Patent Number: 040574679
Section: summary

BACKGROUND OF THE INVENTION The present invention concerns a pressurized-water reactor whose primary cooling system gives off its heat within a pressure vessel to a steam generator within the vessel and which is inserted between the reactor core and the intake space of the circulating pumps, i.e., in the cold leg of the main coolant loop. This pressurized-water reactor, whose primary cooling system is normally operated with forced circulation, is particularly well suited for ship propulsion and stationary installations of smaller power rating. In order to avoid damage to the circulating pumps of the primary cooling system due to cavitation, particularly in the case of rapid load changes, these pumps should operate in a zone as cool as possible, of the primary cooling system. If these pumps operate at close to the boiling temperature of the pressurized-water coolant, a small brief lowering of the normal pressure is sufficient to cause the water in the pump housings to boil. The steam bubbles produced in this manner collapse during any subsequent pressure increase and cause destruction at the pump internals in a locally closely confined area. Particularly exposed in this respect are circulating pumps which, for reasons of better maintenance and inspection, are preferably located above the core and steam generator, because as compared to pumps located underneath, such pumps receive a considerably smaller inflow head or hydrostatic pressure and therefore have a greater tendency toward cavitation. These problems are often avoided by means of an external pressurizer for the coolant which, however, requires much space and is expensive. A typical example for a shipboard reactor proven in practice is represented by the propulsion plant of the nuclear vessel "OTTO HAHN". In this arrangement, with a pump located at the bottom of the pressure vessel, the desired flow can be realized with water as cold as possible ahead of the pump and with a considerable inflow head to the pump. If, with the design the same otherwise, the circulating pump or pumps are arranged at the upper end of the pressure vessel, e.g., in its closure head end, the pumps not only are approached by the hotter primary coolant, but the inflow head is at the same time also reduced considerably. In the disclosures of the German Offenlegungsschrift No. 22 27 895 (U.S. Ser. No. 153,304, filed June 15, 1971 now U.S. Pat. 3,888,734) the described problems with the circulating pumps are avoided by using a very large and, therefore, also expensive external pressurizer. In this external pressurizer, the pressure in the pressure vessel is adjusted to the desired level by controlled heating of the water in the pressurizer or injection of cold water. In the same disclosures, it is proposed to support all the internals in the pressure vessel at the vessel's upper closure head, so that for every refueling and every inspection or maintenance action on internals in the pressure vessel, practically all the internals must be removed together from the pressure vessel, with their considerable weight. Such refueling is necessary about every one to two years, while a routine inspection is necessary only every 8 years. It is therefore desirable that the fuel assemblies can be exchanged without the necessity to remove the steam generator. In order to obtain the desired flow path from the reactor through the heat exchanger to the circulating pump, it is proposed in the same disclosures to have the flow through the reactor core go in normal operation from top to bottom. This flow path results, in the case of load changes or at low load as well as in the event of a failure of the circulating pumps, in very confusing flow conditions in the reactor core which should be avoided. An object of the present invention is to provide a pressurized-water reactor whose primary cooling system gives off its heat within a pressure vessel, to a steam generator which within the pressure vessel is inserted between the reactor core and the suction space of the circulating pumps, and which can be disassembled without destruction for inspecting the pressure vessel. A specific object of the present invention is to provide an arrangement of a steam generator which can take up the decay heat of the reactor core through natural circulation in the event of a failure of the circulating pumps and lowering of the water level. A further object of the present invention is to provide a pressurized-water reactor whose internals in the pressure vessel, fabricated from austenitic metal, can expand freely relative to the pressure vessel, which is made of ferritic metal. SUMMARY OF THE INVENTION According to the present invention, the annular steam generator is arranged in a hollow cylindrical housing, which is closed on all sides excepting for openings for directing the coolant flow, and which is supported on the upper end of the pressure vessel via a hollow ring supported by the vessel; a core support structure with an assembled reactor core being likewise suspended by this housing; and this housing being radially braced at the lower end via several vertically sliding surfaces against the inner wall of the pressure vessel. With this arrangement, all important internals within vessel are suspended in the pressure vessel with the exception of the pumps and the feed water and steam nozzles, by the housing, the hollow ring being firmly clamped at the upper end of the pressure vessel between a step or internal flange formed by the pressure vessel and the inner periphery of closure head of the pressure vessel. This housing is made of austenitic metal but can freely expand downward within the ferritic metal pressure vessel, and it is supported at its lower end at several places, vertically sliding at the inner wall of the pressure vessel, so that forces in the horizontal direction can be taken up by the pressure vessel. The core housing is fastened on the one hand at the already described steam generator housing and can be centered with its lower end by a likewise vertically sliding post, so that is follows all expansions of the housing in the axial direction and transmits in the horizontal direction the occurring forces to the pressure vessel. In this manner, all welded steam for lugs or other fastening means, which cannot be checked, are avoided at the pressure vessel and the ultrasonic testing of the pressure vessel wall is facilitated. All the pressure vessel internals may be fabricated of the same material, so that stresses induced by unequal expansion are eliminated. The arrangement of the steam generator in a cylindrical housing closed on all sides not only has the advantage that the thin tubes of this steam generator can be protected better against vibrations, but it also protects this steam generator against damage during installation and disassembly. The hollow ring of box-like cross section serves, on the one hand, to stiffen the steam generator housing with all internals attached thereto, and, on the other hand, serves to guide the flow. The inclined positions, which are unavoidable in a shipboard reactor, do not cause trouble with the water circulation either in normal operation or in the event of a failure of the pumps, as they can have an effect only in the relatively narrow, ring-shaped steam generator housing. Thus, the structural height of the pressure vessel above the pumps can be decreased considerably. In a further embodiment of the invention, the hollow ring forms the pressure chamber of the primary circulation pumps and is penetrated by several inlet sections which communicate with the intake space of the circulating pumps. In this manner, each pump has its own inlet section favorably shaped from a flow point of view; all the pumps together, however, push into the hollow ring of box-shaped cross section which has several openings at its underside, so that the primary cooling water can flow to the reactor core, distributed uniformly over the circumference, also in the event of a failure of a pump.