3D deterministic core calculation represents important category of the nuclear fuel cycle and safe Nuclear Power Plant operation. The appropriate solution was not published yet. Data preparation process for non-fuel elements of the core represents the challenge for scientists. This report briefly introduce the problem of the data preparation process and gives the information about new input format for macrocode PARCS (PMAXS). The best homogenization process approach is to prepare data in infinite lattice cell for fuel assemblies, which are placed next to the another fuel assembly. Data for fuel assembly located next to the non-fuel region are better with preparation in the real geometry with the real boundary conditions. Results of the neut...
Ce travail de thèse est consacré à la mise en œuvre d’une méthode de décomposition de domaine appliq...
The main goal of this work is to perform pin-by-pin calculations of Swiss LWR fuel assemblies with n...
MSc (Nuclear Engineering), North-West University, Potchefstroom CampusUncertainty and sensitivity an...
Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepare...
The constant preparation issues are important for performing the few-group analysis for different st...
Within an energy system where nuclear reactors will likely play a critical role, it is fundamental t...
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B...
Reactor physics codes rely on cross-section data to determine, for example, flux profiles or burn-up...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The reactor core system consists of many materials, involving multi-physics processes, and can be an...
The high-level wastes stored in facilities above ground or shallow repositories, in close connection...
International audienceJHR is a new material testing reactor under construction at CEA Cadarache. Cur...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
M.Phil. (Energy Studies)Nodal diffusion methods are often used to calculate the distribution of neut...
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F a...
Ce travail de thèse est consacré à la mise en œuvre d’une méthode de décomposition de domaine appliq...
The main goal of this work is to perform pin-by-pin calculations of Swiss LWR fuel assemblies with n...
MSc (Nuclear Engineering), North-West University, Potchefstroom CampusUncertainty and sensitivity an...
Macroscopic cross section generation is key part of core calculation. Commonly, the data are prepare...
The constant preparation issues are important for performing the few-group analysis for different st...
Within an energy system where nuclear reactors will likely play a critical role, it is fundamental t...
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B...
Reactor physics codes rely on cross-section data to determine, for example, flux profiles or burn-up...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The reactor core system consists of many materials, involving multi-physics processes, and can be an...
The high-level wastes stored in facilities above ground or shallow repositories, in close connection...
International audienceJHR is a new material testing reactor under construction at CEA Cadarache. Cur...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
M.Phil. (Energy Studies)Nodal diffusion methods are often used to calculate the distribution of neut...
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F a...
Ce travail de thèse est consacré à la mise en œuvre d’une méthode de décomposition de domaine appliq...
The main goal of this work is to perform pin-by-pin calculations of Swiss LWR fuel assemblies with n...
MSc (Nuclear Engineering), North-West University, Potchefstroom CampusUncertainty and sensitivity an...