阅读说明：本技术 一种压力容器顶部双层壳体设计的安全设施配置方案 (Safety facility configuration scheme for pressure vessel top double-layer shell design ) 是由 刘展 杨波 曹克美 王海涛 于 2020-06-10 设计创作，主要内容包括：本发明公开了一种压力容器顶部双层壳体设计的安全设施配置方案,包括安全壳。本发明通过设计一体化反应堆,消除大破口发生的可能性；在压力容器顶部设置第二层压力壳体,将稳压器、主回路管线等布置在双层壳体间,通过有效隔离破口,维持压力边界,有效缓解因小破口对反应堆安全性的挑战,保证反应堆的安全性,并简化系统设计,同时,减小双层压力容器壳体设计带来的不利经济性以及维修的复杂性；通过换料水池与利用主回路换热器与非能动余热排出热交换器之间的自然循环带出设计基准失水与非失水事故下的堆芯释热(两个系列)；通过壳外空气自然对流的方式,对安全壳进行冷却降温、降压,提供无限时冷却。(The invention discloses a safety facility configuration scheme of a double-layer shell design on the top of a pressure vessel, which comprises a containment. The invention eliminates the possibility of large break by designing the integrated reactor; the second layer of pressure shell is arranged at the top of the pressure container, the voltage stabilizer, the main loop pipeline and the like are arranged between the double-layer shells, and the pressure boundary is maintained by effectively isolating the break, so that the challenge to the safety of the reactor caused by a small break is effectively relieved, the safety of the reactor is ensured, the system design is simplified, and the adverse economy and the maintenance complexity caused by the design of the double-layer pressure shell are reduced; the natural circulation between the refueling water pool and the heat exchanger which utilizes the heat of the main loop and the passive residual heat to be discharged brings out the core heat release (two series) under the design basis water loss and non-water loss accidents; the containment is cooled and depressurized in a natural convection mode of air outside the containment, and infinite cooling is provided.)

1. The safety facility configuration scheme comprises a containment (1) and is characterized in that a pressure vessel and a refueling water tank (13) are fixedly arranged in the containment (1) respectively, the pressure vessel comprises a first layer shell (7) of the pressure vessel and a second layer shell (4) of the top of the pressure vessel, a main loop pipeline (2) is connected between the first layer shell (7) of the pressure vessel and the second layer shell (4) of the top of the pressure vessel, a main loop pipeline isolation valve (3) between the two layers of shells is connected to the main loop pipeline (2) between the first layer shell (7) of the pressure vessel and the second layer shell (4) of the top of the pressure vessel, an outer main loop pipeline isolation valve (15) of the shell is connected to the main loop pipeline (2) outside the second layer shell (4) of the top of the pressure vessel, and an outer main loop pipeline isolation valve (15) of the top of the pressure vessel are arranged between the first layer shell (7) of the pressure vessel and the second layer shell (4) of the top of the pressure The device comprises a voltage stabilizer (5), wherein a voltage stabilizer fluctuation pipe (6) is connected between the voltage stabilizer (5) and a first-layer shell (7) of a pressure vessel, two or even-numbered main loop heat exchangers (8) and a reactor core (9) are arranged in the first-layer shell (7) of the pressure vessel, and two series of passive waste heat discharge heat exchangers (12) are arranged in a refueling water pool (13); a passive residual heat discharging heat exchanger outlet pipeline (10) and a passive residual heat discharging heat exchanger inlet pipeline (14) are respectively connected between the main loop heat exchangers (8) of the respective series and the passive residual heat discharging heat exchangers (12) of the same series, and the passive residual heat discharging heat exchanger outlet pipeline (10) is connected with a passive residual heat discharging heat exchanger outlet isolation valve (11).

2. The safety facility configuration scheme of the design of the double-layer shell on the top of the pressure vessel as claimed in claim 1, wherein all the main loop pipelines (2) penetrate through one end of the second layer shell (4) on the top of the pressure vessel and are connected with the top of the first layer shell (7) of the pressure vessel, all the outer-shell main loop pipeline isolation valves (15) are located in the containment shell (1), the main loop pipelines (2) are led out from the double-layer shell of the pressure vessel, all the main loop pipelines (2) between the double-layer shell are provided with isolation valves, and the main loop pipelines (2) led out of the second layer shell (4) on the top of the pressure vessel are also provided with isolation valves.

3. The safety arrangement of the design of double shell on top of pressure vessel according to claim 2, characterized in that the pressure vessel adopts double shell structure, the second shell (4) on top of the pressure vessel is located on top of the pressure vessel, and the first shell (7) on the bottom of the pressure vessel is located on the bottom of the pressure vessel.

4. The safety equipment arrangement scheme of the design of the double-layer shell at the top of the pressure vessel is characterized in that two ends of the passive residual heat removal heat exchanger outlet pipeline (10) are respectively connected with one end of the main loop heat exchanger (8) and one end of the passive residual heat removal heat exchanger (12) of the same series, and two ends of the passive residual heat removal heat exchanger inlet pipeline (14) are respectively connected with the other end of the main loop heat exchanger (8) and the other end of the passive residual heat removal heat exchanger (12) of the same series.

5. The safety arrangement of the double-shell design at the top of the pressure vessel according to claim 4, characterized in that two or even number of the main loop heat exchangers (8), the passive residual heat removal heat exchanger inlet line (14), the passive residual heat removal heat exchanger (12) and the passive residual heat removal heat exchanger outlet line (10) are connected end to form a circulation loop structure, and the two series are total.

6. The safety-equipment arrangement of the double-shell design at the top of the pressure vessel according to claim 5, characterized in that two or even number of the main-loop heat exchangers (8) are connected with their respective series of passive waste-heat removal heat exchanger inlet lines (14) and passive waste-heat removal heat exchanger outlet lines (10) at both ends.

7. A safety arrangement for a pressure vessel double shell top design according to claim 6, characterized in that the reactor core (9) is located below the primary loop heat exchanger (8).

Technical Field

The invention relates to the technical field of nuclear power plant systems and safety, in particular to a safety facility configuration scheme of a double-layer shell design on the top of a pressure vessel.

Background

At present, in order to meet the requirements of different application scenarios and to enable automated mechanical equipment to be popularized and applied to a higher degree, research and development of small reactors have been focused at home and abroad, and small reactors can be built independently or as modules of a larger complex, and the capacity can be increased along with the increase of the requirements. The application, safety and economy of the small reactor are focused, and especially the safety of the reactor in the design benchmark water loss and non-water loss accidents is ensured.

In order to improve the safety of the reactor and deal with design benchmark accidents of the nuclear power plant, the success or failure of the reactor type design is directly determined by the quality of a special safety facility configuration scheme. How to adopt an optimized configuration scheme of a special safety facility to relieve design benchmark accidents, simplify system design on the premise of ensuring safety, and improve economy is always a content which needs to be focused in reactor type research and development. In this situation, the integrated design shows its unique advantages. The invention provides an advanced configuration scheme of a special safety facility based on the design idea of an integrated small stack.

Disclosure of Invention

The invention aims to solve the problem that active coping with the reactor design benchmark loss of coolant accident and non-loss of coolant accident in the pressure vessel of a nuclear power plant is difficult in the prior art, and provides a safety facility configuration scheme of a double-layer shell design on the top of the pressure vessel.

In order to achieve the purpose, the invention adopts the following technical scheme:

a safety facility configuration scheme of a pressure vessel top double-layer shell design comprises a containment, wherein a pressure vessel and a refueling water pool are respectively and fixedly arranged in the containment, the pressure vessel comprises a pressure vessel first-layer shell and a pressure vessel top second-layer shell, a main loop pipeline is connected between the pressure vessel first-layer shell and the pressure vessel top second-layer shell, an inter-double-layer shell main loop pipeline isolation valve is connected on the main loop pipeline between the pressure vessel first-layer shell and the pressure vessel top second-layer shell, an outer-shell main loop pipeline isolation valve is connected on the main loop pipeline outside the pressure vessel top second-layer shell, a voltage stabilizer is arranged between the pressure vessel first-layer shell and the pressure vessel top second-layer shell, and a voltage stabilizer wave pipe is connected between the voltage stabilizer and the pressure vessel first-layer shell, two or even number of main loop heat exchangers and a reactor core are arranged in the first layer of shell of the pressure vessel, and two series of passive waste heat discharging heat exchangers are arranged in the refueling water pool; an outlet pipeline of the passive residual heat removal heat exchanger and an inlet pipeline of the passive residual heat removal heat exchanger are connected between the main loop heat exchangers of the respective series and the passive residual heat removal heat exchangers of the same series respectively, and an outlet pipeline of the passive residual heat removal heat exchanger is connected with an outlet isolation valve of the passive residual heat removal heat exchanger.

Preferably, all the main loop pipelines penetrate through one end of the second-layer shell at the top of the pressure vessel and are connected with the top of the first-layer shell of the pressure vessel, the main loop pipeline isolation valves outside all the shells are located in the containment, the main loop pipelines are led out from the space between the double-layer shells of the pressure vessel, all the main loop pipelines between the double-layer shells are provided with the isolation valves, and the main loop pipelines led out from the second-layer shell at the top of the pressure vessel are also provided with the isolation valves.

Preferably, the pressure vessel adopts a double-layer shell structure, the second layer of shell at the top of the pressure vessel is positioned at the top of the pressure vessel, and the first layer of shell of the pressure vessel is positioned at the bottom of the pressure vessel.

Preferably, two ends of the outlet pipeline of the passive residual heat removal heat exchanger are respectively connected with one end of the main loop heat exchanger and one end of the passive residual heat removal heat exchanger in the same series, and two ends of the inlet pipeline of the passive residual heat removal heat exchanger are respectively connected with the other end of the main loop heat exchanger and the other end of the passive residual heat removal heat exchanger in the same series.

Preferably, two or even number of the main loop heat exchangers, the passive residual heat removal heat exchanger inlet pipeline, the passive residual heat removal heat exchanger and the passive residual heat removal heat exchanger outlet pipeline are connected end to form a circulation loop structure, and the two series are formed.

Preferably, two or even number of the main loop heat exchangers are respectively connected with the passive residual heat removal heat exchanger through the respective series of passive residual heat removal heat exchanger inlet pipelines and the passive residual heat removal heat exchanger outlet pipelines.

Preferably, the reactor core is located below the primary loop heat exchanger.

Compared with the prior art, the invention has the following advantages:

1. the invention eliminates the possibility of large break by designing the integrated reactor, so as to improve the safety of the reactor core of the nuclear reactor.

2. According to the invention, the second layer of pressure shell is arranged at the top of the pressure container, the voltage stabilizer, the main loop pipeline and the like are arranged between the double-layer shells, and the pressure boundary is maintained by effectively isolating the break, so that the challenge on the safety of the reactor caused by design basis water loss and non-water loss accidents is effectively relieved, the safety of the reactor is ensured, and the system design is simplified; at the same time, the disadvantageous economy associated with the double-deck pressure vessel shell design and the complexity of maintenance are reduced.

3. The invention utilizes natural circulation to bring out the reactor core heat release under the design basis water loss and non-water loss accidents by designing the secondary side passive waste heat discharge system.

4. According to the invention, by providing an air cooling design scheme for the containment, an inlet pipeline of the passive residual heat removal heat exchanger and an outlet pipeline of the passive residual heat removal heat exchanger are connected between the main loop heat exchanger and the passive residual heat removal heat exchanger to form a circulation loop, and after the pressure of the containment is increased due to the evaporation of water in the refueling water pool, the containment is cooled, reduced in pressure and subjected to infinite cooling in a natural convection mode through air outside the containment.

In conclusion, the integrated reactor is designed, so that the influence of the design reference water loss and non-water loss accidents on the reactor is reduced, and the probability of large break is reduced; through the design of the double-layer shell and the application of reasonable arrangement of a main loop pipeline system, the crevasses are effectively isolated, the pressure boundary is maintained, and the adverse economy and the maintenance complexity caused by the traditional double-layer pressure vessel shell design technology are reduced; a circulation loop between a main loop heat exchanger and a non-active waste heat discharging heat exchanger is utilized, and natural circulation is utilized to bring out the core heat release under the design basis water loss and non-water loss accidents; the containment is cooled and depressurized in a natural convection mode of air outside the containment, and infinite cooling is provided.

Drawings

Fig. 1 is a schematic structural diagram of a safety device configuration scheme of a pressure vessel top double-layer shell design according to the invention.

In the figure: 1 containment vessel, 2 main loop pipelines, 3 main loop pipeline isolation valves between double layers of shells, 4 second layers of shells at the top of a pressure vessel, 5 voltage stabilizers, 6 voltage stabilizer fluctuation pipes, 7 first layers of shells of the pressure vessel, 8 main loop heat exchangers, 9 reactor cores, 10 passive residual heat removal heat exchanger outlet pipelines, 11 passive residual heat removal heat exchanger outlet isolation valves, 12 passive residual heat removal heat exchangers, 13 refueling water pools, 14 passive residual heat removal heat exchanger inlet pipelines and 15 main loop pipeline isolation valves outside the shells.

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.

