The Numerical Nuclear Reactor (NNR) was developed to provide a high-fidelity tool for light water reactor analysis based on first-principles models. High fidelity is accomplished by integrating full physics, highly refined solution modules for the coupled neutronic and thermal-hydraulic phenomena. Each solution module employs methods and models that are formulated faithfully to the first principles governing the physics, real geometry, and constituents. Specifically, the critical analysis elements that are incorporated in the coupled code capability are a direct whole-core neutron transport solution and an ultra-fine-mesh computational fluid dynamics / heat transfer solution, each obtained with explicit (subfuel- pin-cell level) hete...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the de...
This thesis presents fine-mesh multiphysics methodologies and algorithms for <br />numerical predict...
In this paper we present a fine-mesh solver aimed at resolving in a coupled manner and at the pin ce...
AbstractIn this paper we present a fine-mesh solver aimed at resolving in a coupled manner and at th...
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...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
An overview on nuclear methods for boiling water reactors (BWR) core design and analysis is provided...
Traditional nuclear reactor system analysis codes such as RELAP and TRAC employ an operator split me...
The accuracy requirements for modern nuclear reactor simulation are steadily increasing due to the c...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions o...
This paper describes the use of detailed multidisciplinary fluid/thermal/ structural/neutronic simul...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the de...
This thesis presents fine-mesh multiphysics methodologies and algorithms for <br />numerical predict...
In this paper we present a fine-mesh solver aimed at resolving in a coupled manner and at the pin ce...
AbstractIn this paper we present a fine-mesh solver aimed at resolving in a coupled manner and at th...
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...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
An overview on nuclear methods for boiling water reactors (BWR) core design and analysis is provided...
Traditional nuclear reactor system analysis codes such as RELAP and TRAC employ an operator split me...
The accuracy requirements for modern nuclear reactor simulation are steadily increasing due to the c...
The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technol...
This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions o...
This paper describes the use of detailed multidisciplinary fluid/thermal/ structural/neutronic simul...
The thermal hydraulic analysis of nuclear reactors is largely performed by what are known as system...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the de...