KR102340622B1 - Refueling water discharge device and integral reactor equipped with it - Google Patents

Abstract

The present invention relates to a refueling water discharge device and an integrated nuclear reactor with the same which discharge refueling water, filled in a nuclear reactor vessel, to a refueling water tank while uniformly maintaining a water level of the refueling water tank before separating a steam generator and a nuclear reactor coolant pump after removing a nuclear fuel assembly in case of maintenance of the integrated nuclear reactor in which the steam generator and the nuclear reactor coolant pump are installed to penetrate the nuclear reactor vessel, thereby preventing refueling water from being leaked to the outside of the nuclear reactor vessel.

Description

REFUELING WATER DISCHARGE DEVICE AND INTEGRAL REACTOR EQUIPPED WITH IT

The present invention relates to a reloading water discharging device for discharging reloading water filled inside a reactor vessel in an integrated reactor to a reloading water tank, and to an integrated nuclear reactor having the same.

Nuclear reactors can be divided into separate reactors and integrated reactors according to the installation location of major equipment.

In a separate reactor (eg, commercial reactor: domestic), the main equipment (steam generator, pressurizer, pump, etc.) is installed outside the reactor vessel.

In integrated reactors such as SMART (Korea), ACP1000 (China), CAREM (Argentina), and IRIS (International Joint Research), major devices such as a steam generator and reactor coolant pump are installed inside the reactor vessel.

In an integrated reactor, the main equipment is installed inside the reactor vessel and the flow path between the main equipment is formed by the internal structure of the reactor vessel, so there is no need for a large pipe connecting the main equipment. Various types of integrated nuclear reactors are being developed because there is an advantage in that the loss of coolant accident is fundamentally excluded.

Integral reactors are filled with reactor coolant during operation.

During the period of performing the maintenance work of the reactor, the reloading water is also filled in the inside of the reactor vessel along with the reloading tank.

The reactor coolant pump and steam generator are installed through the reactor vessel.

In order to install the reactor coolant pump and steam generator inside the reactor vessel in an integrated reactor or to extract from the inside of the reactor vessel to the outside, the water level in the reloading tank is maintained at a constant height, and the reloading water filled in the inside of the reactor vessel is discharged. In one state, it is possible to install and extract the reactor coolant pump and steam generator.

However, if the sealing flange of the reactor coolant pump and the steam generator is opened while the reactor vessel is filled with reloading water, the reloading water flows out through the nozzle of the reactor vessel into the surrounding space of the reactor vessel, so the installation and extraction operations are impossible there is a problem.

The present invention prevents the reloading water from leaking to the outside of the reactor vessel when installing or extracting the reactor coolant pump and steam generator in an integrated reactor, and maintains a constant level of reloading water in the reloading tank, and the inside of the reactor vessel An object of the present invention is to provide a reloading water discharging device capable of discharging the reloading water filled in the reloading tank to a reloading tank, and an integrated nuclear reactor having the same.

In order to achieve the above object, the reloading water discharge device according to the present invention includes a sealing plate mounted on the upper flange portion of the reactor vessel so as to cover the upper opening of the reactor vessel; a water level meter mounted on the sealing plate and measuring the level of reloading water filled in the reactor vessel; a drain pump mounted on the sealing plate and discharging the reloading water to a reloading water tank installed at an upper portion of the reactor vessel; and a control unit for controlling the operation of the drain pump according to the level of the reloading water sensed by the water level meter.

According to an example related to the present invention, the drain pump penetrates the sealing plate to achieve the above object. Sealing plate mounted on the upper flange portion; a water level meter mounted on the sealing plate and measuring the level of reloading water filled in the reactor vessel; a drain pump mounted on the sealing plate and discharging the reloading water to a reloading water tank installed at an upper portion of the reactor vessel; and a control unit for controlling the operation of the drain pump according to the level of the reloading water sensed by the water level meter.

According to an example related to the present invention, the drain pump may include: a pump housing extending in a vertical direction to pass through the sealing plate; an impeller rotatably installed in the pump housing and sucking the reloading water; an electric motor installed inside the pump housing so as to be connected to the impeller and driving the impeller; and a suction pipe extending from the pump housing to an inner lower portion of the reactor vessel to suck the reloading water.

According to an example related to the present invention, a first flange is formed to penetrate in the vertical direction in the central portion of the sealing plate, and the drain pump is radially protruded from the outer peripheral surface of the pump housing penetrating the first flange, , a pump flange disposed to overlap the first flange in the vertical direction; and a plurality of first fastening members for fastening the pump flange and the first flange.

According to an example related to the present invention, the drain pump may include a pump gasket disposed between the pump flange and the first flange to seal between the sealing plate and the drain pump.

According to an example related to the present invention, the drain pump may further include a non-return valve installed inside the pump housing to prevent a reverse flow of the reload water from the reload tank to the reactor vessel.

According to an example related to the present invention, a second flange is eccentrically formed through the sealing plate, and the water level meter includes: a meter housing installed to pass through the second flange and accommodating the water level meter; a measuring flange protruding in a radial direction from the outer circumferential surface of the measuring instrument housing and disposed to overlap the second flange in a vertical direction; and a plurality of second fastening members for fastening the meter flange and the second flange.

According to an example related to the present invention, an instrument gasket may be disposed between the instrument flange and the second flange to seal between the sealing plate and the instrument housing.

According to an example related to the present invention, a lighting lamp installed inside the instrument housing to illuminate the inside of the reactor vessel; and a closed circuit camera installed inside the instrument housing to photograph the internal state of the reactor vessel.

According to an example related to the present invention, the apparatus may further include an intake pipe installed inside the instrument housing to equalize the pressure between the reactor vessel and the reload tank.

According to an example related to the present invention, the sealing plate may include a mounting portion protruding from a lower portion of the sealing plate to an upper flange portion of the reactor vessel; and a sealing gasket installed on a bottom surface of the mounting part to seal between the sealing plate and the upper flange part of the reactor vessel.

An integrated reactor according to an embodiment of the present invention includes a reactor vessel; a reload tank installed on the upper part of the reactor vessel; a steam generator installed inside the reactor vessel; a reactor coolant pump installed to pass through the reactor vessel; a sealing plate disposed between the reload tank and the reactor vessel to seal between the reload tank and the reactor vessel; a water level meter mounted on the sealing plate and measuring the level of reloading water filled in the reactor vessel; a drain pump mounted on the sealing plate and discharging the reloading water to a reloading water tank installed at an upper portion of the reactor vessel; and a control unit controlling the operation of the drain pump according to the level of the reloading water sensed by the water level meter.

According to an example related to the present invention, the sealing plate is formed in the form of a disk,

and a plurality of guide post insertion holes formed to penetrate through the edge portion of the sealing plate in the thickness direction, wherein the reactor vessel is inserted through the guide post insertion hole at the upper flange portion of the reactor vessel. It may further include a plurality of guide pillars extending upwardly inward, guiding the vertical movement of the sealing plate.

According to an example related to the present invention, a plurality of lifting equipment insertion holes may be formed to protrude from the upper surface of the sealing plate so as to be coupled with the lifting equipment for lifting the sealing plate.

According to an example related to the present invention, the sealing plate may include: a first flange formed to penetrate vertically in a central portion of the sealing plate so that the drain pump can penetrate the sealing plate; a second flange disposed to be spaced apart from the first flange in a radial direction so that the water level gauge can penetrate the sealing plate and formed to penetrate vertically through the sealing plate; and a plurality of reinforcing bars extending radially from the outer peripheral surface of the first flange to the outermost end of the sealing plate and protruding upward from the upper surface of the sealing plate.

According to an example related to the present invention, a first flange is formed to penetrate in the vertical direction in the central portion of the sealing plate, and the drain pump is a pump extending to protrude in the vertical direction of the sealing plate through the first flange. housing; an impeller rotatably installed in the pump housing and sucking the reloading water; an electric motor installed inside the pump housing so as to be connected to the impeller and driving the impeller; a suction port positioned lower than the sealing plate and formed at a lower end of the pump housing so that the reloading water is sucked into the pump housing; a discharge port positioned higher than the sealing plate so that the reloading water flows out from the pump housing to the reloading water tank and formed at an upper end of the pump housing; and a suction pipe extending vertically downward from the suction port of the pump housing so that the reloading water rises to the suction port.

According to an example related to the present invention, the steam generator is disposed lower than the reactor coolant pump, and in the steam generator, the coolant supplied from the water supply system can flow therein, and the reactor coolant is circulated inside the reactor vessel. a heat transfer tube for generating steam by exchanging heat with the cooling water; a water supply header provided at the lower end of the steam generator and installed to pass through the reactor vessel to deliver the cooling water to the heat transfer tube; It is provided at the upper end of the steam generator, is installed to penetrate the reactor vessel, may include a steam header for transferring the steam generated in the heat transfer tube to the turbine system.

According to an example related to the present invention, the lower end of the suction pipe may extend to be positioned lower than the water supply header.