Referring to fig. 1, a safety facility configuration scheme for a pressure vessel top double-layer shell design includes a containment 1, a pressure vessel and a refueling water tank 13 are respectively and fixedly arranged in the containment 1, the pressure vessel includes a pressure vessel first-layer shell 7 and a pressure vessel top second-layer shell 4, a main loop pipeline 2 is connected between the pressure vessel first-layer shell 7 and the pressure vessel top second-layer shell 4, a main loop pipeline isolation valve 3 between the double-layer shells is connected on the main loop pipeline 2 between the pressure vessel first-layer shell 7 and the pressure vessel top second-layer shell 4, and an outer-shell main loop pipeline isolation valve 15 is connected on the main loop pipeline 2 outside the pressure vessel top second-layer shell 4, which is worth explaining that: firstly, by adopting the design scheme, partial pipeline of the main loop pipeline 2 can be positioned between the first layer shell 7 of the pressure vessel and the second layer shell 4 at the top of the pressure vessel, the broken opening is effectively isolated, and the water supplement of the main loop under the design basis water loss accident is reduced or even cancelled; secondly, the first layer shell 7 of the pressure vessel and the second layer shell 4 at the top of the pressure vessel can be effectively utilized, the fluid in the first layer shell 7 of the pressure vessel or the second layer shell 4 at the top of the pressure vessel can be cooled and depressurized to the utmost extent through a passive residual exhaust system, the consequence of the design reference loss of coolant accident is effectively relieved, and the increased equipment in the typical reactor type adopting low-pressure injection or pressure accumulation injection cooling can be expected to be cancelled.

A voltage stabilizer 5 is arranged between the first layer shell 7 of the pressure vessel and the second layer shell 4 at the top of the pressure vessel, and a voltage stabilizer fluctuation tube 6 is connected between the voltage stabilizer 5 and the first layer shell 7 of the pressure vessel, further explaining that: when the surge pipe 6 of the pressure stabilizer is broken, the sprayed coolant is still contained in the second shell 4 at the top of the pressure vessel, and the reactor core 9 of the reactor can still be effectively cooled; when the main loop pipeline 2 between the first layer shell 7 of the pressure vessel and the second layer shell 4 at the top of the pressure vessel is broken, after a breach accident is monitored, the main loop pipeline isolation valve 15 outside the second layer shell 4 at the top of the pressure vessel is quickly closed, so that the coolant is still contained in the second layer shell 4 at the top of the pressure vessel, a new pressure boundary is formed by the second layer shell 4 at the top of the pressure vessel, and the reactor core 9 can still be effectively cooled; when the main loop pipeline 2 outside the second layer shell 4 at the top of the pressure vessel is broken, the main loop pipeline isolation valve 3 between the double layers of shells is quickly closed after the occurrence of a breach accident is monitored, and then the coolant is contained in the first layer shell 7 of the pressure vessel, so that the reactor core 9 can still be effectively cooled. Two or even number of main loop heat exchangers 8 and a reactor core 9 are arranged in the first layer shell 7 of the pressure vessel, and two series of passive waste heat discharging heat exchangers 12 are arranged in the refueling water pool 13.

And a passive residual heat discharging heat exchanger outlet pipeline 10 and a passive residual heat discharging heat exchanger inlet pipeline 14 are respectively connected between two or even number of main loop heat exchangers 8 and respective series of passive residual heat discharging heat exchangers 12, and the passive residual heat discharging heat exchanger outlet pipeline 10 is connected with a passive residual heat discharging heat exchanger outlet isolation valve 11.

It is worth noting that: a passive residual heat removal system is designed, namely, one end of a main loop heat exchanger is connected with a passive residual heat removal heat exchanger inlet pipeline 14, fluid flows into respective series of main loop heat exchangers 8 again after being cooled through a residual heat removal heat exchanger outlet pipeline 10 to form a natural circulation loop, a passive residual heat removal heat exchanger 12 is placed in a refueling water pool 13 arranged in a containment, and after the pressure of the containment 1 is increased due to water evaporation of the refueling water pool 13, the containment 1 is cooled and depressurized in a natural convection mode through air outside the containment 1, so that an infinite cooling effect is achieved.

All the main loop pipelines 2 penetrate through one end of the second-layer shell 4 at the top of the pressure vessel and are connected with the first-layer shell 7 of the pressure vessel, the main loop pipeline isolation valves 15 outside all the shells are located in the containment vessel 1, the main loop pipelines 2 are led out from the space between the double-layer shells of the pressure vessel, all the main loop pipelines 2 between the double-layer shells are provided with isolation valves, the main loop pipelines 2 led out of the second-layer shell 4 at the top of the pressure vessel are also provided with isolation valves, the pressure vessel adopts a double-layer shell structure, the second-layer shell 4 at the top of the pressure vessel is located at the top of the pressure vessel, and the first-layer shell 7 of the pressure vessel is located at the bottom of the.

