When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodium-cooled fast reactors, a high-velocity, high-temperature jet with sodium-water chemical reaction may cause wastage on the adjacent tubes. For assessment of the wastage environment, a mechanistic computer code called SERAPHIM calculating compressible multicomponent multiphase flow with sodium-water chemical reaction has been developed. In this study, applicability of the SERAPHIM code was investigated through the analysis of the experiment on water vapor discharging in liquid sodium under actual condition of the steam generator. The computational domain consists of the cylindrical vessel and the simulated two horizontal heat transfer tubes. T...
L’étude des conséquences de la réaction sodium-eau (RSE) est un enjeu dans le cadre de la sûreté des...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
The aim of the project is to design a steam generator in which the sodium flows pipeline hand, and o...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
Sensitivity studies on Sodium-Water Reaction (SWR), which will take place in a steam generator of Li...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
In this paper, we describe a physicomathematical model of the processes that occur in a sodium circu...
AbstractIn this paper, we describe a physicomathematical model of the processes that occur in a sodi...
The presented paper contains a description of approaches to simulate processes, observed during leak...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
A sodium–water reaction takes place when high-pressured water vapor leaks into sodium through a tiny...
Abstract – A numerical investigation of sodium-water reaction (SWR) phenomenon under a tube bundle c...
In a sodium-cooled fast reactor (SFR), liquid sodium is used as a heat transfer fluid because of its...
Translating the steam generator functional requirements intospecific design criteria requires a deep...
L’étude des conséquences de la réaction sodium-eau (RSE) est un enjeu dans le cadre de la sûreté des...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
The aim of the project is to design a steam generator in which the sodium flows pipeline hand, and o...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
Sensitivity studies on Sodium-Water Reaction (SWR), which will take place in a steam generator of Li...
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat fr...
AbstractSodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer...
In this paper, we describe a physicomathematical model of the processes that occur in a sodium circu...
AbstractIn this paper, we describe a physicomathematical model of the processes that occur in a sodi...
The presented paper contains a description of approaches to simulate processes, observed during leak...
AbstractThe prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Kor...
A sodium–water reaction takes place when high-pressured water vapor leaks into sodium through a tiny...
Abstract – A numerical investigation of sodium-water reaction (SWR) phenomenon under a tube bundle c...
In a sodium-cooled fast reactor (SFR), liquid sodium is used as a heat transfer fluid because of its...
Translating the steam generator functional requirements intospecific design criteria requires a deep...
L’étude des conséquences de la réaction sodium-eau (RSE) est un enjeu dans le cadre de la sûreté des...
In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for r...
The aim of the project is to design a steam generator in which the sodium flows pipeline hand, and o...