Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepared independently without a knowledge of fuel loading pattern. The fuel assemblies are simulated in infinite lattice (with mirror boundary conditions). Rehomogenization method is based on combination of actual neutron flux in fuel assembly with macroscopic data from infinite lattice. Rehomogenization method was implemented into the macrocode Andrea and tested on a reference cases. Cases consist of fuel cases, cases with strong absorber, cases with absorption rods, or cases with reflector assemblies. Testing method is based on a comparisons of homogenized and rehomogenized macroscopic cross sections and later on a comparisons of relative power o...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and co...
In Very High Temperature Reactors (VHTRs), the long mean-free-path and large migration area of neutr...
Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepare...
Diplomová práce je zaměřena na homogenizaci dat pro výpočty tlakovodních reaktorů s použitím metody ...
3D deterministic core calculation represents important category of the nuclear fuel cycle and safe N...
Few-group cross sections used in nodal calculations derive from standard energy collapsing and spati...
High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR),...
Nodal diffusion is currently the preferred neutronics model for industrial reactor core calculations...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with b...
Due to cost effective and simplicity homogeneous reactors have been widely used for experimental and...
We propose a two-dimensional (2-D) modal approach for spatial rehomogenization of nodal cross sectio...
The paper presents the influence of spacer grid homogenization during cross section generation on co...
In reactor core nodal analysis, the dependence of few-group, homogenized cross sections on the local...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and co...
In Very High Temperature Reactors (VHTRs), the long mean-free-path and large migration area of neutr...
Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepare...
Diplomová práce je zaměřena na homogenizaci dat pro výpočty tlakovodních reaktorů s použitím metody ...
3D deterministic core calculation represents important category of the nuclear fuel cycle and safe N...
Few-group cross sections used in nodal calculations derive from standard energy collapsing and spati...
High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR),...
Nodal diffusion is currently the preferred neutronics model for industrial reactor core calculations...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with b...
Due to cost effective and simplicity homogeneous reactors have been widely used for experimental and...
We propose a two-dimensional (2-D) modal approach for spatial rehomogenization of nodal cross sectio...
The paper presents the influence of spacer grid homogenization during cross section generation on co...
In reactor core nodal analysis, the dependence of few-group, homogenized cross sections on the local...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and co...
In Very High Temperature Reactors (VHTRs), the long mean-free-path and large migration area of neutr...