Nuclear reactor unit arranged in a cylindrical prestressed concrete pressure vessel and having a gas-cooled nuclear reactor

摘要

The invention relates to a nuclear reactor unit having a cylindrical prestressed concrete pressure vessel, having a gas-cooled nuclear reactor accommodated in a cavity of the pressure vessel, having, installed in vertical shafts in the pressure vessel, main heat exchangers and main circulators, auxiliary heat exchangers and auxiliary circulators, and having gas lines between the reactor cavity and the vertical shafts for guiding the hot gas and the cold gas. In this arrangement, each vertical shaft is connected to the reactor cavity by means of a hot gas line emanating from the lower region of the reactor cavity and of a cold gas line entering the upper region of the reactor cavity. The reactor cavity is arranged eccentrically, in a manner known per se, in the prestressed concrete pressure vessel in order to achieve smaller dimensions for the pressure vessel. A simplified design of the nuclear reactor unit is achieved in common with the guarantee of higher safety owing to the fact that the auxiliary heat exchangers, which take over the dissipation of afterheat in the event of accidents, are respectively arranged above one another in pairs in a manner known per se in one of the vertical shafts, the associated auxiliary circulators being provided at the top in case of the upper auxiliary heat exchangers and at the bottom in the case of the lower auxiliary heat exchangers, and that the cold gas from the lower auxiliary circulators is guided in each case through a gas line which is laid in parallel in concrete and enters the relevant vertical shaft in the region of the cold gas line.