Two ends of an outlet pipeline 10 of the passive residual heat removal heat exchanger are respectively connected with one end of a main loop heat exchanger 8 and one end of a passive residual heat removal heat exchanger 12 of the same series, and two ends of an inlet pipeline 14 of the passive residual heat removal heat exchanger are respectively connected with the other end of the main loop heat exchanger 8 and the other end of the passive residual heat removal heat exchanger 12 of the same series.

Two or even number of main loop heat exchangers 8, passive residual heat discharging heat exchanger inlet pipelines 14, passive residual heat discharging heat exchangers 12 and passive residual heat discharging heat exchanger outlet pipelines 10 are connected end to form a circulating loop structure, and the two series are formed.

Two or even number of the main loop heat exchangers 8 are connected with the passive residual heat removal heat exchanger 12 through respective series of passive residual heat removal heat exchanger 14 inlet pipelines and passive residual heat removal heat exchanger outlet pipelines 10.

The reactor core 9 is located below the primary loop heat exchanger 8.

Further explanation is as follows: after a design basis water loss or non-water loss accident occurs, the heat released by the reactor core 9 is transmitted to the refueling water pool 13 through the passive residual heat removal system, the water capacity in the refueling water pool 13 can ensure that the reactor core 9 is brought to a safe and stable state, and after the water in the refueling water pool 13 is heated and evaporated, the containment vessel 1 is continuously cooled through natural convection of air outside the containment vessel 1.

The invention can be illustrated by the following operating modes:

when the main loop pipeline 2 between the first layer shell 7 and the second layer shell 4 at the top of the pressure vessel is broken, after the broken opening is monitored, the main loop pipeline isolation valve 15 outside the shell is quickly closed through a manual or relative controller, at the moment, the coolant of the reactor core 9 is still contained in the second layer shell 4 at the top of the pressure vessel, a new pressure boundary is formed through the second layer shell 4 at the top of the pressure vessel, and the reactor core 9 can still be effectively cooled; after an accident, the reactor core 9 releases heat and is brought into the refueling water pool 13 through the passive residual heat discharging system; the pool capacity can ensure that the reactor core 9 is brought to a safe and stable state, and after water in the refueling pool 13 is heated and evaporated, the containment vessel 1 is cooled by natural convection of air outside the containment vessel 1.

When the main loop pipeline 2 outside the second shell 4 at the top of the pressure vessel is broken, and after the breakage is monitored, the main loop pipeline isolation valve 3 between the double shells is correspondingly and quickly closed, so that the coolant of the reactor core 9 is contained in the first shell 7 of the pressure vessel, and the reactor core 9 can still be effectively cooled; after an accident, the reactor core 9 releases heat and is brought into a refueling water tank 13 through a passive residual heat discharging system; the water capacity of the refueling water pool 13 can ensure that the reactor core 9 is brought to a safe and stable state, and after the water in the refueling water pool 13 is heated and evaporated, the containment vessel 1 is cooled by natural convection of air outside the containment vessel 1.

When the surge pipe 6 of the voltage stabilizer is broken, the sprayed coolant is still contained in the second shell 4 at the top of the pressure vessel and still has the relieving effect on the reactor core 9; under this condition, the pressure boundary of the reactor core 9 is not damaged (belonging to the design basis non-loss of coolant accident). The accident process is similar to the main loop pipeline 2 break accident which occurs between the first layer shell 7 and the second layer shell 4 on the top of the pressure vessel, and the accident relieving mode is the same.

The relieving mode of other design standard non-loss-of-coolant accidents (any layer of reactor pressure boundary is not damaged, such as normal water supply story loss) is similar to the loss-of-coolant accidents: after an accident, the reactor core 9 releases heat and is brought to the refueling water pool 13 through the passive waste heat discharging system, so that the temperature and pressure of the main loop are reduced; the capacity of the refueling water pool 13 can ensure that the reactor core 9 is brought to a safe and stable state, and after water in the refueling water pool 13 is heated and evaporated, the containment vessel 1 is cooled by natural convection of air outside the containment vessel 1, so that the purpose of infinite cooling is realized.

The above description is only for the preferred embodiment of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art should be considered to be within the technical scope of the present invention, and the technical solutions and the inventive concepts thereof according to the present invention should be equivalent or changed within the scope of the present invention.