阅读说明：本技术 一种新型核电站的安全运行系统及其运行方法 (Novel safe operation system of nuclear power station and operation method thereof ) 是由 夏栓 武心壮 黄若涛 张翔云 张立君 董世昕 吴昊 张程 高晓辉 于 2021-10-15 设计创作，主要内容包括：本发明涉及核电站稳压系统技术领域,具体公开了一种新型核电站的安全运行系统及其运行方法,包括中间热交换器、循环泵、高压氮气罐、稳压器、第一电动隔离阀和第二电动隔离阀；所述中间热交换器与稳压器氮气出口相连,用于在氮气进入系统前进行充分升温,中间热交换器的管侧用于流出高压高温氮气,中间热交换器的壳侧用于流入高压低温氮气；所述循环泵通过管线与中间热交换器相连；两组电动隔离阀与高压氮气罐组成稳压器旁路。本发明与传统核电站的稳压系统不同,采用氮气进行稳压,同时增设了中间热交换器、循环泵和高压氮气罐,取代了传统蒸汽稳压中的电加热器和喷雾系统,结构简单,维护方便。(The invention relates to the technical field of a pressure stabilizing system of a nuclear power station, and particularly discloses a novel safe operation system of the nuclear power station and an operation method thereof, wherein the system comprises an intermediate heat exchanger, a circulating pump, a high-pressure nitrogen tank, a pressure stabilizer, a first electric isolation valve and a second electric isolation valve; the intermediate heat exchanger is connected with a nitrogen outlet of the pressure stabilizer and used for fully heating nitrogen before entering the system, the pipe side of the intermediate heat exchanger is used for flowing out high-pressure high-temperature nitrogen, and the shell side of the intermediate heat exchanger is used for flowing in high-pressure low-temperature nitrogen; the circulating pump is connected with the intermediate heat exchanger through a pipeline; the two groups of electric isolation valves and the high-pressure nitrogen tank form a voltage stabilizer bypass. The invention is different from the pressure stabilizing system of the traditional nuclear power station, adopts nitrogen gas to stabilize pressure, is additionally provided with an intermediate heat exchanger, a circulating pump and a high-pressure nitrogen tank, replaces an electric heater and a spraying system in the traditional steam pressure stabilization, and has simple structure and convenient maintenance.)

1. A novel safe operation system of a nuclear power station is characterized in that: comprises an intermediate heat exchanger (2), a circulating pump (3), a high-pressure nitrogen tank (4), a voltage stabilizer (1), a first electric isolating valve (5) and a second electric isolating valve (6); the intermediate heat exchanger (2) is connected with a nitrogen outlet of the pressure stabilizer (1) and is used for fully heating nitrogen before entering a system, the pipe side of the intermediate heat exchanger (2) is used for flowing out high-pressure high-temperature nitrogen, and the shell side of the intermediate heat exchanger (2) is used for flowing in high-pressure low-temperature nitrogen; the circulating pump (3) is connected with the intermediate heat exchanger (2) through a pipeline; the two groups of electric isolation valves and the high-pressure nitrogen tank (4) form a voltage stabilizer bypass.

2. The method for operating the safe operation system of the novel nuclear power plant as claimed in claim 1, wherein: the method comprises the following specific steps:

s1: when the system is in a normal operation state, the pressure change function of the system is not required to be realized;

s2: when the system pressure is reduced, the pressure of the system is increased through the bypass of the voltage stabilizer, and nitrogen is supplemented to the system through the high-pressure nitrogen tank (4) to restore the pressure to a normal operation value;

s3: when the system pressure rises, the pressure reduction function of the system is realized through the bypass of the voltage stabilizer, and redundant nitrogen is stored through the high-pressure nitrogen tank (4), so that the pressure is recovered to a normal operation value.

3. The method of claim 2, wherein the method comprises the following steps: in step S1: when the system is in a normal operation state, high-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger (2) through an outlet pipeline for heat exchange and enters the circulating pump (3) for pressurization, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger (2) for temperature rise and then enters the system through an inlet pipeline again; in this state, the inlet and outlet flow rates are the same, and the system pressure is unchanged.

4. The method of claim 2, wherein the method comprises the following steps: in step S2: when the system pressure is reduced, the system sends a boosting signal, and the second electric isolation valve (6) is opened; high-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger (2) through an outlet pipeline for heat exchange and then enters the circulating pump (3) for pressurization, and the pressurized high-pressure low-temperature nitrogen and stored nitrogen in the high-pressure nitrogen tank (4) enter the shell side of the intermediate heat exchanger (2) together for temperature rise and then enter the system through an inlet pipeline again; in this state, the inlet flow is greater than the outlet flow, and the system pressure rises; when the pressure rises to a preset value, the second electric isolation valve (6) is closed, and the normal operation state of the system is maintained.

5. The method of claim 2, wherein the method comprises the following steps: in step S3: when the pressure of the system rises, the system sends a pressure reduction signal, and the first electric isolation valve (5) is opened; high-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger (2) through an outlet pipeline for heat exchange, then enters the circulating pump (3) for pressurization and enters the high-pressure nitrogen tank (4) for storage, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger (2) for temperature rise and then enters the system through an inlet pipeline again; in this state, the inlet flow is smaller than the outlet flow, and the system pressure is reduced; when the pressure is reduced to a preset value, the first electric isolating valve (5) is closed, and the normal operation state of the system is maintained.

Technical Field

The invention relates to the technical field of a voltage stabilizing system of a nuclear power station, in particular to a novel safe operation system of the nuclear power station and an operation method thereof.

Background

In the pressurized water reactor nuclear power device, a loop system is a closed loop, and pressure fluctuation caused by temperature change or volume fluctuation of reactor coolant is controlled by a steam pressure stabilizer or a gas pressure stabilizer. The pressure stabilizer can control and protect the pressure of a reactor coolant system under the conditions of starting and stopping of the reactor, steady-state power operation, normal power change and various accident conditions, and has the functions of liquid level control, assisted start and stop of the reactor and the like.

At present, steam manostats are widely applied to various large commercial pressurized water reactor nuclear power stations, but the steam manostats need to be provided with electric heaters and manostat spraying systems to realize pressure control, and the steam manostats have the disadvantages of overlarge arrangement space, complex structure, high maintenance difficulty and the like in space-limited integrated reactor type and small and dense boat reactors. The existing gas stabilizer design has the advantages of simple structure, convenience in maintenance and the like, and simultaneously has a series of problems of material damage caused by thermal shock. If a gas pressure stabilizing system which has a pressure stabilizing function and greatly reduces thermal shock can be designed, the system of the nuclear power station is simplified, and the system is safer and more reliable.

Disclosure of Invention

The invention aims to provide a novel safe operation system of a nuclear power station and an operation method thereof, so as to solve the problems in the background technology.

In order to achieve the purpose, the invention provides the following technical scheme: a novel safe operation system of a nuclear power station comprises an intermediate heat exchanger, a circulating pump, a high-pressure nitrogen tank, a voltage stabilizer, a first electric isolation valve and a second electric isolation valve; the intermediate heat exchanger is connected with a nitrogen outlet of the pressure stabilizer and used for fully heating nitrogen before entering the system, the pipe side of the intermediate heat exchanger is used for flowing out high-pressure high-temperature nitrogen, and the shell side of the intermediate heat exchanger is used for flowing in high-pressure low-temperature nitrogen; the circulating pump is connected with the intermediate heat exchanger through a pipeline; the two groups of electric isolation valves and the high-pressure nitrogen tank form a voltage stabilizer bypass.

The invention also provides a safe operation system of the novel nuclear power station and an operation method thereof, which are characterized in that: the method comprises the following specific steps:

s1: when the system is in a normal operation state, the pressure change function of the system is not required to be realized;

s2: when the system pressure is reduced, the pressure of the system is increased through the bypass of the voltage stabilizer, and nitrogen is supplemented to the system through the high-pressure nitrogen tank, so that the pressure is recovered to a normal operation value;

s3: when the system pressure rises, the pressure reduction function of the system is realized through the bypass of the voltage stabilizer, and the redundant nitrogen is stored through the high-pressure nitrogen tank, so that the pressure is recovered to a normal operation value.

