System for removing the residual power of a pressurised water nuclear reactor
US10255999B2 · kind B2 · utility
Assignee
Inventors
Key dates
| Filing date | Jan 17, 2013 |
| Grant date | Apr 9, 2019 |
| Priority date | — |
| Expiry date | Mar 6, 2036 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A system for removing the residual power of a pressurized water nuclear reactor, includes a reserve of water, a steam generator, wherein the primary water heated by the core either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and a condenser housed in the containment vessel. The condenser includes a recovery unit for recovering the condensed water and a condenser link to ensure the circulation of water in a closed circuit between the reserve and the condenser. The system further includes a device for circulating the secondary water between the steam generator and the condenser, the device 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 and circulating in the steam generator vaporizes the secondary water.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.