The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technology (KIT) is investigating the application of the meso- and microscale analysis for the prediction of local safety parameters for light water reactors (LWR). By applying codes like CFD (computational fluid dynamics) and SP3 (simplified transport) reactor dynamics it is possible to describe the underlying phenomena in a more accurate manner than by the nodal/coarse 1D thermal hydraulic coupled codes. By coupling the transport (SP3) based neutron kinetics (NK) code DYN3D with NEPTUNE-CFD, within a parallel MPI-environment, the NHESDYN platform is created. The newly developed system will allow high fidelity simulations of LWR fuel assemblies and...
The precise prediction of power generation, heat transfer and flow distribution within a reactor cor...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
This dissertation contributes to the development of high-fidelity coupled neutron kinetic and therma...
We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal-hydrau...
The aim of this thesis is to develop and implement a code for solving the coupled multiphysics of PW...
We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal- hydra...
International audienceMolten salt nuclear reactors (MSRs) constitute a promising technology to produ...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions o...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
The precise prediction of power generation, heat transfer and flow distribution within a reactor cor...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
The precise prediction of power generation, heat transfer and flow distribution within a reactor cor...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
This dissertation contributes to the development of high-fidelity coupled neutron kinetic and therma...
We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal-hydrau...
The aim of this thesis is to develop and implement a code for solving the coupled multiphysics of PW...
We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal- hydra...
International audienceMolten salt nuclear reactors (MSRs) constitute a promising technology to produ...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions o...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
The precise prediction of power generation, heat transfer and flow distribution within a reactor cor...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
The precise prediction of power generation, heat transfer and flow distribution within a reactor cor...
In this work we investigate the thermal-hydraulics behavior of a PWR nuclear reactor core, evaluatin...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...