International audienceIn order to accurately compute the ASTRID4$^{th}$ generation Sodium Fast Reactor (SFR) prototype neutronic parameters, a new APOLLO3® deterministic code is under development at CEA. It will be part of the APOLLO3-SFR package (set of nuclear data, solvers from the code, calculation schemes) dedicated to fast reactor studies. In this paper, an experimental validation of this package is carried out with both ECCO and TDT-generated cross-sections libraries provided from ERANOS2 and APOLLO3-SFR respectively. To do so, experiments realized in the ZPPR reactor, dedicated to large sodium fast breeder reactors are reproduced according to the corresponding benchmark available in the IRPhE database. The new INCA neutronic interfa...
In the last few years, and within the framework of different European projects, KENO-VI code from SC...
International audienceTo support the development of Sodium-cooled Fast Reactors (SFRs) of Generation...
A study was performed to validate the existing tools for fast reactor neutronics analysis against pr...
International audienceIn order to accurately compute the ASTRID4$^{th}$ generation Sodium Fast React...
International audienceASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
International audienceHigh accuracy neutronic simulations are required for the development of Genera...
International audienceHigh accuracy neutronic simulations are required for the development of Genera...
International audienceThe present work details a new benchmark to be produced to the International C...
The present work details a new benchmark to be produced to the International Community, for dealing ...
Sodium-cooled Fast Reactors (SFRs) remain a potential candidate to meet future energy needs. In addi...
International audienceThe Sodium-cooled fast neutron reactor ASTRID is currently under design and de...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
International audienceThe Superphenix reactor remains the largest Sodium-cooled Fast Reactor ever bu...
International audienceThe development of Sodium-cooled Fast Reactors (SFRs) is promoted by the Gener...
In the last few years, and within the framework of different European projects, KENO-VI code from SC...
International audienceTo support the development of Sodium-cooled Fast Reactors (SFRs) of Generation...
A study was performed to validate the existing tools for fast reactor neutronics analysis against pr...
International audienceIn order to accurately compute the ASTRID4$^{th}$ generation Sodium Fast React...
International audienceASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
International audienceHigh accuracy neutronic simulations are required for the development of Genera...
International audienceHigh accuracy neutronic simulations are required for the development of Genera...
International audienceThe present work details a new benchmark to be produced to the International C...
The present work details a new benchmark to be produced to the International Community, for dealing ...
Sodium-cooled Fast Reactors (SFRs) remain a potential candidate to meet future energy needs. In addi...
International audienceThe Sodium-cooled fast neutron reactor ASTRID is currently under design and de...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
International audienceThe Superphenix reactor remains the largest Sodium-cooled Fast Reactor ever bu...
International audienceThe development of Sodium-cooled Fast Reactors (SFRs) is promoted by the Gener...
In the last few years, and within the framework of different European projects, KENO-VI code from SC...
International audienceTo support the development of Sodium-cooled Fast Reactors (SFRs) of Generation...
A study was performed to validate the existing tools for fast reactor neutronics analysis against pr...