KR20170028334A - Nuclear reactor and nuclear power plant having the same - Google Patents

Abstract

The present invention relates to an integrated reactor and a nuclear power plant including the same. The integrated reactor comprises: a reactor vessel formed to accommodate a core; a heat exchanger which is disposed in the reactor vessel and has a first passage in which a first fluid flows, wherein the first fluid is accommodated in the reactor vessel; a vapor generator which is disposed on the outside of the reactor vessel and has a third passage in which a third fluid flows, wherein the third fluid is changed from liquid to vapor by heat exchange; and a mid-loop having a second passage in which a second fluid exchanging heat with each of the first and third fluids and forms a circulation system by being connected to the heat exchanger and a steam generator.

Description

BACKGROUND OF THE INVENTION 1. Field of the Invention [0001] The present invention relates to nuclear reactor,

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor in which a steam generator is disposed outside a reactor vessel and a nuclear power plant having the same.

Reactors can be divided into separate reactors (eg domestic pressurized light water reactors) in which main devices (steam generator, pressurizer, pump, etc.) are installed outside the reactor depending on the installation position of the main equipment and integral reactors in which the main equipment is installed inside the reactor vessel SMART reactor).

On the other hand, printed circuit type heat exchanger technology has been developed by Heatric (United States Patent Publication No. US4665975, published on 1987.05.19) in the United Kingdom and is widely used in general industrial fields. The plate-type heat exchanger is a heat exchanger of which the welding between the plates of the heat exchanger is eliminated by using a dense flow path arrangement and diffusion bonding technique by photo-chemical etching technique.

Accordingly, the plate-type heat exchanger is applicable to high-temperature and high-pressure environments, and has high integration and excellent heat exchange performance. The plate-type heat exchanger has advantages of durability against high-temperature and high-pressure environment, excellent heat exchange performance, and high integration degree. It can be used for evaporator, condenser, The application range is expanding to a wide variety of fields such as cooler, radiator, heat exchanger, and reactor.

In addition, plate type heat exchangers have been widely used in industry for over 100 years. Plate heat exchangers typically extrude the plate to form a flow channel and join the plates using a gasket or using conventional welding or brazing. As a result, the application field is similar to that of the plate-type heat exchanger, but it is used more and more in a low-pressure environment with low pressure. The heat exchange performance of a plate heat exchanger is smaller than that of a plate-type heat exchanger, and is superior to a shell and tube heat exchanger. In addition, it is easier to manufacture than a printing plate heat exchanger.

On the other hand, the main equipment of the nuclear power plant is performing maintenance work including the non-destructive inspection of the steam generator according to the purpose of safety, reliability and operation rate improvement of the nuclear power plant and related requirements. However, in the case of a plate-type steam generator (heat exchanger) of a printing plate type, the maintenance work such as the precise inspection for each flow channel due to the very small size of the tubing or the detailed flow path, and the reason that the ISI is not possible, Difficulties are occurring.

The present invention is intended to provide a reactor capable of alleviating precise inspection and maintenance requirements, and a nuclear power plant equipped with the reactor, by applying a printing plate type steam generator to a reactor.

According to another aspect of the present invention, there is provided a reactor comprising: a reactor vessel configured to receive a core; a first fluid disposed inside the reactor vessel and accommodated in the reactor vessel; And a third flow path which is disposed outside the reactor vessel and into which a third fluid flowing from the liquid to the steam by the heat exchange flows, and a second flow path, And an intermediate loop having a second flow path through which a second fluid that is heat-exchanged with the fluid flows and which is connected to the heat exchanger and the steam generator to form a circulation system.

According to an embodiment of the present invention, the first to third flow paths include first to third flow path channels, respectively, and the first to third fluids are respectively connected to the first to third flow path channels So that heat exchange can be performed.

According to another embodiment of the present invention, the third flow channel may be formed in the inlet region of the third fluid to increase flow resistance to mitigate the flow instability generated when the third fluid flows in. The flow path resistance portion may be provided.

The flow path resistance portion may be formed so that the flow path area of the inlet region of the third fluid is narrowed to some extent and the flow resistance of the third fluid is increased while passing through the plurality of curved flow paths.

According to another embodiment of the present invention, the apparatus may further include a circulation pump disposed on the second flow path to provide a circulating power of the second fluid circulating through the second flow path.

The reactor may be configured to perform a heating operation to increase the temperature of the first fluid by using the circulation pump.

According to another embodiment of the present invention, the apparatus may further include a pressure unit connected to the inside of the reactor vessel to control the pressure of the reactor coolant system.

According to another embodiment of the present invention, the heat exchanger may be disposed at a higher position than the steam generator.

According to another embodiment of the present invention, the steam generator may be disposed at a higher position than the heat exchanger.

Further, in order to realize the above-mentioned problem, the present invention proposes a nuclear power plant including a reactor having a drift residual heat removal system and a storage portion for accommodating the reactor. The reactor includes a reactor vessel formed to receive a reactor core, a heat exchanger disposed inside the reactor vessel and having a first flow path through which a first fluid accommodated in the reactor vessel flows, and a heat exchanger disposed outside the reactor vessel And a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows; a second fluid, which is heat-exchanged with each of the first and third fluids, flows through the heat exchanger and the steam generator, An intermediate loop having a second flow path for forming a system, and a driven residual heat removal system connected to the intermediate loop to remove residual heat of the reactor and sensible heat of the reactor when an accident occurs.

Further, in order to realize the above-mentioned problem, the present invention proposes a nuclear power plant including a reactor having a stationary cooling system and a storage portion for accommodating the reactor. The reactor includes a reactor vessel formed to receive a reactor core, a heat exchanger disposed inside the reactor vessel and having a first flow path through which a first fluid accommodated in the reactor vessel flows, and a heat exchanger disposed outside the reactor vessel And a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows; a second fluid, which is heat-exchanged with each of the first and third fluids, flows through the heat exchanger and the steam generator, And an idle cooling system connected to the intermediate loop to remove residual heat of the reactor and residual heat of the reactor when the reactor is shut down.

Further, in order to realize the above-mentioned problem, the present invention proposes a nuclear power plant including a reactor and a storage portion for accommodating the reactor. The reactor includes a reactor vessel formed to receive a reactor core, a heat exchanger disposed inside the reactor vessel and having a first flow path through which a first fluid accommodated in the reactor vessel flows, and a heat exchanger disposed outside the reactor vessel And a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows; a second fluid, which is heat-exchanged with each of the first and third fluids, flows through the heat exchanger and the steam generator, And an intermediate loop having a second flow path forming a system.

According to the nuclear reactor of the present invention and the nuclear power plant having the nuclear reactor, there is provided an intermediate loop disposed between the heat exchanger and the steam generator and through which the second fluid, which exchanges heat with the first and third fluids flowing through the heat exchanger and the steam generator, The first fluid is not transferred to the third fluid even if an accident occurs between the trough and the intermediate loop or between the steam generator and the intermediate loop. As a result, it is possible to greatly alleviate the maintenance requirements of the reactor having the printing plate type steam generator.

In addition, the steam generator is disposed outside the reactor vessel, which can greatly reduce the overall size of the nuclear reactor as well as the reactor vessel, compared to the prior art. Accordingly, it is advantageous in terms of economy in construction and operation of nuclear power plants.

Also, by connecting the drift elimination system or the stationary cooling system to the intermediate loop, it is possible to effectively implement safety and cooling systems required at the time of a nuclear accident or during normal operation. Further, there is an advantage that the heating operation for raising the temperature of the first fluid accommodated in the reactor vessel can be performed through the circulation pump disposed on the second flow path of the intermediate loop.

1 is a conceptual diagram showing a reactor according to an embodiment of the present invention and a nuclear power plant having the same.
2 is a conceptual diagram showing a nuclear reactor according to another embodiment of the present invention and a nuclear power plant having the same.
FIG. 3 and FIG. 4 are conceptual diagrams showing a reactor according to another embodiment of the present invention and a nuclear power plant having the same.
FIG. 5 is a conceptual view showing an example of a third flow path through the steam generator shown in FIG. 1. FIG.

Hereinafter, a nuclear reactor of the present invention and a nuclear power plant having the same will be described in detail with reference to the accompanying drawings. In the present specification, the same or similar components are denoted by the same or similar reference numerals in different embodiments, and the description thereof is replaced with the first explanation. As used herein, the singular forms "a", "an" and "the" include plural referents unless the context clearly dictates otherwise.

FIG. 1 is a conceptual diagram showing a nuclear reactor 100 and a nuclear reactor having the same according to an embodiment of the present invention. FIG. 2 is a conceptual diagram showing a nuclear reactor 200 and a nuclear reactor having the same according to another embodiment of the present invention.

Referring first to FIG. 1, a reactor 100 includes a reactor vessel 110, a heat exchanger 120, a steam generator 130, and an intermediate loop 140.

The reactor vessel 110 is formed to receive the core 110a therein as shown. In addition, a coolant for cooling the heat generated in the core 110a is accommodated in the reactor vessel 110 together. The reactor 100 may further include a pressing unit 150 connected to the inside of the reactor vessel 110 to control the pressure of the reactor coolant system. The coolant is pressurized by the pressurizing unit 150 so that the coolant pressurized by the pressurizing unit 150 increases in boiling point and is maintained in a liquid state, (Not shown).

1, the heat exchanger 120 may include a first flow path (not shown) disposed inside the reactor vessel 110 and through which a first fluid contained in the reactor vessel 110 flows . The heat exchanger 120 may include an inlet header 120a and an outlet header 120b through which the first fluid is introduced and discharged. In addition, the first fluid may be the coolant contained in the reactor vessel 110. In addition, the heat exchanger 120 may be disposed at a position lower than the steam generator 130, as shown in FIG. Meanwhile, the reactor 100 may include a reactor coolant pump 122 that provides a circulating power for the first fluid so that the first fluid smoothly flows into and out of the first flow path. The coolant inside the reactor vessel 110 can be smoothly circulated by the reactor coolant pump 122. [

1, the steam generator 130 may have a third flow path (not shown) disposed outside the reactor vessel 110 and through which a third fluid that changes from liquid to vapor by heat exchange flows have. For example, the third fluid is supplied as a fluid in a liquid state through the water supply system shown in FIG. 1, passes through the flow path of the steam generator 130, changes into a steam state through heat exchange and flows into the turbine system . To this end, the steam generator 130 may include an inlet header 133a and an outlet header 133b through which the third fluid is introduced and discharged.

The intermediate loop 140 is connected to the heat exchanger 120 and the steam generator 130 through a pipe or the like so that a second fluid, which is heat-exchanged with the first and third fluids, And a second flow path (not shown) for forming a circulation system. To this end, the intermediate loop 140 may have a further inlet and outlet outlet to the heat exchanger 120 and the steam generator 130, respectively.

For example, as shown in FIG. 1, the intermediate loop 140 includes an inlet header and an outlet header 140a1 and 140b1 formed on the heat exchanger 120 side to receive and discharge the second fluid, And an inlet header and an outlet header 140a2 and 140b2 formed on the side of the steam generator 130 and through which the second fluid is introduced and discharged. In addition, the second fluid may be formed such that the fluid does not flow into or out of the other system while circulating through the second flow path. The second fluid may be an incompressible fluid. In this case, a pressure controller 144 may be provided to mitigate the influence of the second flow path due to the temperature of the second fluid being compressed and expanded. The pressure controller 144 may be disposed outside the reactor vessel 110 as shown.

Meanwhile, the reactor 100 may further include a circulation pump 142.

The circulation pump 142 is disposed on the second flow path and includes an outlet header of the intermediate loop formed on the heat exchanger 120 side to provide a circulating power of the second fluid circulating through the second flow path 140b1 may be disposed on the flow path formed to flow into the inlet header 140a2 of the intermediate loop 140 formed on the steam generator 130 side.

In addition, the reactor 100 may be heated to a temperature for raising the temperature of the first fluid by using the circulation pump 142. In the heating operation, the core 110a is brought into a critical state through the start-up operation of the core 110a, and the temperature of the coolant (the first fluid) is output by using the heat generated in the core 110a The operation of increasing the state to the state. Accordingly, the reactor 100 is configured such that the volume of the reactor vessel 110 is reduced by arranging the steam generator 130 in the reactor vessel 110, and at the same time, the circulation pump 142, It is possible to perform the heating operation by the heating means.

Hereinafter, the flow of fluid in the heat exchanger 120 and the steam generator 130 of the present invention will be described with reference to FIG.

First, the first fluid flows into the inlet header 120a of the heat exchanger 120 disposed inside the reactor vessel 110. At this time, the first fluid may be supplied with circulating power by the reactor coolant pump 122. The first fluid introduced into the inlet header 120a of the heat exchanger 120 flows into the intermediate loop 140 through the second fluid flowing through the second flow path of the intermediate loop 140, The heat of the first fluid is transferred to the second fluid and the first fluid whose temperature has been lowered flows through the outlet header 120b of the heat exchanger 120 into the first fluid (coolant) accommodated in the reactor vessel 110 Circulated again.

Next, the second fluid flowing through the second flow path provided in the intermediate loop 140 flows through the outlet header 140b1 formed on the heat exchanger 120 side after heat exchange with the first fluid, The second fluid flowing into the steam generator 130 through the inlet header 140a2 formed in the generator 130 flows into the steam generator 130 through the third flow passage of the steam generator 130, And is heat-exchanged with the third fluid. The second fluid heat-exchanged with the third fluid is discharged to the outside of the steam generator 130 through an outlet header 140b2 formed on the steam generator 130 side, And then flows into the inlet header 140a1 formed at the heat exchanger 120 side through the second flow path of the intermediate loop 140 and circulated. At this time, the second fluid may be supplied with the circulating power by the circulation pump 142 disposed on the second flow path.

The third flow path provided in the steam generator 130 receives the third fluid in the liquid state supplied from the water supply system through the inlet header 133a of the steam generator 130, The third fluid supplied to the steam generator 130 is changed from a liquid state to a steam state through heat exchange with the second fluid and is discharged through an outlet header 133b of the steam generator 130, 3 Fluid is supplied to the turbine system. The first to third flow paths may include a plurality of first to third flow path channels (not shown), respectively. The first and third fluids flow through the first to third flow path channels, respectively, . In addition, the first through third flow channels may be formed in a plate type or a printed circuit type.

2, the reactor 200 includes a reactor vessel 210, a heat exchanger 220, a steam generator 230, and an intermediate loop 240. The reactor vessel 210, the heat exchanger 220, the steam generator 230 and the intermediate loop 240 are connected to the nuclear reactor vessel 110, the heat exchanger 120, The steam generator 130 and the intermediate loop 140 in terms of function and effectiveness.

The heat exchanger 220 of the nuclear reactor 200 shown in FIG. 2 and the heat exchanger 220 of the nuclear reactor having the nuclear reactor 200 shown in FIG. 2 are different from the nuclear reactor 100 shown in FIG. 1, The steam generator 230 is disposed at a position higher than the steam generator 230 disposed in the steam generator 230.

According to the nuclear reactor 100 of the present invention and the nuclear power plant having the nuclear reactor 100 of the present invention as described above, the heat exchanger 120 and the steam generator 130 are disposed, and the heat exchanger 120 and the steam generator 130, And an intermediate loop 140 through which the second fluid is heat-exchanged with the first and third fluids, respectively. Accordingly, even when an accident occurs at the pressure boundary between the heat exchanger 120 and the intermediate loop 140 or between the steam generator 130 and the intermediate loop 140, the first fluid is transferred to the third fluid 140 It does not. As a result, it is possible to greatly alleviate the maintenance requirements of the reactor 100, particularly the plate-type steam generator 130. In addition, the steam generator 130 is disposed outside the reactor vessel 110, so that the overall size of the reactor as well as the reactor vessel 110 can be greatly reduced compared to the prior art. Accordingly, it is advantageous in terms of economy in construction and operation of nuclear power plants.

Hereinafter, nuclear reactors 300 and 400 according to still another embodiment of the present invention will be described with reference to FIGS. 3 and 4. FIG.

3 and 4 are conceptual diagrams showing reactors 300 and 400 according to another embodiment of the present invention and a nuclear power plant having the same.

3, the nuclear reactor 300 and the nuclear power plant including the nuclear reactor 300 include a reactor vessel 310, a heat exchanger 320, a steam generator 330, and an intermediate loop 340. The reactor vessel 310, the heat exchanger 320, the steam generator 330 and the intermediate loop 340 are connected to the nuclear reactor vessel 110, the heat exchanger 120, The steam generator 130 and the intermediate loop 140 in terms of function and effectiveness.

However, the reactor 300 shown in FIG. 3 and the nuclear power plant including the reactor 300 include a driven residual heat eliminating system 360.

The passive residual heat eliminating system 360 is one of the safety systems operated when an accident occurs in the nuclear power plant, and the sensible heat of the reactor 300 and the residual heat of the core 310a are removed when the accident occurs. The driven residual heat elimination system 360 is connected to the intermediate loop 340 disposed between the heat exchanger 320 and the steam generator 330. Thus, since the intermediate loop 340 is connected to the heat exchanger 320 disposed inside the reactor vessel 310, the passive residual heat eliminating system 360 is connected to the intermediate loop 340 through a relatively simple structure May be additionally provided.

4, the nuclear reactor 400 and the nuclear power plant including the nuclear reactor 400 include a reactor vessel 410, a heat exchanger 420, a steam generator 430, and an intermediate loop 440. The reactor vessel 410, the heat exchanger 420, the steam generator 430 and the intermediate loop 440 are connected to the reactor 100, the nuclear reactor vessel 110, the heat exchanger 120, The steam generator 130 and the intermediate loop 140 in terms of function and effectiveness.

However, the reactor 400 shown in Fig. 4 and the nuclear power plant having the reactor 400 shown in Fig. 4 include the stationary cooling system 460.

The stationary cooling system 460 is a non-safety system operated during normal operation of a nuclear power plant, unlike the drift residual heat elimination system 360 operated at the time of an accident. When the reactor 400 stops operation, And the residual heat of the core 410a. The stop cooling system 460 is connected to the intermediate loop 440 disposed between the heat exchanger 420 and the steam generator 430. Accordingly, the stationary cooling system 460 can be additionally provided through a relatively simple structure in which the stationary cooling system 460 is directly connected to the intermediate loop 440, similarly to the driven residual heat elimination system 360 .

According to the nuclear reactors 300 and 400 of the present invention and the nuclear power plant having the same, the driven residual heat elimination system 360 or the stationary cooling system 460 is connected to the intermediate loops 340 and 440, The required safety and cooling systems can be effectively implemented.

Hereinafter, an example of the third flow path through the steam generator 130 shown in FIG. 1 will be described in detail with reference to FIG.

5 is a conceptual diagram illustrating an example of a third flow path through the steam generator 130 shown in FIG.

5, the steam generator 130 includes a third flow path (not shown) through which the third fluid flows, and the third flow path includes a third flow channel 130 'through which the third fluid flows. . The steam generator 130 includes an inlet header 133a and an outlet header 133b through which the third fluid is introduced and discharged and the third flow channel 130 ' .

The flow path resistance portion 135 may be formed in the inlet region of the third fluid to increase the flow path resistance to mitigate the flow instability phenomenon generated when the third fluid flows. For example, the flow path resistance portion 135 is formed so that the flow path area of the inlet region of the third fluid is narrowed to some extent, and the flow resistance is increased while the third fluid passes through the plurality of curved flow paths. As shown in Fig. However, the flow path resistance portion 135 formed in the inlet region of the third flow path may be formed in various forms, and is not limited to the shape shown in FIG.

However, the scope of the present invention is not limited to the configuration and method of the embodiments described above, and all or some of the embodiments may be selectively combined so that various modifications may be made to the embodiments. In addition, the present invention can be applied to all equivalents of inventions, such as inventions that can be modified, added, deleted, or replaced at the level of those skilled in the art, It belongs to the scope is self-evident.

100: Reactor 110: Reactor vessel
120: heat exchanger 130: steam generator
140: intermediate loop

Claims (12)

A reactor vessel configured to receive a core;
A heat exchanger disposed inside the reactor vessel and having a first flow path through which the first fluid accommodated in the reactor vessel flows;
A plate-shaped steam generator disposed outside the reactor vessel and having a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows and flows into the turbine system;
An intermediate loop having a second flow path for circulating the second fluid by connecting the heat exchanger and the plate-type steam generator of the printing plate, the second fluid being heat-exchanged with the first and third fluids, respectively;
And a reactor core. The method according to claim 1,
Wherein the first to third flow paths include first to third flow path channels formed in plural, respectively,
Wherein the first to third fluids flow through the first to third flow channels to perform heat exchange, respectively. 3. The method of claim 2,
Wherein the third flow channel includes a flow path resistance portion formed in an inlet region of the third fluid to increase the flow path resistance to mitigate flow instability generated when the third fluid flows in, Integral reactor. The method of claim 3,
The flow-
Wherein a flow path area of the inlet region of the third fluid is formed so as to be narrowed, and the third fluid is formed so as to corrugate the flow path resistance while passing through the plurality of curved flow paths. The method according to claim 1,
Further comprising a circulation pump disposed on the second flow path and providing a circulation power of the second fluid circulating through the second flow path. 6. The method of claim 5,
And a heating operation for raising the temperature of the first fluid by using the circulation pump is enabled. The method according to claim 1,
Further comprising a pressurizing portion connected to the inside of the reactor vessel to control a pressure of the reactor coolant system. The method according to claim 1,
Wherein the heat exchanger is disposed at a higher position than the printing plate-type steam generator. The method according to claim 1,
Wherein the pressurized plate type steam generator is disposed at a higher position than the heat exchanger. Integral reactor;
A compartment for accommodating the integral nuclear reactor; And
A passive residual heat removal system connected to an intermediate loop of the integrated reactor to remove sensible heat of the integrated reactor and residual heat of the core when an accident occurs;
/ RTI >
In the integrated reactor,
A reactor vessel configured to receive a core;
A heat exchanger disposed inside the reactor vessel and having a first flow path through which the first fluid accommodated in the reactor vessel flows;
A plate-shaped steam generator disposed outside the reactor vessel and having a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows and flows into the turbine system;
And an intermediate loop having a second flow path for circulating the second fluid by connecting the heat exchanger and the plate-type steam generator of the printing plate, the second fluid being heat-exchanged with the first and third fluids, respectively, Nuclear power plant. Integral reactor;
A compartment for accommodating the integral nuclear reactor; And
A stationary cooling system connected to an intermediate loop of the integrated reactor to remove the sensible heat of the integrated reactor and residual heat of the core when the integrated reactor is shut down;
/ RTI >
In the integrated reactor,
A reactor vessel configured to receive a core;
A heat exchanger disposed inside the reactor vessel and having a first flow path through which the first fluid accommodated in the reactor vessel flows;
A plate-shaped steam generator disposed outside the reactor vessel and having a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows and flows into the turbine system;
And an intermediate loop having a second flow path for circulating the second fluid by connecting the heat exchanger and the plate-type steam generator of the printing plate, the second fluid being heat-exchanged with the first and third fluids, respectively, Nuclear power plant. Integral reactor;
And a storage portion for accommodating said integral nuclear reactor,
Said integrated reactor comprising: a reactor vessel formed to receive a core;
A heat exchanger disposed inside the reactor vessel and having a first flow path through which the first fluid accommodated in the reactor vessel flows;
A plate-shaped steam generator disposed outside the reactor vessel and having a third flow path through which a third fluid flowing from the liquid to the steam by heat exchange flows and flows into the turbine system;
And an intermediate loop having a second flow path through which the second fluid for heat exchange with the first and third fluids flows and which connects the heat exchanger and the plate type steam generator for circulation of the second fluid, Nuclear power plant.

Images