| 摘要 |
The present invention relates to a system for discharging the residual power of a pressurised water nuclear reactor (100). The system comprises a reserve of water (102), at least one steam generator, called the GV module (119), wherein the primary water heated by the core (113) either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and at least one condenser (105) housed in the containment vessel (101). The condenser includes a recovery unit (106) suitable for recovering the condensed water and a condenser link (110, 107, 111) to ensure the circulation of the water in a closed circuit between the reserve (102) and the condenser (105). The system further comprises means (112) of circulating the secondary water between the GV module (119) and the condenser (105), said means being activated without an external supply of electrical energy, when an operating parameter characteristic of excessive heating of the primary water reaches a certain threshold, such that the primary water heated by the core (113) and circulating in the GV module vaporises the secondary water, a hot link (123) ensuring the natural circulation of the steam from the GV module (119) to the condenser (105), the condenser (105) being designed to condense the steam circulating in the hot link (123) by means of thermal contact with the water circulating naturally in the condenser link (110, 107, 111), and a cold link (124) ensuring the circulation, by gravity, of the water from the recovery unit (106) to the GV module (119).
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