International audienceIn order to improve safety and design of Sodium-cooled Fast nuclear Reactors (SFR), the CEA (French Commission for Atomic Energy and Alternative Energy) is involved in hypothetical severe accident scenario studies. These scenarios may lead to a nuclear power excursion that might induce the melting down of nuclear fuel, followed by its quick vaporization pushing away the surrounding liquid sodium. The mechanical energy released by the fuel vapor expansion leads to the reactor vessel mechanical loading. This paper presents a methodology relying on Non-Equilibrium Thermodynamics (NET) and Dimensional Analysis (DA) which allows to identify the driving physical phenomena that should be considered for the modeling of the vap...
International audienceOne important issue for the Sodium Fast Reactor (SFR) concept is the reactivit...
The explosion of superheated sodium is a phenomenon of interest in the analysis of automatic shutdow...
A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most...
International audienceIn order to improve safety and design of Sodium-cooled Fast nuclear Reactors (...
International audienceThe safety assessment of Sodium-cooled Fast Reactors (SFR) requires to account...
International audienceImproving safety is one of the current objective of the fourth generation of s...
International audienceThe fourth generation of sodium fast reactors (SFR) is developed taking into a...
This work concerns the assessment of the consequences deriving from a Hypothetical Core Disruptive A...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R&D...
Severe accidents’ modeling is required for the design and safety analysis of ASTRID, a Generation IV...
International audienceOne important issue for the Sodium Fast Reactor (SFR) concept is the reactivit...
The explosion of superheated sodium is a phenomenon of interest in the analysis of automatic shutdow...
A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most...
International audienceIn order to improve safety and design of Sodium-cooled Fast nuclear Reactors (...
International audienceThe safety assessment of Sodium-cooled Fast Reactors (SFR) requires to account...
International audienceImproving safety is one of the current objective of the fourth generation of s...
International audienceThe fourth generation of sodium fast reactors (SFR) is developed taking into a...
This work concerns the assessment of the consequences deriving from a Hypothetical Core Disruptive A...
A new computational methodology of sodium-water reaction (SWR), which occurs in a steam gen-erator o...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R&D...
Severe accidents’ modeling is required for the design and safety analysis of ASTRID, a Generation IV...
International audienceOne important issue for the Sodium Fast Reactor (SFR) concept is the reactivit...
The explosion of superheated sodium is a phenomenon of interest in the analysis of automatic shutdow...
A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most...