Xenon Transients Simulation Using the Reactor Code DONJON

Abstract

The DONJON reactor code has a spatial-kinetic capability used to study the transient behavior of the flux distribution. The xenon transients are simulated in a CANDU reactor using the improved quasistatic method with the help of the Feedback Model which calculates the nuclear properties depending on local parameters for each bundle in the core. The introduction of a new module in DONJON allows the calculation of the xenon and iodine concentrations for each bundle in the core by considering its local conditions.