As a preferable aspect of the present invention, in step S1: when the system is in a normal operation state, high-pressure high-temperature nitrogen in the system enters the tube side of the intermediate heat exchanger through an outlet pipeline for heat exchange, then enters the circulating pump for pressurization, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger for temperature rise and then enters the system through an inlet pipeline again; in this state, the inlet and outlet flow rates are the same, and the system pressure is unchanged.

As a preferable aspect of the present invention, in step S2: when the pressure of the system is reduced, the system sends a boosting signal, and a second electric isolating valve is opened; high-pressure high-temperature nitrogen in the system enters the tube side of the intermediate heat exchanger through an outlet pipeline for heat exchange and then enters a circulating pump for pressurization, and the pressurized high-pressure low-temperature nitrogen and stored nitrogen in the high-pressure nitrogen tank enter the shell side of the intermediate heat exchanger together for temperature rise and then enter the system through an inlet pipeline again; in this state, the inlet flow is greater than the outlet flow, and the system pressure rises; when the pressure rises to a preset value, the second electric isolating valve is closed, and the normal operation state of the system is maintained.

As a preferable aspect of the present invention, in step S3: when the pressure of the system rises, the system sends a pressure reduction signal, and the first electric isolating valve is opened; high-pressure high-temperature nitrogen in the system enters the tube side of the intermediate heat exchanger through an outlet pipeline for heat exchange, then enters a circulating pump for pressurization and enters a high-pressure nitrogen tank for storage, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger for temperature rise and then enters the system through an inlet pipeline again; in this state, the inlet flow is smaller than the outlet flow, and the system pressure is reduced; when the pressure is reduced to a preset value, the first electric isolating valve is closed, and the normal operation state of the system is maintained.

Compared with the prior art, the invention has the beneficial effects that:

1. the invention provides a novel safe operation system of a nuclear power station and an operation method thereof, which are different from a pressure stabilizing system of a traditional nuclear power station, adopt nitrogen for pressure stabilization, and are additionally provided with an intermediate heat exchanger, a circulating pump and a high-pressure nitrogen tank to replace an electric heater and a spraying system in the traditional steam pressure stabilization, and have simple structure and convenient maintenance.

2. According to the novel safe operation system of the nuclear power station and the operation method thereof, the design of the intermediate heat exchanger enables nitrogen to be fully heated before entering the system, and damage of thermal shock to materials is reduced.

3. The novel safe operation system of the nuclear power station and the operation method thereof provided by the invention have the advantages that the pipeline, the valve, the circulating pump, the intermediate heat exchanger, the high-pressure nitrogen tank and other related equipment which are additionally arranged in the system are convenient to operate and manufacture, and the nitrogen pressure stabilizing system of the novel nuclear power station does not influence the realization of the normal functions of the first loop and the second loop of the reactor.

4. According to the novel safe operation system of the nuclear power station and the operation method thereof, the pipeline and the valve which are additionally arranged can meet the requirements of in-service inspection, maintenance and experiment of the valve and the pipeline.

Drawings

FIG. 1 is a schematic flow diagram of a nitrogen pressure stabilizing system of a nuclear power station in a normal operation state according to the present invention;

FIG. 2 is a schematic flow diagram of a nitrogen pressure stabilizing system of a nuclear power station in a pressure boosting state according to the invention;

FIG. 3 is a schematic flow diagram of the novel nuclear power station nitrogen pressure stabilizing system in a pressure reduction state.

In the figure: 1. a voltage regulator; 2. an intermediate heat exchanger; 3. a circulation pump; 4. a high-pressure nitrogen tank; 5. a first electrically powered isolation valve; 6. a second electrically powered isolation valve.

Detailed Description

The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.

In the description of the present invention, it should be noted that the terms "vertical", "upper", "lower", "horizontal", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of describing the present invention and simplifying the description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present invention.

