International audienceThe present work details a new benchmark to be produced to the International Community, for dealing with neutronics code validation in the frame of SFRs (Sodium Fast Reactors) severe accidents sequences leading to core degradation and material relocation. The benchmark is based on a complete re-analysis of the SNEAK-12A experimental program, using TRIPOLI-4, MCNP and Serpent-2 Monte Carlo codes as reference tools, and the ERANOS system of codes for deterministic calculations, all based on JEFF-3.1.1 nuclear data libraries. The complete material balance is resumed, and the main degradation sequences are detailed. Preliminary results on available experimental results (k eff) are given, and additional local quantities are...
Paper 15214International audienceIn the framework of the development of the Sodium Fast Reactor tech...
The aim of the present paper is to present first representativity studies of local reactivity effect...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...
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 ...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
The present work details further information regarding a new benchmark to be introduced to the inter...
The field of recriticality possibilities in both light water reactors and fast reactors remains an i...
Studies related to severe core accidents constitute a crucial element in the safety design of Gen-IV...
International audienceStudies related to severe core accidents are a key factor in Gen-IV safety. A ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
International audienceWithin the framework of the generation IV Sodium Fast Reactors (SFR) R&D progr...
International audienceIn order to accurately compute the ASTRID4$^{th}$ generation Sodium Fast React...
A study was performed to validate the existing tools for fast reactor neutronics analysis against pr...
Paper 15214International audienceIn the framework of the development of the Sodium Fast Reactor tech...
The aim of the present paper is to present first representativity studies of local reactivity effect...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...
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 ...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
The present work details further information regarding a new benchmark to be introduced to the inter...
The field of recriticality possibilities in both light water reactors and fast reactors remains an i...
Studies related to severe core accidents constitute a crucial element in the safety design of Gen-IV...
International audienceStudies related to severe core accidents are a key factor in Gen-IV safety. A ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
International audienceWithin the framework of the generation IV Sodium Fast Reactors (SFR) R&D progr...
International audienceIn order to accurately compute the ASTRID4$^{th}$ generation Sodium Fast React...
A study was performed to validate the existing tools for fast reactor neutronics analysis against pr...
Paper 15214International audienceIn the framework of the development of the Sodium Fast Reactor tech...
The aim of the present paper is to present first representativity studies of local reactivity effect...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...