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Differential influence of instruments in nuclear core activity evaluation by ...
International audience -
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...
