Patent · US Expired

Secondary-side residual-heat removal system for pressurized-water nuclear reactors

US5414743A · kind A · utility

8Cited by
2References
6Claims
0Family size

Assignee

Inventors

Key dates

Filing dateFeb 14, 1994
Grant dateMay 9, 1995
Priority date
Expiry dateFeb 14, 2014

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02E30/30
  • WIPO fieldEngines, pumps, turbines
  • WIPO sectorMechanical engineering

Abstract

A secondary-side residual-heat removal system for a pressurized-water reactor removes residual heat through a secondary side of a steam generator in certain modes of operation and malfunction. For this purpose, the respective steam generator has a connection on a live-steam and feed-water side to a secondary side of a safety condenser. The connection on the feed-water side is led to a supply connection of a swirl or vortex chamber valve having a control connection which is connected to a feed-water line part on the pressure side, with a downgradient from a main feed-water pump, and the swirl or vortex chamber valve has an outlet which opens out into a feed-water inflow space of the steam generator. A tertiary side of the safety condenser is fed from a water reservoir disposed at a geodetically higher level. The steam being generated is discharged into the atmosphere through a blowing-off line, with a separating device if appropriate. Due to the geodetically higher configuration of the safety condenser in comparison with the steam generator, the energy transmission on the secondary side takes place by natural circulation.

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