SU1649104A1 - Method for operation of double-contour nuclear power plant with water-moderated reactor - Google Patents

Abstract

The invention relates to nuclear energy and can be used on double circuit power plants with water-cooled power reactors - ;. In order to increase the efficiency and reliability of nuclear power plants, instead of a steam generator, a water-based heat exchanger 1 is used and the secondary circuit water is heated therein at a pressure excluding its vaporization, and then part of the water from the water-heat exchanger is fed to the hydro steam turbine 2 for adiabatic expansion with the subsequent separation in the separator 3, the steam gon of the mixture formed in it into composite phases, and the vapor phase through the superheater 7 is fed to the input of the steam turbine, in cylinders 4-6 o, the medium and low pressures of which the steam expands in the area in

Description

states corresponding to superheated steam, due to the use of double intermediate superheating of steam and conjugation of the parameters of the initial and intermediate superheating of steam, carried out by the corresponding flows of heated thieves from the water-based heat exchanger 1 with their subsequent injection into. return line of a water-to-water heat exchanger 1. Steam condensate of a technical technical college is fed through a regenerative heaters 11-13 to a separator.

3 for mixing with separating water, and the total flow of water using the feed pump 16 is fed from separator 3 to the inlet of the water-water heat exchanger 1. The proposed method allows you to directly connect a hot water battery to the water-water heat exchanger 1 and the most rationalize peak power production in a steam power plant with a steam battery. 2 Il.

The invention relates to nuclear energy and can be used in a dual-circuit water-cooled power reactor.

The aim of the invention is to increase the efficiency and reliability of the operation of a nuclear power plant.

FIG. 1 shows a diagram of a nuclear power plant in T-S coordinates; in fig. 2 is a diagram of a nuclear power plant that implements this method of operation.

The nuclear power plant contains a water heat exchanger 1, a hydro steam turbine 2, a separator 3, a steam turbine consisting of high, medium and low cylinders 4–6, respectively, a steam superheater 7, the steam inlet of which is connected to the steam outlet of the separator 3, and the steam one the outlet is with an inlet of a high pressure cylinder 4, intermediate steam heaters 8 and 9, whose steam outputs are connected to the inlet of the cylinder 5 of medium pressure and to the inlet of the cylinder-6 of low pressure, respectively, condenser 10, regenerative preheater and 11 low pressure, deaerator 12, high pressure regenerative preheaters 13, condensate pump 14, feed pumps 15 and 16, and pump 17 for pumping heating water flows from the superheaters 7-9 to the return line of the water heat exchanger 1.

The method of operation of a nuclear power plant is carried out as follows.

The working medium — water at the initial pressure in the RF cycle is heated in a water-based heat exchanger 1 to a temperature equal to or close to the saturation temperature (process P – H at

FIG. 1) due to the supply of heat to the water from the coolant that entered the heat exchanger 1 from the reactor.

Part of the heated water in the amount of sgpt under Pressure PH n temperature

Tm from the heat exchanger 1 enters the hydro steam turbine 2, where it expands to a certain pressure P, and the steam content Xc (process H – C in FIG. 1). The resulting vapor-liquid mixture then enters the separator 3, in which the mixture is divided into constituent phases. The separated steam from the separator 3 enters the superheater 7,

it is heated in it to the temperature Tflfl (process g - 1 in Fig. 1) due to the supply of heat to the steam from the water entering the surface superheater from the water-water heat exchanger

1, and is directed to the high-pressure cylinder 4 of the steam turbine, where it expands from the pressure D ° to the pressure P in the region of the superheated steam state (process 1 - C1 in Fig. 1).

From cylinder 4, steam is directed to intermediate chamber, 8, .a after overheating up to TPP (process C1-2

Fig. 1) and expansion in the cylinder 5 of the medium pressure in the state of superheated steam (process 2-C2 in Fig. 1) the steam is subjected to secondary re-heating in the superheater 9 (process C2-3 in Fig. 1), from which steam enters the low-pressure cylinder 6 of the steam turbine. In the steam superheaters 8 and 9, the water from the heat exchanger 1 is also used as the heating medium. After

four.

Compiled by Y.Radin. Editor A.Makovska Techred M. Morgantal

Order 1505

Circulation 330

VNIIPI State Committee for Inventions and Discoveries at the State Committee on Science and Technology of the USSR 113035, Moscow, Zh-35, 4/5 Raushsk Nab.

3 T,

PP

1

S

- $ Corrector T.Paly

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Claims (1)

Claim The way the double-circuit atom separator works, and the water released in the separator is returned to the water-to-water heat exchanger, and the other stream is fed to a power plant with a water-to-water power reactor in the primary circuit and a steam turbine installation with at least one heating medium transfer to a steam superheater 25 to the steam turbine generators, after which they are also returned to the water / water heat exchanger. FIG. 1