Patent Number: 053923235
Section: claims

1. A reactor pressure vessel of a nuclear power station, having at least one pipe socket connected to a feed-water supply line, in which a coaxial protective sleeve (thermal sleeve) expanding with changes in temperature is disposed, which with its outer end slidably abuts the pipe socket and with its inner end is connected to a feed-water distributing ring situated in the vessel, characterised in that a pipe section is inserted between the outer end of the pipe socket and the feed-water supply line, and in that in the pipe section are disposed bellows, which with one end are tightly connected to the outer end of the expanding protective sleeve and with their other end are tightly connected to the pipe section. 2. A vessel according to claim 1, characterised in that in the bellows is disposed a pipe, which at one end outside the bellows is connected to the pipe section and the other end of which extends into the outer end of the expanding protective sleeve. 3. A vessel according to claim 1, characterised in that the pipe section is extended opposite the pipe socket and at both its ends is provided with hollow conical parts, the tapered ends of which are adapted to the dimensions of the feed-water supply line and the end of the pipe socket respectively.