Compartmentalized safety coolant injection system
Patent
·
OSTI ID:5735794
A nuclear reactor system is described wherein pressurized water coolant is circulated from the reactor vessel through at least one reactor coolant supply loop that includes a reactor coolant pump and a steam generator, the system being housed in a containment building. The system consists of: a compartment that includes the reactor vessel; a reactor coolant loop compartment corresponding to each reactor coolant loop that includes the reactor coolant pump and steam generator of a single reactor coolant supply loop, the loop compartment having a water-tight base and sidewalls satisfactory to contain leakage from the coolant loop within the loop compartment; an emergency water storage tank within the reactor containment building that is in communication with the reactor coolant loop compartment through a spillway positioned to drain coolant leakage within the loop compartment above a given level, into the emergency water storage tank; a mump module that is connected to the emergency water storage tank and to the reactor vessel, the pump module being operative to draw coolant from the emergency water storage tank and supply it to the reactor vessel; and a containment building sump located in a lower portion of the containment building separate and normally isolated from the emergency water storage tank and loop compartment, normally serving as a fluid collecting reservoir for substantially all non-radioactive fluids drained in the containment building from outside the loop compartment.
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA
- Patent Number(s):
- US 4587080
- OSTI ID:
- 5735794
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
BUILDINGS
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SPRAY SYSTEMS
CONTAINMENT SYSTEMS
COOLANTS
COOLING SYSTEMS
DESIGN
DRAINAGE
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
HEAT EXCHANGERS
HYDROGEN COMPOUNDS
LEAKS
OXYGEN COMPOUNDS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR VESSELS
REACTORS
RHR SYSTEMS
SPACE HVAC SYSTEMS
STEAM GENERATORS
STORAGE FACILITIES
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
BUILDINGS
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SPRAY SYSTEMS
CONTAINMENT SYSTEMS
COOLANTS
COOLING SYSTEMS
DESIGN
DRAINAGE
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
HEAT EXCHANGERS
HYDROGEN COMPOUNDS
LEAKS
OXYGEN COMPOUNDS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR VESSELS
REACTORS
RHR SYSTEMS
SPACE HVAC SYSTEMS
STEAM GENERATORS
STORAGE FACILITIES
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS