CN214671852U

CN214671852U - System for high temperature gas cooled reactor nuclear power unit sliding pressure starts

Info

Publication number: CN214671852U
Application number: CN202120364693.8U
Authority: CN
Inventors: 马晓珑; 徐校飞; 陈立强; 常重喜; 余俨; 韩传高; 张瑞祥; 武方杰
Original assignee: Xian Thermal Power Research Institute Co Ltd
Current assignee: Xian Thermal Power Research Institute Co Ltd
Priority date: 2021-02-07
Filing date: 2021-02-07
Publication date: 2021-11-09
Anticipated expiration: 2031-02-07

Abstract

The utility model discloses a system for the sliding pressure starting of a nuclear power unit of a high temperature gas cooled reactor, which comprises a first valve group, a steam generator, a reactor and a steam-water separator; the outlet of the first valve group is connected with the first inlet of the steam generator, the first outlet of the steam generator is connected with the inlet of the steam-water separator, the outlet of the reactor is connected with the second inlet of the steam generator, and the second outlet of the steam generator is connected with the inlet of the reactor. In the starting stage of the utility model, the circulating water quantity of the evaporator is matched with the load of the reactor, so that too much steam heating is not needed to be invested in the initial stage, and the power consumption of the electric boiler is less; the water consumption and the heat consumption of the unit are relatively small in the starting process; the pressure, flow and temperature of water supply of the unit are matched with the load of the unit in the starting process, the control is easy, the change of the steam temperature and pressure is smooth, and the safety and stability of the operation of the unit are facilitated.

Description

System for high temperature gas cooled reactor nuclear power unit sliding pressure starts

Technical Field

The utility model belongs to the technical field of the nuclear power, concretely relates to system that high temperature air-cooled reactor nuclear power unit sliding pressure starts.

Background

The high temperature gas cooled reactor nuclear power unit constructed at present needs to keep pressure of about 14MPa of an evaporator at the initial starting stage of the unit, 36kg/s of circulating flow needs to be established in a secondary loop, and the unit always keeps 14MPa of constant pressure operation in the starting and operating processes. The current design has several problems:

(1) in the starting stage of the unit, the water supply of the evaporator can only be heated by supplying steam to the deaerator by the electric boiler, and the electric boiler has serious power consumption and poor economy due to large circulating water amount;

(2) the unit consumes a large amount of water and heat in the starting process;

(3) the difficulty of water supply pressure and flow control of the unit in the starting process is high, severe change of steam temperature is easily caused, and the safety and stability of unit operation are affected.

SUMMERY OF THE UTILITY MODEL

An object of the utility model is to provide a system that high temperature gas cooled piles nuclear power unit sliding pressure and start to the not enough of present unit system.

The utility model discloses a following technical scheme realizes:

a system for starting a nuclear power unit of a high-temperature gas cooled reactor in a sliding pressure mode comprises a first valve group, a steam generator, a reactor and a steam-water separator; the outlet of the first valve group is connected with the first inlet of the steam generator, the first outlet of the steam generator is connected with the inlet of the steam-water separator, the outlet of the reactor is connected with the second inlet of the steam generator, and the second outlet of the steam generator is connected with the inlet of the reactor.

The utility model discloses further improvement lies in, and first valve group comprises governing valve and stop valve, and the governing valve is used for controlling steam generator's the size of feedwater flow.

The utility model discloses further improvement lies in, the reactor passes through the coolant with the produced heat transfer of reactor for water and steam in the steam generator heat transfer pipe.

The utility model has the further improvement that the utility model also comprises a condenser and a steam turbine; the first outlet of the steam-water separator is divided into two streams, the first stream is connected to the inlet of the steam turbine, the outlet of the steam turbine is connected to the first inlet of the condenser, and the second outlet of the steam-water separator is connected to the third inlet of the condenser.

The utility model discloses further improvement lies in, still includes the second valve group, and the second export of catch water connects in the entry of second valve group, and the export of second valve group connects in the third entry of condenser.

The utility model discloses further improvement lies in, still includes the bypass control valve, and the second thigh of the first export of catch water connects in the entry of bypass control valve, and the export of bypass control valve connects in the second entry of condenser.

The utility model discloses at least, following profitable technological effect has:

the utility model provides a pair of system that nuclear power unit sliding pressure starts is piled to high temperature gas cooling has following several obvious advantages in the aspect:

(1) in the starting stage of the unit, the circulating water quantity of the evaporator is matched with the load of the reactor, so that too much steam is not required to be added for heating in the initial stage, and the electric boiler consumes less power;

(2) the water consumption and the heat consumption of the unit are relatively small in the starting process;

(3) the pressure, flow and temperature of water supply of the unit are matched with the load of the unit in the starting process, the control is easy, the change of the steam temperature and pressure is smooth, and the safety and stability of the operation of the unit are facilitated.

Drawings

Fig. 1 is a block diagram of a system for starting a nuclear power plant by sliding pressure in a high temperature gas cooled reactor.

Description of reference numerals:

1. the system comprises a first valve group, a second valve group, a steam generator, a first valve group, a second valve group, a steam-water separator, a second valve group, a steam turbine, a steam condenser, a steam turbine, a bypass regulating valve and a steam turbine, wherein the first valve group 2, the steam generator 3, the reactor 4, the steam-water separator 5, the second valve group 6, the steam condenser 7, the steam turbine 8 and the bypass regulating valve.

Detailed Description

The present invention will be described in further detail with reference to the accompanying drawings.