A method for discharging reloading water for an integrated nuclear reactor according to an embodiment of the present invention includes a reactor vessel having a core in which a nuclear fuel assembly is loaded, a reloading water tank installed in an upper portion of the reactor vessel, and a steam generator installed in the reactor vessel and supplying reloading water to the reactor vessel and the reloading tank during maintenance of an integrated reactor including a reactor coolant pump installed penetratingly into the reactor container to fill the reloading tank to a certain height; removing the nuclear fuel assembly from the reactor vessel; inserting a sealing plate into a plurality of guide pillars extending vertically from the upper flange portion of the reactor vessel, and lowering the sealing plate along the plurality of guide pillars to cover the upper opening of the reactor vessel; mounting a drain pump through a first flange formed to pass through the sealing plate; mounting a water level gauge through a second flange formed to pass through the sealing plate; The operation of the drain pump is controlled according to the level of the reloading water level of the reactor vessel detected by the water level meter to maintain a constant water level in the reloading tank, and the reloading water of the reactor vessel is transferred to the reloading tank. It may include the step of discharging.

According to an example related to the present invention, when the water level of the reactor vessel is lower than that of the steam generator, the method may include separating and extracting the reactor coolant pump and the steam generator.

The effects of the reloading water discharge device and the integrated reactor having the same according to the present invention will be described as follows.

First, during maintenance of an integrated reactor, reloading water is supplied and filled to the reactor vessel and the reloading tank disposed at the upper end thereof, after the nuclear fuel assembly is removed from the reactor vessel, before separating the steam generator and the reactor coolant pump, the sealing plate Descend along the guide column and mount to cover the upper opening of the reactor vessel.

Then, the drain pump and the water level gauge are mounted on the sealing plate.

The water level gauge detects the level of reloading water in the reactor vessel, and the drain pump is controlled by the controller according to the detected level of the reactor vessel.

The drain pump pumps up the reloading water through the suction pipe extending directly downward from the lower part of the sealing plate toward the core until the level of the reloading water inside the reactor vessel is below the lower end of the steam generator and discharges it to the reloading tank. have.

Accordingly, while maintaining the water level of the reloading tank constant, the reloading water level of the reactor vessel is lowered below the lower end of the steam generator, thereby separating and installing the steam generator and the reactor coolant pump. A sealing flange installed on the nozzle of the reactor vessel Even if the reactor is opened, it is possible to prevent the radioactively contaminated reload water from leaking to the outside of the reactor vessel.

Second, since the leakage of radioactivity to the outside of the reactor vessel is prevented, the safety of the nuclear power plant can be secured.

Third, it is easy to install and dismantle the reactor coolant pump and steam generator during maintenance of the reactor assembly, and it is possible to perform inspection and maintenance work on the reactor assembly.

1 is a conceptual diagram illustrating an example of an integrated nuclear reactor to which the present invention is applicable.
2 is a conceptual diagram illustrating a state in which the reloading water discharge device according to the present invention is mounted on the upper part of the reactor vessel in a state in which the nuclear fuel assembly is removed from the reactor core.
3 is a conceptual view showing a state in which each of the pump assembly and the measuring instrument assembly is mounted on the sealing plate in FIG. 2 .
FIG. 4 is a conceptual view illustrating a pump assembly and a meter assembly mounted on the sealing plate of FIG. 3 as viewed from the bottom of the sealing plate.
5 is a cross-sectional view showing a state in which the sealing gasket is mounted on the lower portion of the sealing plate taken along VV in FIG. 4 .
6 is a perspective view showing the pump assembly in FIG. 3 .
7 is a cross-sectional view of the pump assembly taken along VII-VII in FIG. 6 ;
FIG. 8 is a perspective view showing the instrument assembly in FIG. 3 .
FIG. 9 is a side view illustrating a side view of the measuring instrument assembly of FIG. 8 .
10 is a conceptual diagram illustrating a state in which a nuclear fuel assembly is removed from a reactor vessel according to the present invention.
11 is a conceptual diagram illustrating a state in which the sealing plate descends along the guide pillar to cover the upper end of the reactor vessel in FIG. 10 .
12 is a conceptual view illustrating a state in which the pump assembly is mounted on the sealing plate in FIG. 11 .
13 is a conceptual diagram illustrating a state in which the instrument assembly is mounted on a sealing plate in FIG. 12 and an operating state of the reloading water discharge device.

