Concentric pipe loop arrangement for pressurized water nuclear reactors

Patent · Tue Mar 29 04:00:00 EST 1988

OSTI ID:5159957

Veronesi, L

In a nuclear reactor primary coolant system having a reactor vessel, a steam generator, and a reactor coolant pump, a pipe loop arrangement is described comprising: a first pipe connecting an outlet of the reactor vessel with an inlet of the steam generator whereby hot reactor coolant is ducted to the steam generator; a second pipe substantially concentrically mounted within the first pipe forming an annulus therebetween; means for flow connecting a steam generator outlet with an inlet to the pump; means for flow connecting an outlet of the pump with the second pipe; and means for flow connecting the second pipe with inlets to the reactor vessel whereby cooled reactor coolant is ducted from the steam generator to the reactor vessel comprising a hollow Y-shaped transition piece welded at one end to the second pipe and having two other ends each slidingly engaged with a respective inlet to the reactor vessel whereby the second pipe is maintained in the concentric arrangement with the first pipe; and, means for smoothing the flow of hot reactor coolant around the transition piece and into the first pipe.

• Assignee: Westinghouse Electric Corp., Pittsburgh, PA
• Patent Number(s): US 4734250
• OSTI ID: 5159957
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CONTAINERS
CONTROL EQUIPMENT
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
EQUIPMENT
FABRICATION
FLOW REGULATORS
FLUID MECHANICS
HYDRAULICS
JOINING
MECHANICS
PIPES
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR VESSELS
REACTORS
STEAM GENERATORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDING