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Analysis and development of spatial hp-refinement methods for the neutron tra...
The different neutronic parameters have to be calculated with a higher accuracy in order to design the 4th generation reactor cores. As memory storage and computation... -
New modelling method for fast reactor neutronic behaviours analysis.
Due to safety rules running on fourth generation reactors’ core development,neutronics simulation tools have to be as accurate as never before. First part of this... -
Suppression of the initial transient in MonteCarlo criticality simulations
Criticality Monte Carlo calculations aim at estimating the effective multiplication factor (k-effective) for a fissile system through iterations simulating neutrons... -
Mixed-hybrid finite element method for the transport equation<br />and diffus...
This thesis focuses on mathematical analysis, numerical resolution and modelling of the transport equations.<br /> First of all, we deal with numerical... -
Monte Carlo burnup codes acceleration using the correlated sampling method
For several years, Monte Carlo burnup/depletion codes have appeared, which couple Monte Carlo codes to simulate the neutron transport to deterministic methods, which... -
Analysis and development of a numerical discretization scheme of the neutron ...
The method of characteristics is a flexible and efficient method solving the transport equation. It has been largely used in two dimension calculations because it...
