Low pressure coolant injection modification for boiling water reactors

Patent · Tue May 25 04:00:00 EDT 1993

OSTI ID:6551542

Kelly, D M; Chi, Lawrence L; Stoll, C H; Sozzi, G L

A low pressure coolant injection system for a nuclear power facility of a variety having a boiling water reactor having a reactor core with normal operating pressure, first and second recirculation loops including respective first and second recirculation pumps and actuable discharge valves, a suppression pool water source, a condensate storage tank, and a safety system responsive to a loss-of-coolant accident to generate a safety output is described, comprising: first and second low pressure coolant injection pumps having suction inputs and discharge outputs and actuable to pump water; supply conduit means for coupling said suction inputs of said first and second low pressure coolant injection pumps in fluid flow communication with said suppression pool; first and second coolant injection conduits coupled with respective said discharge outputs of said first and second low pressure coolant injection pumps and to respective said first and second recirculation loops; first and second hydraulic resistance means within respective said first and second coolant injection conduits for restricting the flow of water coolant therein to a predetermined fluid rate selected to deliver a predetermined quantity of water coolant to each said first and second recirculation loops, said flow rate being selected as effective for carrying out the emergency cooling of said reactor core from one said coolant injection conduit; and control means responsive to said safety output for actuating said first and second low pressure coolant injection pumps.

• Assignee: General Electric Company, San Jose, CA (United States)
• Patent Number(s): US 5213755; A
• Application Number: PPN: US 7-678384
• OSTI ID: 6551542
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLOW RATE
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER SUPPLY