In this paper, we describe a physicomathematical model of the processes that occur in a sodium circuit with a variable flow cross-section in the case of a water leak into sodium. The application area for this technique includes the possibility of analyzing consequences of this leak as applied to sodium–water steam generators in fast neutron reactors. Hydrodynamic processes that occur in sodium circuits in the event of a water leak are described within the framework of a one-dimensional thermally nonequilibrium three-component gas–liquid flow model (sodium–hydrogen–sodium hydroxide). Consideration is given to the results of a mathematical modeling of experiments involving steam injection into the sodium loop of a circulation test facility. T...
Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework ...
Sensitivity studies on Sodium-Water Reaction (SWR), which will take place in a steam generator of Li...
391-396Steam generator (SG) of a liquid metal cooled fast breeder reactor (LMFBR) comprises sodium ...
AbstractIn this paper, we describe a physicomathematical model of the processes that occur in a sodi...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
The presented paper contains a description of approaches to simulate processes, observed during leak...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
A methodological approach has been developed for the computational investigation of the thermal-hydr...
The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolan...
In a sodium-cooled fast reactor (SFR), liquid sodium is used as a heat transfer fluid because of its...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework ...
Sensitivity studies on Sodium-Water Reaction (SWR), which will take place in a steam generator of Li...
391-396Steam generator (SG) of a liquid metal cooled fast breeder reactor (LMFBR) comprises sodium ...
AbstractIn this paper, we describe a physicomathematical model of the processes that occur in a sodi...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
The presented paper contains a description of approaches to simulate processes, observed during leak...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
A methodological approach has been developed for the computational investigation of the thermal-hydr...
The paper evaluates the possibility of modeling the heat transfer phenomena in a liquid-metal coolan...
In a sodium-cooled fast reactor (SFR), liquid sodium is used as a heat transfer fluid because of its...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework ...
Sensitivity studies on Sodium-Water Reaction (SWR), which will take place in a steam generator of Li...
391-396Steam generator (SG) of a liquid metal cooled fast breeder reactor (LMFBR) comprises sodium ...