Nuclear reactor coolant recirculation
A system is described for forcing a liquid water coolant to recirculate through an unshrouded nuclear core in a pressure vessel. The core includes an array of spaced fuel assemblies supported between a lower core support member and an upper core support member. Each of the fuel assemblies is fitted with a tubular flow channel for containing water coolant flowing therethrough; an annular lower support ring attached to the pressure vessel and connected to the lower core support member for support thereof. The lower core support member, the lower support ring and the lower part of the pressure vessel form a lower plenum wherein the coolant can be pressurized. An upper support ring is attached to the pressure vessel and connected to the upper core support member. A space in the pressure vessel above the upper core support member forms an upper plenum for containing water coolant. Coolant pressurizers within the pressure vessel each have a coolant inlet and a coolant outlet and vertically oriented elongated coolant conducts conduits positioned in radially spaced relation between the core and the inner wall of the pressure vessel and extends from the upper plenum to the lower plenum. Each is connected to the coolant inlet of a respective one of the coolant pressurizers and each penetrates the upper support ring for conducting coolant from the upper plenum to the coolant inlet. The coolant outlet of each coolant pressurizer is in fluid communication with the lower plenum for pressurizing the coolant therein. Primary coolant passages are through the lower support member for admitting a pressurized coolant from the lower plenum into the fuel assemblies; and coolant outlet means at the upper end of the core are for discharging liquid coolant from the core to the upper plenum whereby the coolant is recirculated from the lower plenum, through the core to the upper plenum and back to the lower plenum.
- Assignee:
- General Electric Co., San Jose, CA
- Patent Number(s):
- US 4696792
- OSTI ID:
- 5836858
- Country of Publication:
- United States
- Language:
- English
Similar Records
BWR parallel flow recirculation system
Conceptual Design of a Reactor Pressure Vessel and its Internals for a HPLWR
Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CIRCULATING SYSTEMS
CONTAINERS
COOLANTS
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
LIQUID FLOW
MECHANICS
OPERATION
PRESSURE VESSELS
PRESSURIZING
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS