Patent · US Expired

Device for and method of removing the residual power from a fast-neutron nuclear reactor at shutdown

US5392324A · kind A · utility

2Cited by
6References
2Claims
0Family size

Assignee

Inventors

Key dates

Filing dateJul 1, 1993
Grant dateFeb 21, 1995
Priority date
Expiry dateJul 1, 2013

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02E30/30
  • WIPO fieldThermal processes and apparatus
  • WIPO sectorMechanical engineering

Abstract

The nuclear reactor includes a fuel core (5) inside a vessel (2) and a system (1) for cooling the core (5), in which a liquid metal circulates and on which is placed at least one steam generator (15). The steam generator includes a casing (15a) in which the liquid metal circulates, water-feed means (16) and means for heat exchange between the liquid metal and the feed water. The liquid metal is caused to circulate in the cooling system (1), the steam generator (15) not being fed with water and the liquid metal circulating in the steam generator (15) is cooled by the flow of a gas in contact with the casing (15a) of the steam generator (15). The cooling device includes a tubular element (25) placed around the casing (15a) of the steam generator and defining an annular space for a cooling gas to flow around the casing (15a).

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.