Jet pump-drive system for heat removal
Patent
·
OSTI ID:5765364
In a nuclear reactor having an electrically conductive metal coolant, this patent describes the reactor having an elevated operating temperature at which the metal coolant circulates through the reactor to remove heat therefrom and a safe temperature at which the reactor is shut down and is sufficiently cool for the flow of metal coolant through the reactor to be terminated. The improvement comprises a reactor cooling system that includes: a primary flow path for the metal coolant; a primary pump positioned in the primary flow path to provide a primary pumping force to the metal coolant; an auxiliary flow path for the metal coolant; the auxiliary flow path being parallel in flow to a portion of the primary flow path; a jet pump positioned in the primary flow path for the metal coolant; the auxiliary flow path including an inlet and a discharge connecting the auxiliary path to the primary path; the jet pump having a drive nozzle with the discharge from the auxiliary flow path positioned to feed metal coolant into the drive nozzle, and temperature responsive means positioned in the auxiliary flow path with the pump means operating at temperatures above the safe temperature of the reactor to increase the velocity of metal coolant in the auxiliary flow path and to drive the jet pump, whereby the temperature responsive pump means provides coolant flow through the reactor during shutdown of the reactor as the reactor and the metal coolant for the reactor undergo cooling from the reactor operating temperature down to the safe temperature where coolant flow through the reactor may be terminated.
- Assignee:
- National Aeronautics and Space Administration, Washington, DC
- Patent Number(s):
- US 4699754
- OSTI ID:
- 5765364
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
COOLANTS
COOLING
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
JETS
MECHANICS
METALS
PRIMARY COOLANT CIRCUITS
PUMPING
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SOLIDS FLOW
THERMODYNAMICS
220200* -- Nuclear Reactor Technology-- Components & Accessories
COOLANTS
COOLING
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
JETS
MECHANICS
METALS
PRIMARY COOLANT CIRCUITS
PUMPING
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SOLIDS FLOW
THERMODYNAMICS