Hereinafter, the embodiments disclosed in the present specification will be described in detail with reference to the accompanying drawings, but the same or similar components are assigned the same reference numbers regardless of reference numerals, and redundant description thereof will be omitted. The suffixes "module" and "part" for components used in the following description are given or mixed in consideration of only the ease of writing the specification, and do not have distinct meanings or roles by themselves. In addition, in describing the embodiments disclosed in the present specification, if it is determined that detailed descriptions of related known technologies may obscure the gist of the embodiments disclosed in this specification, the detailed description thereof will be omitted. In addition, the accompanying drawings are only for easy understanding of the embodiments disclosed in the present specification, and the technical idea disclosed herein is not limited by the accompanying drawings, and all changes included in the spirit and scope of the present invention , should be understood to include equivalents or substitutes.

Terms including an ordinal number such as 1st, 2nd, etc. may be used to describe various elements, but the elements are not limited by the terms. The above terms are used only for the purpose of distinguishing one component from another.

When an element is referred to as being “connected” or “connected” to another element, it is understood that it may be directly connected or connected to the other element, but other elements may exist in between. it should be On the other hand, when it is said that a certain element is "directly connected" or "directly connected" to another element, it should be understood that the other element does not exist in the middle.

The singular expression includes the plural expression unless the context clearly dictates otherwise.

In the present application, terms such as “comprises” or “have” are intended to designate that a feature, number, step, operation, component, part, or combination thereof described in the specification exists, but one or more other features It should be understood that this does not preclude the existence or addition of numbers, steps, operations, components, parts, or combinations thereof.

1 is a conceptual diagram illustrating an example of an integrated nuclear reactor to which the present invention is applicable.

The integrated reactor includes a reactor vessel 100, a core 104, a plurality of steam generators 103, a plurality of reactor coolant pumps 105, a pressurizer 106, a core support barrel 107, an upper guide structure 108, It is configured to include a control rod driving device (109).

The integrated reactor is a nuclear reactor in which a core 104, a plurality of steam generators 103, a pressurizer 106, a plurality of reactor coolant pumps 105, and the like are built in a single vessel without connecting pipes.

The reactor vessel 100 may integrally form the exterior of the nuclear reactor.

The reactor vessel 100 may be a pressure vessel made of a carbon steel material so that a chain of fission reactions can occur safely by loading nuclear fuel.

The reactor vessel 100 may include a lower vessel body and a reactor head 102 .

The lower container body may be formed in a cylindrical shape. The reactor vessel 100 may be formed to have a longer length in the vertical direction compared to its diameter.

A hemispherical lower head may be mounted on the lower portion of the lower container body.

The reactor head 102 may be flanged using stud bolts to cover the upper portion of the lower vessel body. A control rod driving device 109 for inserting or withdrawing the control rod 110 for controlling the nuclear fission reaction rate may be mounted outside the reactor head 102 .

The core 104 is disposed below the reactor vessel 100 . The core 104 is a place where nuclear fuel is loaded, and may be composed of a nuclear fuel assembly.

A core support barrel 107 and an upper guide structure 108, which are internal structures separable from each other, may be installed inside the reactor vessel 100 .

The core support barrel 107 and the upper guide structure 108 support nuclear fuel from above and below, and may form a circulation path of the reactor coolant inside the reactor vessel 100 .

An annular space may be formed between the inner wall of the reactor vessel 100 and the core support barrel 107 . A plurality of steam generators 103 in the annular space may be arranged to be spaced apart in the circumferential direction.

A plurality of nozzles are formed to penetrate through the reactor vessel 100 in the thickness direction. The plurality of nozzles may include a plurality of first nozzles 111 for installing the reactor coolant pump 105 and a second nozzle 112 and a third nozzle 113 for installing the steam generator 103 . .

A reactor coolant pump 105 may be installed above the steam generator 103 . A part of the impeller and the rotation shaft of the reactor coolant pump 105 is disposed inside the reactor vessel 100 , and the electric motor of the reactor coolant pump 105 may be installed to protrude to the outside of the reactor vessel 100 .

The rotating shaft may be disposed to pass through the first nozzle 111, one side of the rotating shaft may be connected to the impeller, and the other side of the rotating shaft may be connected to the electric motor. The electric motor may provide power to the impeller through a rotating shaft.

The motor of the reactor coolant pump 105 may be isolated from the coolant by enclosing the stator and the rotor with a sealing can to prevent the coolant from permeating the stator and the rotor. The electric motor of the reactor coolant pump 105 may be referred to as a canned motor.

The impeller of the reactor coolant pump 105 is connected to an electric motor and a rotating shaft. As the motor runs, the impeller rotates to provide circulating power to the reactor coolant.

The inside of the reactor vessel 100 is filled with a primary system fluid, and the heat received from the core 104 is transferred from the steam generator 103 to the secondary system fluid.

The primary system is a system that cools the core 104 by receiving heat directly from the core 104 by circulating the reactor coolant, which is the primary system fluid. The primary system includes a reactor coolant pump 105 , a steam generator 103 , a pressurizer 106 , and the like.

The secondary system is a system that receives heat from the primary system while maintaining a pressure boundary with the primary system and uses the received heat to produce electricity. The secondary system includes a turbine and a generator, and generates electricity through the generator.

The steam generator 103 may be located higher than the core 104 .

According to this configuration, the reactor coolant of the primary system circulates in the order of the core 104, the reactor coolant pump 105, the steam generator 103, and the core 104, and the heat generated in the core 104 is transferred to the steam generator ( 103) can be forwarded.

The steam generator 103 may be configured in a once-through spiral form. The steam generator 103 may be composed of a shell and a spiral heat pipe. The reactor coolant flows to the outside of the heat pipe, and the secondary-side water supply is configured to flow into the inside of the heat pipe.

A water supply header 1031 is installed at the lower end of the steam generator 103 . The water supply header 1031 is connected to the water supply system 10 through the main water supply pipe 12 , and receives water from the water supply system 10 .

A water supply valve 11 is installed in the main water supply pipe 12 to open and close the main water supply pipe 12 . A check valve (not shown) is installed in the main water supply pipe 12 to prevent reverse flow of the water supply.

A steam header 1032 is installed at the upper end of the steam generator 103 . The steam header 1032 is connected to the turbine system 13 through the chief complaint engine 14 , and supplies the steam generated by the steam generator 103 to the turbine system 13 .

A steam valve 15 is installed in the chief complaint engine 14, and the chief complaint engine 14 can be opened and closed.

A check valve (not shown) is installed in the chief complaint engine 14 to prevent the reverse flow of steam.

When water is supplied from the water supply system 10 to the steam generator 103 through the main water supply pipe 12 during normal operation of the nuclear power plant, the steam generator 103 generates steam using the heat transferred from the core 104 . Steam is supplied to the turbine system 13 through the chief complaint engine 14, and the turbine system 13 generates electricity using the supplied steam.

For the soundness of a pressurized light water nuclear power plant, a pressure boundary must be maintained between the primary system and the secondary system.

The steam generator 103 is disposed at the boundary between the primary system and the secondary system to induce heat exchange between the primary system fluid and the secondary system fluid.

Each of the water supply header 1031 and the steam header 1032 of the steam generator 103 is installed to penetrate through the reactor vessel 100 .

The steam header 1032 may be coupled to the second nozzle 112 , and the steam header 1032 may be connected in communication with the chief complaint engine 14 outside the reactor vessel 100 through the second nozzle 112 . The steam header 1032 may supply the steam generated by the steam generator 103 to the turbine system 13 .

The water supply header 1031 may be coupled to the third nozzle 113 , and the water supply header 1031 may be connected in communication with the main water supply pipe 12 outside the reactor vessel 100 through the third nozzle 113 . The water supply header 1031 may receive cooling water from the water supply system 10 and introduce it into the heat transfer tube of the steam generator 103 .

The pressurizer 106 is provided in the space between the reactor head 102 (reactor cover) and the upper guide structure 108, and is configured to control the pressure of the reactor coolant system to a preset pressure using thermal equilibrium between steam and reactor coolant. do.

A plurality of sealing flanges 114 may be installed in the plurality of nozzles. The plurality of sealing flanges 114 cover and seal the opening of the nozzle. The sealing flange 114 may be fastened by a plurality of fastening bolts.

According to this configuration, the plurality of sealing flanges 114 can maintain a pressure boundary between the header of the steam generator 103 and the reactor vessel 100 .

In addition, the plurality of sealing flanges 114 are configured to maintain a pressure boundary between the reactor coolant pump 105 and the reactor vessel 100 .

FIG. 2 is a conceptual diagram illustrating a state in which the reloading water discharge device according to the present invention is mounted on the upper part of the reactor vessel 100 in a state in which the nuclear fuel assembly 1041 is removed from the nuclear reactor core 104 .

3 is a conceptual diagram illustrating a state in which each of the pump assembly 130 and the meter assembly 140 is mounted on the sealing plate 120 in FIG. 2 .

