RU1351448C - Boiling nuclear reactor for superheating foam - Google Patents

Abstract

The invention relates to nuclear technology and can be used in nuclear power plants and transport installations with water-cooled reactors. The aim of the invention is to increase the efficiency of a boiling nuclear reactor by reducing energy consumption for pumping a working fluid. The boiling nuclear reactor contains a multiple circulation loop of the heating coolant, in which a steam generator 5 and a feed water heater 6 are included in parallel with the superheater 7. The primary coolant is heated and partially evaporated in a boiling core 2, from where water enters the steam generator 5 and heater 6, where it gives up part of its heat, and then is returned by pump 9 to the inlet of the boiling core 2. Separated in the steam to the pensioner 3, the steam of the first circuit overheats in the overheating core 4, enters the superheater 7, where it gives off its heat, condenses and returns to the inlet of the boiling core 2.2 by the condensate pump. 2 Il. i (L C her SP 4 J 00

Description

AND; obkrtrn does not belong to atomic engineering and can be used in atomic power plants (somn, 1kh e; hectrost stations and transport-HF.ix installations with water-water reactors).

The aim of the invention is to increase the efficiency of a boiling nuclear reactor by reducing energy costs for pumping body work,

Fig. 1 is a diagram of a double-circuit boiling water reactor for superheating steam with forced circulation of the heating fluid, and Fig. 2 is the same, with natural circulation of the heating fluid in the multiple circulation section of the heating fluid. The boiling nuclear reactor with forced circulation contains (Fig. 1) case 1, in which the circuit

the boiling active zone 2, the steam compensator 3 and the overheating active zone 4, the steam generator 5 and the feed water superheater 6 included in the multiple circulation circuit of the heating coolant parallel to the superheater 7, the condensate transfer pump 8 and the pump for the condensate transfer 9 of the multiple circulation circuit (CMC ) heating medium. In addition to the above elements, except for the pump 9, the CMC boiling reactor with natural circulation contains (Fig. 2) an elevated section 10 of the multiple circulation circuit of the heating fluid, channel .1 1 of the overheated steam outlet, made like a pipe in a pipe and annular cavity 12, where the superheater 7. is located.

The proposed reactor operates as follows.

The primary coolant is heated and partially evaporated in the boiling core 2 (Fig. 1), from where water enters the steam generator 5 and the feed water heater 6 where it gives up part of its heat, and then the KJttI pump 9 returns to the boiling core 2. The steam of the first circuit separated in the steam compensator 3 overheats in the overheating core 4, enters the superheater 7, where it gives off its heat, condenses and returns to the inlet of the boiling core 2 with the condensate transfer pump 8. In a boiling nuclear reactor D of FIG. 2 calipers 1y1 coolant in the primary circuit: boiling active

5 s after heating - due to rl5zone 2 - steam generator. The carrier carries out a density nostal of the coolant of the lifting and lowering parts of the reactor. From the divided steam from the steam box of the shaker 3 along the annular gap k; 5ill 11 of the outlet of the superheated steam to the steam in the lifting section K1-P1, it enters the overheating actress zone 4, where it overheats and enters the annular cavity through the central part of the channel 11 12 to the pipe system of the superheater 7. Overheating of the steam of the second circuit, the heating medium condenses and the condensate transfer pumps 8 return to the lower part of the boiling nuclear reactor, i.e. at the entrance to the boiling core 2. I overheat 0

5

B

of the heating reactor core of FIG. 2 are located inside the housing 1.

Parallel connection of a steam generator with a feedwater heater and a superheater in this boiling nuclear reactor for superheating steam leads to a decrease in the required flow rates of the heating fluid (both total and individual to the superheater and to the boiling zone), due to the direct connection of the flow rate of the generated steam with a flow rate of water circulating through the boiling core, which is used to heat and evaporate the secondary water.

This circumstance (lowering the required coolant flow rates) made it possible, in addition to increasing the cost-effectiveness (reducing the energy consumption for pumping media), to use the driving pressure of natural circulation in the circuit of multiple circulation of the heating coolant reactor in acceptable overall dimensions.

Claims (1)

The claims 0 5 A boiling nuclear reactor for superheating steam, comprising a housing boiling and overheating active zones, a multiple circulation loop of a heating coolant, a steam generator with a feed water heater, a superheater and a condensate transfer pump, characterized in that, in order to increase the efficiency of the reactor by reducing for 0 . energy expenditures for prefixing the working fluid, a steam generator and preheating of the nutrient hearth switch ((s n loop of repeated circulation of the heated heat transfer steam. to a superheater, moreover, the sodium nitride branch of the transfer pump is connected to the inlet of the boiling core.