Method for managing stoppage of a pressurised-water nuclear reactor

A method for managing stoppage of a submerged pressurized-water nuclear reactor of a module configured to produce electrical power, the module having a plurality of steam generators each being provided with a safety valve and associated with a standby condenser, the method comprising:

• detecting a primary/secondary leak of primary fluid into secondary fluid of one of the steam generators;
• automatically stopping the reactor and isolating the steam generator suffering from the primary/secondary leak;
• bringing the standby condensers online;
• monitoring a primary pressure of the primary fluid;
• determining that the primary pressure is below the set pressure of the safety valve of the steam generator, then isolating the standby condenser of the steam generator suffering from the primary/secondary leak by preventing the primary fluid from being supplied to the standby condenser;
• and
• continuing to passively cool the reactor with remaining steam generators of the plurality of steam generators and condensers.