FIG. 4 is a conceptual view illustrating the pump assembly 130 and the measuring instrument assembly 140 mounted on the sealing plate 120 of FIG. 3 as viewed from the bottom of the sealing plate 120 .

5 is a cross-sectional view showing a state in which the sealing gasket 124 is mounted on the lower portion of the sealing plate 120 taken along V-V in FIG. 4 .

6 is a perspective view illustrating the pump assembly 130 in FIG. 3 .

7 is a cross-sectional view of the pump assembly 130 taken along VII-VII in FIG. 6 .

FIG. 8 is a perspective view showing the instrument assembly 140 in FIG. 3 .

FIG. 9 is a side view illustrating a side view of the measuring instrument assembly 140 of FIG. 8 .

A reload tank 115 may be installed on the upper portion of the reactor vessel 100 . Reloading water may be stored in the reloading tank 115 .

The reload tank 115 is disposed to surround the upper portion of the reactor vessel 100 .

A communication part may be formed so that the reactor head 102 communicates with the upper opening of the reactor vessel 100 from which it has been removed, in the lower portion of the reloading water tank 115 to penetrate in the vertical direction.

During maintenance, reloading water may be injected into the reactor vessel 100 and the reloading water tank 115 , respectively.

The reloading water filled in the reactor vessel 100 and the reloading tank 115 is used for dismantling the nuclear fuel assembly 1041 from the core 104 or for installation and extraction of the steam generator 103 and the reactor coolant pump 105 . When the reactor head 102 is opened from the upper flange portion 101 of the reactor vessel 100 , it provides a function of blocking radiation from leaking out through the top opening of the reactor vessel 100 .

For example, in a state in which the nuclear fuel assembly 1041 is removed from the core 104 of the integrated reactor, the reactor coolant pump 105 and the steam generator 103 coupled to the nozzle of the reactor vessel 100 are separated. It is necessary to maintain a constant water level in the charging water tank 115 and to prevent the reloading water stored in the reactor vessel 100 from leaking out through the nozzle when the sealing flange 114 is opened.

To this end, the present invention provides a reloading water discharging device capable of discharging the reloading water stored in the reactor vessel 100 to the reloading water tank 115 .

The reloading water discharge device includes a sealing plate 120 , a pump assembly 130 , and a meter assembly 140 .

The sealing plate 120 may be formed in a disk shape.

A flange portion 101 may be formed at an upper edge of the reactor vessel 100 . The thickness of the flange portion 101 may be formed to be thicker than the thickness of the reactor vessel 100 .

The sealing plate 120 may be mounted on the flange portion 101 of the reactor vessel 100 . The sealing plate 120 is made to cover the upper opening of the reactor vessel 100 .

The mounting part 123 may be formed to protrude vertically downward from the lower surface of the sealing plate 120 . The mounting part 123 may extend along the circumferential direction of the sealing plate 120 . The outer peripheral diameter of the mounting part 123 may be formed smaller than the outermost diameter of the sealing plate 120 .

A mounting groove may be formed on the inner surface of the flange portion 101 to extend in the circumferential direction.

The mounting part 123 of the sealing plate 120 may be fitted into the mounting groove of the flange part 101 . According to this, the sealing plate 120 may restrict movement in the radial direction in the flange portion 101 .

A sealing gasket 124 may be installed on a bottom surface of the mounting part 123 . A gasket receiving groove for installing the sealing gasket 124 may be formed on the bottom surface of the mounting part 123 . The sealing gasket 124 may be formed in a circular ring shape. The sealing gasket 124 may have a circular cross-sectional shape.

The sealing gasket 124 is configured to seal between the flange portion 101 of the reactor vessel 100 and the mounting portion 123 of the sealing plate 120 .

The sealing gasket 124 may be compressed by the weight of the reloading water positioned on the upper portion of the sealing plate 120 .

Accordingly, it is possible to seal between the sealing plate 120 and the flange of the reactor vessel 100 .

The first flange 121 may be formed to protrude in the vertical thickness direction so that the pump assembly 130 is installed vertically through the central portion of the sealing plate 120 .

The first flange 121 may be formed in a circular closed loop shape. A first through hole may be formed inside the first flange 121 . The pump assembly 130 may be installed to pass through the first through hole.

The first flange 121 may be formed in a plurality of first fastening grooves. The plurality of first fastening grooves may be disposed to be spaced apart from each other in the circumferential direction of the first flange 121 .

