Vessel steam relief system for a nuclear reactor. [PWR]

Patent · Tue Apr 26 04:00:00 EDT 1977

OSTI ID:7221100

Grubelich, F T

A system is provided for the relief of excess pressure from the region above the nuclear reactor core to the cold leg on the occurrence of a loss of coolant accident. This system includes a series of passages connecting the annulus surrounding the exterior of the core barrel with the interior of the outlet nozzle or with the plenum above the reactor core. A flow blocking obstruction, such as a seal band, is held in a flow blocking position by the differential pressure experienced during normal operation of the reactor between the exterior of the core barrel and the exit region of the reactor core. Reversal of the differential pressure, which may be expected upon the occurrence of a loss of coolant accident, removes the flow blocking obstruction to permit the relief of excess pressure which may result at the outlet end of the reactor core. 10 claims, 5 figures.

• Assignee: Combustion Engineering, Inc.
• Patent Number(s): US 4019955
• OSTI ID: 7221100
• 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
ACCIDENTS
COOLING SYSTEMS
LOSS OF COOLANT
PRESSURE SUPPRESSION
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS