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U.S. Department of Energy
Office of Scientific and Technical Information

DEVICE FOR PRESSURE SUPPRESSION VAPOR CONTAINMENT

Patent ·
OSTI ID:4748900
The basic concept of the device described involves quenching of the steam issuing from a break in the primary reactor system in a water pool. The nuclear reactor and primary coolant system are completely contained in a vapor- tight pressure vessel. The inside of the pressure vessel is subdivided by a perforated horizontal partitionwall, the holes of which are normally sealed by diaphragms. The reactor and its primary coolant system are located in the lower part of the pressure vessel, which is dry. On the horizontal partition-wall in the upper part of the pressure vessel there is a pool of cold water. In the event of a primary system rupture, water and steam will discharge into the lower part of the pressure vessel. The resulting pressure in this part of the vessel will disrupt the diaphragms and the steam will flow through the holes into the pool. (Gmelin Institute)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-17-017514
OSTI ID:
4748900
Report Number(s):
DE 1142041
Country of Publication:
Germany
Language:
English

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