Forced-circulation reactor with enhanced natural circulation
Patent
·
OSTI ID:7232950
This patent describes a forced-circulation dual-phase reactor. It comprises a reactor vessel; a reactor core disposed within the vessel and defining a core inlet plenum below the core; a chimney means disposed above the core for guiding fluid exiting upward from the core along a substantially vertical path so as to support a steam/water column therein; a fluid return path from the chimney means to the core inlet plenum; pump means for controllably enhancing a pressure differential along the fluid return path so as to urge fluid along the fluid return path for recirculating fluid through the core; and valve means for opening a bypass for fluid to flow from the fluid return path to the core inlet plenum without passing through the pump means.
- Assignee:
- General Electric Co., San Jose, CA (United States)
- Patent Number(s):
- A; US 5120493
- Application Number:
- PPN: US 7-716024
- OSTI ID:
- 7232950
- Country of Publication:
- United States
- Language:
- English
Similar Records
BWR natural steam separator
BWR parallel flow recirculation system
Enhancing load-following and/or spectral shift capability in single-sparger natural circulation boiling water reactors
Patent
·
Tue Apr 21 00:00:00 EDT 1992
·
OSTI ID:5064983
BWR parallel flow recirculation system
Patent
·
Mon Jan 20 23:00:00 EST 1992
·
OSTI ID:5405251
Enhancing load-following and/or spectral shift capability in single-sparger natural circulation boiling water reactors
Patent
·
Mon Mar 30 23:00:00 EST 1992
·
OSTI ID:5178131
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CONVECTION
COOLING SYSTEMS
DUAL CYCLE COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FORCED CONVECTION
HEAT TRANSFER
MASS TRANSFER
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
THERMAL POWER PLANTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CONVECTION
COOLING SYSTEMS
DUAL CYCLE COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FORCED CONVECTION
HEAT TRANSFER
MASS TRANSFER
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
THERMAL POWER PLANTS