International audienceThe Sodium-cooled Fast Reactor (SFR) core predesign process is commonly realized on the basis of expert advices and local parametric studies. As such, in-deep knowledge of physical phenomena avoids an important number of expensive simulations. However, the study space is explored only partially. To ease the computational burden metamodels, or surrogate models, can be used, to quickly evaluate the performances of a wide set of different cores, individually defined by a set of parameters (pellet diameter, fissile height...), in the study space. This paper presents the development of a simplified neutronics ERANOS reference core calculation scheme that is then implemented in the construction of the Design of Experiment (D...
Reactor core design is inherently a multi-objective problem which spans a large design space, and po...
International audienceIn the framework of Sodium-cooled Fast Reactors, core design studies are perfo...
Many scenario studies conducted by several countries consider the progressive deployment of low void...
International audienceThe Sodium-cooled Fast Reactor (SFR) core predesign process is commonly realiz...
Nuclear reactor core design is a highly multidisciplinary task where neutronics, thermal-hydraulics,...
La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
The sodium-cooled fast reactor (SFR), as a fast neutron spectrum system, is characterized by several...
Traditional designs of sodium cooled fast reactors have a positive sodium expansion feedback. During...
In this thesis, a parametric study was performed for four core designs of Sodium Fast Reactors (SFRs...
International audienceSince Sodium cooled Fast Reactors are present in many scenarios and strategies...
In the European Sodium Fast Reactor (ESFR) project supported by EURATOM in 2008-2012, a concept for ...
International audienceAn OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, O...
International audienceTo support the development of Sodium-cooled Fast Reactors (SFRs) of Generation...
Reactor core design is inherently a multi-objective problem which spans a large design space, and po...
International audienceIn the framework of Sodium-cooled Fast Reactors, core design studies are perfo...
Many scenario studies conducted by several countries consider the progressive deployment of low void...
International audienceThe Sodium-cooled Fast Reactor (SFR) core predesign process is commonly realiz...
Nuclear reactor core design is a highly multidisciplinary task where neutronics, thermal-hydraulics,...
La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo...
The design of innovative cores for Generation IV Sodium-cooled Fast Reactors (SFRs) must chiefly foc...
The sodium-cooled fast reactor (SFR), as a fast neutron spectrum system, is characterized by several...
Traditional designs of sodium cooled fast reactors have a positive sodium expansion feedback. During...
In this thesis, a parametric study was performed for four core designs of Sodium Fast Reactors (SFRs...
International audienceSince Sodium cooled Fast Reactors are present in many scenarios and strategies...
In the European Sodium Fast Reactor (ESFR) project supported by EURATOM in 2008-2012, a concept for ...
International audienceAn OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, O...
International audienceTo support the development of Sodium-cooled Fast Reactors (SFRs) of Generation...
Reactor core design is inherently a multi-objective problem which spans a large design space, and po...
International audienceIn the framework of Sodium-cooled Fast Reactors, core design studies are perfo...
Many scenario studies conducted by several countries consider the progressive deployment of low void...