Patent · US Expired

Nuclear reactor

US6718001B2 · kind B2 · utility

21Cited by
15References
6Claims
0Family size

Assignee

Inventors

Key dates

Filing dateAug 31, 2001
Grant dateApr 6, 2004
Priority date
Expiry dateAug 31, 2021

Classification

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

Abstract

In an indirect cycle nuclear reactor, a size of the reactor containment vessel is decreased by removing decay heat inside the reactor pressure vessel without using any active component to improve the economic feasibility. A main steam pipe communicating with a heat exchanger of the indirect cycle nuclear reactor is branched in a position upstream of a main steam isolation valve to connect the branched pipe to a heat exchanger in a pressure suppression pool through an isolation valve. A feed water pipe is also branched in a position upstream of an isolation valve to connect the branched pipe to the heat exchanger through the isolation valve. Decay heat is dissipated from the heat exchanger into the pressure suppression pool, and condensed water condensed by heat dissipation is returned to the heat exchanger to cool the inside of the pressure vessel. Heat in the pressure suppression pool is transferred from a condensing type heat exchanger to a heat dissipater outside a containment vessel to be dissipated to the outside of the containment vessel.

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