Device and method for cooling a reactor pressure vessel of a boiling water reactor plant
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.
1. A device for cooling a reactor pressure vessel of a boiling water reactor plant, the device comprising:
a differential-pressure measurement pipe disposed outside the reactor pressure vessel, said differential-pressure measurement pipe having a first pipe leg and a second pipe leg connected to one another above a critical filling level of the reactor pressure vessel, said first pipe leg being flow-connected at a height of the critical filling level to an interior of the reactor pressure vessel; and
a measurement device coupled to said differential-pressure measurement pipe for detecting a differential pressure existing between said first and second pipe legs, said measurement device initiating a cooling of the reactor pressure vessel in an event of an overshooting of a triggering differential pressure.
2. The device according to claim 1 , further comprising a jacket pipe surrounding at least a lower region, near the critical filling level, of said first pipe leg, said jacket pipe connected in a communicating manner to the interior of the reactor pressure vessel.
3. The device according to claim 2 , wherein said jacket pipe has a first flow path and a second flow path, said jacket pipe connected to the interior of the reactor pressure vessel below the critical filling level through said first flow path and to the interior above the critical filling level through said second flow path.
4. The device according to claim 2 , wherein said first pipe leg has a lower end with an opening formed therein and disposed within said jacket pipe at a height of the critical filling level.
5. The device according to claim 2 , further comprising a riser pipe connected to said differential-pressure measurement pipe, said riser pipe disposed outside of the reactor pressure vessel and connected in a communicating manner to the interior of the reactor pressure vessel.
6. The device according to claim 5 , further comprising a jacket pipe having two flow paths connected to said riser pipe.
7. The device according to claim 1 , further comprising venting disposed at a highest point of said differential-pressure measurement pipe.
8. The device according to claim 1 , further comprising;
a flood line issuing into an exterior area disposed outside and around the reactor pressure vessel; and
a shutoff valve disposed in said flood line, said measurement device activating said shutoff valve.
9. The device according to claim 8 , further comprising:
a compressed-gas line connected to said shutoff valve for activating said shutoff valve; and
a pneumatic valve connected to said measurement device and disposed in said compressed-gas line.
10. The device according to claim 1 , further comprising a first measurement line flow-connecting said first pipe leg to said measurement device and a second measurement line flow-connecting said second pipe leg to said measurement device.
11. A device for cooling a reactor pressure vessel of a boiling water reactor plant, the device comprising:
a differential-pressure measurement pipe disposed outside the reactor pressure vessel, said differential-pressure measurement pipe having a first pipe leg and a second pipe leg connected to one another above a critical filling level of the reactor pressure vessel, said first pipe leg being flow-connected at a height of the critical filling level to an interior of the reactor pressure vessel;
a jacket pipe surrounding at least a lower region, near the critical filling level, of said first pipe leg, said jacket pipe connected in a communicating manner to the interior of the reactor pressure vessel for establishing a filling level substantially corresponding to a filling level prevailing in the reactor pressure vessel; and
a measurement device coupled to said differential-pressure measurement pipe for detecting a differential pressure existing between said first and second pipe legs, said measurement device initiating a cooling of the reactor pressure vessel in an event of an overshooting of a triggering differential pressure.