Recently the reactor dynamics code DYN3D (including an internal fuel behavior model) was coupled to the fuel performance code TRANSURANUS at assembly level. The coupled code system applies the new general TRANSURANUS coupling interface, hence it can be used for one-way or two-way coupling. In the coupling, DYN3D provides process time, time-dependent rod power and thermal hydraulics conditions to TRANSURANUS, which in case of the two-way coupling approach replaces completely the internal DYN3D fuel behavior model and transfers parameters like radial fuel temperature distribution and cladding temperature back to DYN3D. For the first time results of the coupled code system are presented for a post-crisis heat transfer. The corresponding heat t...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
Multiphysics coupling of neutronics/thermal-hydraulics models is essential for accurate modeling of ...
In the last two decades the reactor dynamics code DYN3D was coupled to thermal hydraulics system cod...
Several institutions plan to couple the fuel performance code TRANSURANUS developed by the European ...
The code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reac...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
The development of an advanced Reduced Order Model (ROM) including four heated channels and meant to...
© 2018 Elsevier Ltd Best-estimate codes, which couple neutronic and thermal-hydraulic solvers, are m...
A loosely coupled reactor is subject to local perturbations due to reactivity device movement that a...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The research deals with boron dilution that might occur during some transient conditions in PWR, V...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
Multiphysics coupling of neutronics/thermal-hydraulics models is essential for accurate modeling of ...
In the last two decades the reactor dynamics code DYN3D was coupled to thermal hydraulics system cod...
Several institutions plan to couple the fuel performance code TRANSURANUS developed by the European ...
The code DYN3D/M2 is used for investigations of reactivity transients in cores of thermal power reac...
Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...
The development of an advanced Reduced Order Model (ROM) including four heated channels and meant to...
© 2018 Elsevier Ltd Best-estimate codes, which couple neutronic and thermal-hydraulic solvers, are m...
A loosely coupled reactor is subject to local perturbations due to reactivity device movement that a...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The research deals with boron dilution that might occur during some transient conditions in PWR, V...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
Analyzing the safety margins in transients and accidents of nuclear reactors 3-dimensional models of...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
Multiphysics coupling of neutronics/thermal-hydraulics models is essential for accurate modeling of ...