DE1201499B - Nuclear power plant with steam-cooled nuclear reactor - Google Patents

Description

FEDERAL REPUBLIC OF GERMANY

GERMAN

PATENT OFFICE

EDITORIAL

Int. Cl .:

G21d

German class: 21g-21/24

Number: 1201499

File number: S 79736 VIII c / 21 g

Filing date: June 1, 1962

Opening day: September 23, 1965

The invention relates to a nuclear power plant with a steam-cooled nuclear reactor, in which the steam in the reactor is superheated and the exiting steam is split into two streams, one of which is the one in a first circuit through a heat exchanger equipped with a steam generator and back to the reactor and the other in a second cycle through a two stage Turbine, a condenser, the steam generating device of said heat exchanger and also leads back into the reactor. The steam used to cool the nuclear reactor is therefore partially relaxed in a two-stage turbine and thus does work.

Nuclear power plants of this type are known in which the work-performing partial stream of the steam heated again after relaxation and then in a mixing device with the other, the heating performing partial steam flow is mixed. This mixture is then put into the reactor by means of returned to a conveyor. In another known nuclear power plant, the Partial steam flow performing work first in the high pressure part of a two-stage steam turbine and relaxes in this. Thereupon it is in a heat exchanger from the other partial steam flow heated again, whereupon it enters the second turbine stage, where it relaxes again. Both Partial steam flows are then combined again in a mixing device and by means of conveyed back into the reactor by a fan. In these nuclear power plants there is the disadvantage that the steam pressure in the reactor must not be kept below the maximum pressure in the power turbine or the like can, so that the returned steam in the reactor in this forced by means of a special Blower device or the like. Must be returned.

The object of the invention is to improve the known nuclear power plants and thereby to create the possibility of a mixture of the partial steam flows before re-entry into the To be able to do without the reactor.

Therefore, according to the invention, a nuclear power plant of the type described at the outset is proposed in which the low pressure stage of the turbine, the condenser, the steam generating device, a superheater device also arranged in the heat exchanger and the high pressure stage of the turbine are flow-connected in series in the second circuit and in which the expanded steam from the high-pressure stage of the Tur nuclear power plant with steam-cooled
Nuclear reactor

Applicant:

Societe Rateau S.A., Paris

Representative:

Dr.-Ing. Dr. jur. F. Redies,

Dr. rer. nat. B. Redies and

Dr. rer. nat. D. Türk, patent attorneys,

Opladen, Rennbaumstr. 27

Named as inventor:
Roger Jean Imbert, Paris;
Jacques Pierre Chaboseau,
Brevannes, Seine-et-Oise (France)

Claimed priority:

France of June 21, 1961 (868 644)

bine and the steam of the first circuit emerging from the heat exchanger separated from one another in flow back through the reactor. This gives you the opportunity to reduce the vapor pressure in the reactor to keep the maximum pressure of the power turbine and the high pressure stage of the turbine with an easy to operate below the outlet temperature of the reactor lying temperature, however, the direct feeding of the low-pressure stage of the turbine with part of the output from the reactor Steam is retained. The overheating of the work performing partial steam flow between the Both turbine stages can take place in such a way that the superheated partial flow has a higher pressure possesses than the other partial steam flow that overheats it. Therefore, the superheated partial steam flow in the high pressure stage of the turbine do work and after the corresponding relaxation still untei a higher pressure than the pressure prevailing in the reactor flow back into them, so that no mixing devices and conveying fans are required to return the steam streams to the reactor.

In the drawing is a schematic embodiment of a nuclear power plant with steam-cooled Nuclear reactor according to the invention shown.

Such a plant essentially consists of a nuclear reactor a, a heat exchanger g,

509 688/372

a turbine with a high pressure turbine stage b _v, a medium and low pressure turbine stage b ₂ , a consumer device c, for example an alternator, and a blower driven by a motor / h. A pipeline emanating from the reactor α divides into two branches, of which branch J ₁ feeds the low-pressure stage of the turbine directly and branch / is connected to the heat exchanger g. A line f ₂ connects this heat exchanger with the fan h, which is connected to the reactor via a line / ₂ "which opens at a _2. The output of the medium-pressure turbine stage b ₂ leads to a condenser d, which is followed by a feed water pump e A water collector s collects the water from the condenser. Furthermore, steam extraction lines from the individual turbine stages open into the condenser d . A line J ₁ ' leads to the evaporator ^ ₁ arranged within the heat exchanger g , followed by a superheater bundle g _2. The high-pressure turbine stage b _x is fed via a line f _x ″ , which comes from the evaporator and establishes the connection to a superheater bundle g ₂ in the heat exchanger g . A line Z ₁ '"connects the outlet of the high-pressure turbine stage b _x with the reactor and opens into this at ö ₃ .

In the superheater bundle g ₂ , superheating of a steam is carried out which is under a pressure which is higher than that which prevails inside the reactor. The steam emerging from the high-pressure turbine can therefore flow back directly to the reactor.

Such an installation enables the advantages of cooling the reactor with a gaseous medium and that of the immediate expansion of at least part of the same agent in a turbine to connect with each other. Furthermore, this makes it possible to use the reactor with only a fraction of the to apply maximum pressure in the circuit and at the same time to increase this maximum pressure, as it only acts on conventional facilities. The resulting increase in Efficiency must also be taken into account.

As a modification to the above, the motor / motor driving the fan h can be replaced by a turbine, which is preferably fed by a steam flow.

By replacing the alternator c with a screw, it is possible to change the arrangement also apply to vehicles. Finally, the subdivision of the heating of the condensed water, the The feed water pump is driven by a turbine or the turbine is divided into three pressure stages possible.

Claims (1)

Claim: Nuclear power plant with steam-cooled nuclear reactor, in which the steam in the reactor is superheated and the emerging steam is divided into two streams, one of which in a first circuit through a heat exchanger equipped with a steam generator and back into the reactor and the other through a second circuit a two-stage turbine, a condenser, the steam generating device of said heat exchanger and also leads back into the reactor, characterized in that in the second circuit the low-pressure stage (b ₂ ) of the turbine, the condenser (d), the steam generating device (gj), also a in the heat exchanger (g) arranged superheater device (g ₂ ) and the high pressure stage Q) ₁ ) of the turbine are connected in series in terms of flow and that the expanded steam from the high pressure stage of the turbine and the steam exiting the heat exchanger of the first circuit separately from one another into the reactor ( a) to backflow. Considered publications:
Belgian patent specification No. 571 011;
Nuclear Engineering, June 1961, pp. 235 to 244. 1 sheet of drawings 509 683/372 9.65 © Bundesdruckerei Berlin