Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Emergency core coolant systems
Reexamination Certificate
2005-03-08
2005-03-08
Keith, Jack (Department: 3641)
Induced nuclear reactions: processes, systems, and elements
Reactor protection or damage prevention
Emergency core coolant systems
C376S277000, C376S247000, C376S258000
Reexamination Certificate
active
06865244
ABSTRACT:
In order to allow a reliable and passive external cooling of a reactor pressure vessel of a boiling water reactor, outside the reactor pressure vessel a differential-pressure measurement pipe is provided and has a first and a second pipe leg which are connected to one another above a critical filling level. The first pipe leg is connected at the height of the critical filling level to the interior of the reactor pressure vessel. In a normal operating state, the differential-pressure measurement pipe is filled completely with water. In the event of the undershooting of the critical filling level, the water flows automatically out of the first pipe leg. As a result, the differential pressure between the two pipe legs rises, the differential pressure being detected by a measurement device via which the flooding of the exterior is then brought about.
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Werner Brettschuch et al.: “SWR 1000—der Siedewasserreaktor der Zukunft” [SWR 1000—the boiling water reactor of the future],Siemens Power Journal, 2/96, pp. 18-22.
Framatome ANP GmbH
Greenberg Laurence A.
Keith Jack
Locher Ralph E.
Stemer Werner H.
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