The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
This paper presents an assessment of three deterministic core simulators with the focus on the neutr...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safe...
DYN3D reactor dynamics nodal diffusion code was originally developed for the analysis of Light Water...
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium...
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
A simulation suite has been developed to model reactor power distribution and multiphysics feedback ...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and tr...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The code DYN3D/M2 was developed for steady-state and transient analysis of reactor cores with hexago...
The code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reac...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
This paper presents an assessment of three deterministic core simulators with the focus on the neutr...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safe...
DYN3D reactor dynamics nodal diffusion code was originally developed for the analysis of Light Water...
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium...
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
A simulation suite has been developed to model reactor power distribution and multiphysics feedback ...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and tr...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The code DYN3D/M2 was developed for steady-state and transient analysis of reactor cores with hexago...
The code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reac...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand ou...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
This paper presents an assessment of three deterministic core simulators with the focus on the neutr...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...