Analysis of lead-cooled fast reactor using a core simulator

Abstract The Lead-cooled Fast Reactor (LFR) is a novel reactor concept, the core of which can be simulated by developing a dynamic model. The model consists of 3 sub-models; a block for reactor kinetics, thermal hydraulics and the reactivity feedback calculations. By implementation of the LFR core simulator, the response of the reactor has been shown for various test inputs. Certain events have been simulated in the LFR core (unprotected transient of overpower, loss of heat sink, loss of flow and a SCRAM shutdown). A sensitivity analysis has been performed and it is observed that the LFR core power is the most sensitive to changes in the average coolant temperature. A stability analysis has been performed to show that the LFR core has a stable configuration (for its normal operating conditions). Similarly, a noise analysis has revealed that the output parameters have the most adverse effect in case of a Gaussian noise being introduced in the reactivity of the core.