A plurality of reinforcing bars 125 may be formed on the upper surface of the sealing plate 120 to protrude upward. Each of the plurality of reinforcing bars 125 may extend from the outer circumferential surface of the first flange 121 to the outer circumferential portion of the sealing plate 120 elongated in the radial direction.

The plurality of reinforcing bars 125 may have a rectangular cross-sectional shape.

The plurality of reinforcing bars 125 may be disposed to be spaced apart from each other in the circumferential direction of the sealing plate 120 .

The plurality of reinforcing bars 125 are configured to reinforce the rigidity of the sealing plate 120 .

The second flange 122 may be formed to protrude in the vertical thickness direction so that the measuring instrument assembly 140 is installed on the sealing plate 120 vertically. The second flange 122 is disposed to be spaced apart from the first flange 121 in a radial direction outward.

The second flange 122 may be disposed between two reinforcing bars 125 adjacent to each other in the circumferential direction of the sealing plate 120 .

The second flange 122 may be formed in a circular closed loop shape. A second through hole may be formed inside the second flange 122 . The measuring instrument assembly 140 may be installed to pass through the second through hole.

A plurality of second fastening grooves may be formed in the second flange 122 . The plurality of second fastening grooves may be disposed to be spaced apart from each other in the circumferential direction of the second flange 122 .

At the upper end of the flange portion 101 of the reactor vessel 100 , a plurality of guide pillars 126 may be installed vertically upward. The plurality of guide posts 126 may be disposed to be spaced apart from each other in the circumferential direction of the flange portion 101 . In this embodiment, two guide posts 126 are installed at an interval of 180 degrees.

The plurality of guide posts 126 are configured to guide the vertical movement of the sealing plate 120 .

A plurality of guide post insertion holes 127 may be formed to penetrate in the vertical direction in the sealing plate 120 . The plurality of guide posts 126 are inserted into the plurality of guide post insertion holes 127 , and the sealing plate 120 may move in the vertical direction along the plurality of guide posts 126 .

The plurality of guide post insertion holes 127 may be formed to be spaced apart from each other in the circumferential direction at the edge of the sealing plate 120 . The plurality of guide post insertion holes 127 may be disposed outside the mounting portion 123 of the sealing plate 120 .

A plurality of lifting equipment insertion holes 128 may be formed to protrude from the upper surface of the sealing plate 120 . The plurality of lifting equipment inserts 128 may be formed in a cylindrical shape.

The plurality of lifting equipment inserts 128 may be disposed to be spaced apart from each other in the circumferential direction of the sealing plate 120 . It is preferable that at least three or more lifting equipment insertion openings 128 are installed to be spaced apart at equal intervals (eg, at intervals of 120 degrees).

If the two lifting equipment inserts 128 are installed in the sealing plate 120, either side of the sealing plate 120 may be inclined during lifting.

The plurality of lifting equipment inserts 128 may be configured to be capable of being coupled with a hook of a lifting equipment such as a crane. For example, a threaded portion may be formed in the lifting equipment insertion hole 128 to be screw-fastened with a hook. Alternatively, a locking hole may be formed in the lifting equipment insertion hole 128, and the hook may be inserted into the locking hole and coupled thereto.

The lifting device of the sealing plate 120 may be used together with the lifting device for the internal structure of the nuclear reactor.

The pump assembly 130 may include a drain pump 131 , a suction pipe 137 , a pump flange 1321 , a pump gasket 133 , and the like.

The drain pump 131 includes a pump housing 132 , an impeller 135 , and an electric motor 136 .

The pump housing 132 may be formed in a cylindrical shape. The pump housing 132 forms the exterior of the drain pump 131 . An accommodation space may be formed inside the pump housing 132 .

The impeller 135 and the electric motor 136 may be installed in the receiving space of the pump housing 132 to be accommodated.

A flow path through which reloading water can flow may be formed in the receiving space of the pump housing 132 .

The impeller 135 is rotatably installed inside the pump housing 132 .

The electric motor 136 includes a stator and a rotor. The stator is installed inside the case. The rotor is rotatably installed with respect to the stator. The rotor may generate rotational force by electromagnetic interaction with the stator.

A shaft may be rotatably installed together with the rotor inside the rotor. The shaft may protrude from the inside of the case of the electric motor 136 toward the impeller 135 . Both ends of the shaft may be rotatably supported by bearings.

The impeller 135 and the electric motor 136 may be connected by a shaft. The rotational force generated by the electric motor 136 may be transmitted to the impeller 135 through the shaft. The impeller 135 may rotate by receiving power transmitted from the electric motor 136 .

The impeller 135 may form an axial flow by rotating the fluid.

