Vessel steam relief system for a nuclear reactor

Details Vessel steam relief system for a nuclear reactor Vessel steam relief system for a nuclear reactor

1975-12-31

1977-04-26

Engle, Samuel W.

176 50, 176 87, G21C 900, G21C 1524

Patent

active

040199550

ABSTRACT:
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.

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