As shown in fig. 1, the utility model provides a system that high temperature gas cooled reactor nuclear power unit sliding pressure starts, including first valve group 1, steam generator 2, reactor 3, catch water 4, second valve group 5, condenser 6, steam turbine 7 and bypass control valve 8. The outlet of the first valve group 1 is connected with the first inlet of the steam generator 2, the first outlet of the steam generator 2 is connected with the inlet of the steam-water separator 4, the outlet of the reactor 3 is connected with the second inlet of the steam generator 2, and the second outlet of the steam generator 2 is connected with the inlet of the reactor 3. The first outlet of the steam-water separator 4 is divided into two parts, the first part is connected to the inlet of the steam turbine 7, the second part is connected to the inlet of the bypass regulating valve 8, the outlet of the bypass regulating valve 8 is connected to the second inlet of the condenser 6, the outlet of the steam turbine 7 is connected to the first inlet of the condenser 6, the second outlet of the steam-water separator 4 is connected to the inlet of the second valve group 5, and the outlet of the second valve group 5 is connected to the third inlet of the condenser 6.

Preferably, the first valve set 1 is composed of a regulating valve and a stop valve, and the regulating valve is used for controlling the feed water flow of the steam generator 2.

Preferably, the reactor 3 transfers heat generated by the reactor 3 to water and steam in the heat transfer tubes of the steam generator 2 through a coolant.

The utility model provides a pair of system that nuclear power unit sliding pressure started is piled to high temperature gas cooling, the during operation, including following step:

1) at the initial stage of starting the nuclear power unit, water is injected into the steam generator 2 under the control of a regulating valve of the first valve group 1, and water injected into the steam generator 2 enters the steam-water separator 4 through a first outlet of the steam generator 2;

2) when the steam generator 2 is filled with water and the water level of the steam-water separator 4 is visible, the water discharge of the steam-water separator 4 is controlled by the regulating valve of the second valve group 5 to maintain the normal water level of the steam-water separator 4;

3) the power of the reactor 3 is increased, the temperature of the coolant of the reactor 3 is increased, and the coolant of the reactor 3 transfers heat to water in the pipe of the steam generator 2 through the steam generator 2;

4) along with the further improvement of the power of the reactor 3, a first outlet of the steam generator 2 generates steam, a steam-water mixture is separated in a steam-water separator 4, water is discharged into a condenser 6 through a second valve group 5, and the steam enters the condenser 6 through a bypass regulating valve 8;

5) the pressure of the tube side of the steam generator 2 and the pressure in the steam-water separator 4 are controlled by controlling the bypass regulating valve 8, the steam temperature in the steam-water separator 4 rises along with the slow rise of the pressure, and the rising rate of the steam temperature in the steam-water separator is enabled to be not more than 10 ℃/h by controlling the pressure of the steam-water separator;

6) with the further increase of the power of the reactor 3, the first outlet of the steam generator 2 generates more steam, and the water amount is reduced until all the steam is changed into steam;

7) when the steam generated by the steam generator 2 meets the impulse requirement of the steam turbine 7, the steam enters the steam turbine 7, the steam turbine 7 operates under load, and the bypass regulating valve 8 is gradually closed until the steam is completely closed.

In addition, the steam pressure at the outlet of the steam generator 2 rises along with the rising of the power of the reactor 3, the load of the steam turbine 7 is synchronously adjusted along with the change of the power of the reactor 3, and the unit operates under the sliding pressure until the main steam pressure and the main steam temperature reach the rated values.

Claims

1. A system for starting a nuclear power unit of a high-temperature gas cooled reactor by sliding pressure is characterized by comprising a first valve group (1), a steam generator (2), a reactor (3) and a steam-water separator (4); the outlet of the first valve group (1) is connected with the first inlet of the steam generator (2), the first outlet of the steam generator (2) is connected with the inlet of the steam-water separator (4), the outlet of the reactor (3) is connected with the second inlet of the steam generator (2), and the second outlet of the steam generator (2) is connected with the inlet of the reactor (3).

2. The system for the sliding pressure starting of the nuclear power plant of the high temperature gas cooled reactor according to claim 1, wherein the first valve set (1) is composed of a regulating valve and a stop valve, and the regulating valve is used for controlling the feed water flow of the steam generator (2).

3. The system for the skid-pressure startup of the nuclear power plant of the high temperature gas cooled reactor according to claim 1, wherein the reactor (3) transfers the heat generated by the reactor (3) to the water and steam in the heat transfer pipe of the steam generator (2) through a coolant.

4. The system for the skid starting of the high temperature gas cooled reactor nuclear power plant according to claim 1, further comprising a condenser (6) and a turbine (7); a first outlet of the steam-water separator (4) is divided into two parts, the first part is connected to an inlet of a steam turbine (7), an outlet of the steam turbine (7) is connected to a first inlet of the condenser (6), and a second outlet of the steam-water separator (4) is connected to a third inlet of the condenser (6).

5. The system for the sliding pressure starting of the nuclear power plant of the high temperature gas cooled reactor according to claim 4, further comprising a second valve bank (5), wherein a second outlet of the steam-water separator (4) is connected to an inlet of the second valve bank (5), and an outlet of the second valve bank (5) is connected to a third inlet of the condenser (6).

6. The system for the sliding pressure starting of the nuclear power generating unit of the high temperature gas cooled reactor according to claim 5, further comprising a bypass regulating valve (8), wherein the second branch of the first outlet of the steam-water separator (4) is connected to the inlet of the bypass regulating valve (8), and the outlet of the bypass regulating valve (8) is connected to the second inlet of the condenser (6).