience a peculiar ...
Pubblicato il: 20 dicembre 2025
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