In the description of the present invention, it should also be noted that, unless otherwise explicitly specified or limited, the terms "disposed," "mounted," "connected," and "connected" are to be construed broadly and may, for example, be fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.

Referring to fig. 1-3, the present invention provides a technical solution: a safe operation system of a novel nuclear power station mainly comprises an intermediate heat exchanger 2, a voltage stabilizer 1, a circulating pump 3, a high-pressure nitrogen tank 4, a first electric isolation valve 5 and a second electric isolation valve 6. The intermediate heat exchanger 2 is connected with a nitrogen outlet of the pressure stabilizer 1, the pipe side of the intermediate heat exchanger 2 is used for flowing out high-pressure high-temperature nitrogen, and the shell side of the intermediate heat exchanger 2 is used for flowing in high-pressure low-temperature nitrogen; the circulating pump 3 is connected with the intermediate heat exchanger 2 through a pipeline, and nitrogen is pressurized and then is pumped into the pressure container again to realize circulation;

a voltage stabilizer bypass is formed by the two groups of electric isolation valves and the high-pressure nitrogen tank 4, and the isolation valves are opened for adjustment when pressure adjustment is needed. When the system pressure is reduced, nitrogen is supplemented to the system through a high-pressure nitrogen tank 4, so that the pressure is recovered to a normal operation value; when the system pressure rises, the excess nitrogen is stored by the high-pressure nitrogen tank 4, so that the pressure is restored to a normal operation value. The design of the intermediate heat exchanger 2 enables nitrogen to be fully heated before entering the system, and reduces damage of thermal shock to materials.

The following further describes the operation method of the nitrogen pressure stabilizing system of the novel nuclear power station, taking a normal operation state, a pressure increasing state and a pressure reducing state as examples.

As shown in fig. 1, the nitrogen pressure stabilizing system of the nuclear power plant in a normal operation state does not need to implement a pressure changing function for the system. High-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger 2 through an outlet pipeline for heat exchange and then enters the circulating pump 3 for pressurization, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger 2 for temperature rise and then enters the system through an inlet pipeline again. In this state, the inlet and outlet flow rates are the same, and the system pressure is unchanged.

As shown in fig. 2, the nitrogen pressure stabilizing system of the nuclear power plant in the boosting state realizes the system pressure boosting function through a voltage stabilizer bypass. The system sends a boost signal and the second electrically operated isolating valve 6 opens. High-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger 2 through an outlet pipeline for heat exchange and then enters the circulating pump 3 for pressurization, and the pressurized high-pressure low-temperature nitrogen and stored nitrogen in the high-pressure nitrogen tank 4 jointly enter the shell side of the intermediate heat exchanger 2 for temperature rise and then enter the system through an inlet pipeline again. In this state, the inlet flow is greater than the outlet flow, and the system pressure rises. When the pressure rises to a predetermined value, the second electrically operated isolating valve 6 is closed, maintaining the normal operating condition of fig. 1.

As shown in fig. 3, the nitrogen pressure stabilizing system of the novel nuclear power station in the depressurization state realizes the pressure reduction function of the system through the voltage stabilizer bypass. The system sends a pressure reduction signal and the first electric isolating valve 5 is opened. High-pressure high-temperature nitrogen in the system enters the pipe side of the intermediate heat exchanger 2 through an outlet pipeline for heat exchange, then enters the circulating pump 3 for pressurization and enters the high-pressure nitrogen tank 4 for storage, and the pressurized high-pressure low-temperature nitrogen enters the shell side of the intermediate heat exchanger 2 for temperature rise and then enters the system through an inlet pipeline again. In this state, the inlet flow is smaller than the outlet flow, and the system pressure is reduced. When the pressure drops to a predetermined value, the first electrically operated isolating valve 5 is closed, maintaining the normal operating state of fig. 1.

It is worth noting that: the whole device realizes control to the device through the controller, and the controller is common equipment and belongs to the existing mature technology, and the electrical connection relation and the specific circuit structure of the controller are not repeated herein.

Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that changes, modifications, substitutions and alterations can be made in these embodiments without departing from the principles and spirit of the invention, the scope of which is defined in the appended claims and their equivalents.