Integration of the algorithms of the reactor control system in a code of kinetic space time

Certain classes of slow accidents, such as a channel break or a loss of moderator involve reactor regulating system (RRS) actions. Core and RRS modelling are then required to simulate such accidents. The RRS controls reactor power level and flux distribution with reactivity mechanisms. The data it uses are provided by flux responses of in-core detectors and by thermal measurements in the cooling system. The goal of this work is to implement CANDU-6 RRS algorithms and to include nuclear property modifications resulting from its actions in the reactor code DONJON. So power transients can be simulated. For time-dependent simulations, an integration technique for the kinetic equations is used to compute the macroscopic fluxes in the reactor A quasistatic approach will be used in order to cope with local perturbations and to shorten the CPU time when long transients are involved. The definition of the neutron behaviour equations and a brief explanation of the RRS algorithms will be given to show the theoretical basis of the simulator. Then core and mechanism modelling and RRS approximations will be explained. A number of transient studies will compose the last part of this thesis. We will then present the simulator validation and also examine its limitations. (author)