Impact of the loss of the RCIC system at different times during the loss of external power in a BWR

As part of the activities aimed to analyzing the consequences of serious accidents at a nuclear power plant with a boiling water reactor, the Instituto Nacional de Investigaciones Nucleares (ININ) through the Group for Thermohydraulic Analysis and Safety of Nuclear Reactors of the Nuclear Systems Department, has carried out the process of simulating events of loss of external and internal power without the emergency systems of the same and with loss of the core cooling system with the reactor isolated at 0.5, 1.0, 1.5, 2.0, 2.5, 3.0, 3.5 and 4.0 hours after the event started performed with the Modular Accident Analysis Program 5.05 computational code. Preliminary results of the accident progression are presented both within the reactor pressure vessel and in the primary container, once of the loss of cooling is given, and in a graphical form, as well as important times for decision making, as the failure times of the reactor pressure vessel, times when hydrogen concentration thresholds are reached, etc. (author)