In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicability range is not enough to study the behavior of a Generation IV sodium-cooled fast reactor (SFR) during transients in which boiling is anticipated. The work reported here concerns the extension of the non-homogeneous, non-equilibrium two-fluid models, which are available in TRACE for steam-water, to sodium two-phase flow simulation. The conventional correlations for ordinary gas-liquid flows are used as basis, with optional correlations specific to liquid metal where necessary. A number...
International audienceThe paper proposes an overview of an R&D program for Gen4 Sodium Fast Reactors...
International audienceSodium Fast Reactors (SFRs) are being considered by several leading nuclearize...
A three-dimensional numerical model for the simulation of sodium boiling transients has been develop...
The thermal-hydraulic code TRACE is currently being extended at the Paul Scherrer Institute (PSI) fo...
International audienceAbstract The computational codes used in the evaluation of the European sodium...
This work involves the development of physical models for the constitutive relations of a two-fuid, ...
ISBN: 978-0-89448-722-4International audienceThe CEA R&D program on SFRs includes the study of react...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
This thesis, “Simulation of CABRI loss-of-flow experiments with the TRACE/FRED codes”, is a result ...
Nuclear power is nowadays in the front rank as regards helping to meet the growing worldwide energy ...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
An experimental and analytical program has been carried out in order to better understand the cause ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R&D...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
International audienceThe paper proposes an overview of an R&D program for Gen4 Sodium Fast Reactors...
International audienceSodium Fast Reactors (SFRs) are being considered by several leading nuclearize...
A three-dimensional numerical model for the simulation of sodium boiling transients has been develop...
The thermal-hydraulic code TRACE is currently being extended at the Paul Scherrer Institute (PSI) fo...
International audienceAbstract The computational codes used in the evaluation of the European sodium...
This work involves the development of physical models for the constitutive relations of a two-fuid, ...
ISBN: 978-0-89448-722-4International audienceThe CEA R&D program on SFRs includes the study of react...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
International audienceIn the framework of the research and development on GEN IV sodium fast reactor...
This thesis, “Simulation of CABRI loss-of-flow experiments with the TRACE/FRED codes”, is a result ...
Nuclear power is nowadays in the front rank as regards helping to meet the growing worldwide energy ...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
An experimental and analytical program has been carried out in order to better understand the cause ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R&D...
When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodiu...
International audienceThe paper proposes an overview of an R&D program for Gen4 Sodium Fast Reactors...
International audienceSodium Fast Reactors (SFRs) are being considered by several leading nuclearize...
A three-dimensional numerical model for the simulation of sodium boiling transients has been develop...