The core of a high-speed sodium-cooled reactor comprises a number of ‘ fuel elements’ consisting of hexagonal casings containing sheathed fissile material inside a large number of ‘ needles’ arranged to a hexagonal pitch. Helical wire windings around the individual needles prevent direct contact between them, with the whole constituting the ‘ fuel assembly ’. The needles form the boundaries of sodium ‘ channels’ , the heat balance and temperature distribution of which can only be calculated if the hydraulic and heat exchanges between individual channels are known. In order to study the ‘mixing problem ’ it was necessary to construct a hydraulic model operating with sodium, in which each needle could be heated individually by the Joule effe...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
Pour assoir la faisabilité du stockage interne dans de futurs réacteurs à neutrons rapides refroidis...
In sodium heat exchanger design, hydraulic problems mainly arise in the local areas comprising the t...
For its research programme on a steam generator for a sodium-cooled highspeed neutron reactor, Socié...
A number of design problems arise with liquid metal pumps (especially for sodium), which are mainly ...
The main methods of approach to liquid-metal circulation problems based on experience with a number ...
Dans le cadre du développement des réacteurs de génération IV, une des voies de recherche concerne l...
A number of problems arose in the design of the * phénix ’ reactor’s steam generators, which were as...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
The thermo-physical properties of a heat-conveying fluid are more fully characterized by its thermal...
La modélisation à échelle fine de la réaction sodium-eau est motivée par ses applications aux réacte...
L’étude des températures de flammes permet de confirmer les hypothèses précédemment émises sur le mo...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
The need for energy is growing in the world and the market of nuclear power is now once more expandi...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
Pour assoir la faisabilité du stockage interne dans de futurs réacteurs à neutrons rapides refroidis...
In sodium heat exchanger design, hydraulic problems mainly arise in the local areas comprising the t...
For its research programme on a steam generator for a sodium-cooled highspeed neutron reactor, Socié...
A number of design problems arise with liquid metal pumps (especially for sodium), which are mainly ...
The main methods of approach to liquid-metal circulation problems based on experience with a number ...
Dans le cadre du développement des réacteurs de génération IV, une des voies de recherche concerne l...
A number of problems arose in the design of the * phénix ’ reactor’s steam generators, which were as...
Fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch wit...
The thermo-physical properties of a heat-conveying fluid are more fully characterized by its thermal...
La modélisation à échelle fine de la réaction sodium-eau est motivée par ses applications aux réacte...
L’étude des températures de flammes permet de confirmer les hypothèses précédemment émises sur le mo...
AbstractNumerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried o...
The need for energy is growing in the world and the market of nuclear power is now once more expandi...
International audienceThe fuel pin bundles of Sodium-cooled Fast Reactors (SFR) undergo significant ...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
Pour assoir la faisabilité du stockage interne dans de futurs réacteurs à neutrons rapides refroidis...