An inlet 1381 may be formed at a lower end of the pump housing 132 . An outlet 1382 may be formed at an upper end of the pump housing 132 .

The fluid flowing by the impeller 135 flows into the inside of the pump housing 132 through the inlet 1381, rises in the pump housing 132, passes the impeller 135 and the electric motor 136, and the outlet 1382 ) can be leaked.

The suction pipe 137 may be connected in communication with the inlet 1381 of the pump housing 132 . The suction pipe 137 may extend long directly downward from the inlet 1381 of the pump housing 132 .

The suction pipe 137 has a flow path formed therein through which a fluid (reloading water) can flow, so that the fluid (reloading water) can be sucked through the suction pipe 137 .

The pump flange 1321 may be formed to protrude outward in the radial direction from the outer circumferential surface of the pump housing 132 .

The pump flange 1321 may be disposed to face the first flange 121 in the longitudinal direction (up and down direction) of the pump housing 132 .

A plurality of fastening holes may be formed to pass through the pump flange 1321 . A plurality of first fastening members 134 such as screws are configured to be respectively fastened to the pump flange 1321 and the first flange 121 of the sealing plate 120 .

Each of the plurality of first fastening members 134 may pass through the fastening hole and be fastened to the fastening groove of the first flange 121 .

According to this configuration, the pump flange 1321 and the first flange 121 are fastened to each other, and the pump housing 132 may be installed to penetrate the sealing plate 120 .

A pump gasket 133 may be disposed between the pump flange 1321 and the first flange 121 .

The pump gasket 133 is disposed between the pump flange 1321 and the first flange 121 and may be compressed by the fastening force of the first fastening member 134 .

The pump gasket 133 is configured to seal between the pump flange 1321 and the first flange 121 .

The pump gasket 133 may be formed in a disk shape while both sides thereof are flat.

According to this configuration, the pump gasket 133 may maintain airtightness between the pump assembly 130 and the sealing plate 120 .

A non-return valve 139 may be installed at an inner lower portion of the pump housing. The non-return valve 139 may be implemented as a check valve. The non-return valve 139 may be disposed below the impeller 135 .

The non-return valve 139 may be disposed on the upstream side of the impeller 135 based on the flow direction of the reloading water.

The non-return valve 139 may prevent the reloading water from flowing back into the reactor vessel 100 from the reloading water tank 115 when the operation of the drain pump 131 is stopped.

The electric motor 136 of the drain pump 131 may be connected to the controller 149 through a power line.

The control unit 149 is configured to control the electric motor 136 of the drain pump 131 . The control unit 149 may control the flow rate of the reloading water discharged from the reactor vessel 100 to the reloading water tank 115 by controlling the drain pump 131 .

The control unit 149 may be located at the work site above the reloading water tank 115 .

One end of the power line may pass through the upper end of the pump housing 132 of the drain pump 131 and be connected to the electric motor 136 , and the other end of the power line may be connected to the controller 149 .

According to this configuration, when the drain pump 131 is operated, the impeller 135 rotates, and the reloading water rises along the suction pipe 137 in the reactor vessel 100 by the suction force generated from the impeller 135 . .

The reloading water flows into the inside of the pump housing 132 through the inlet 1381 of the pump housing 132 through the suction pipe 137, and the impeller 135 and the electric motor 136 of the pump housing 132. It may flow out into the reloading water tank 115 through the outlet 1382 of the pump housing 132 .

The meter assembly 140 may include a meter housing 141 , a water level meter 145 , a closed circuit camera 147 , a lighting lamp 146 , and an intake pipe 148 .

The instrument housing 141 may be formed in a cylindrical shape. The instrument housing 141 may extend in a vertical direction. An accommodating space capable of accommodating the water level gauge 145 and the like is formed in the measuring instrument housing 141 .

The water level meter 145 may be formed to protrude directly downward from the inside of the meter housing 141 toward the receiving space inside the reactor vessel 100 .

The water level gauge 145 is configured to measure the level of the reloading water inside the reactor vessel 100 . The water level meter 145 may be divided into a contact type or a non-contact type.

The contact water level gauge 145 may be implemented as an electrode extending vertically into the reactor vessel 100 . The contact area of the electrode in contact with the reloading water may vary according to the level of the reloading water filled inside the reactor vessel 100 , and the output resistance value may vary according to the contact area of the electrode.

For example, as the surface area of the electrode in contact with the reload water increases, the output resistance value may decrease. The output resistance value of the water level meter 145 may be inversely proportional to the level of the reloading water.

The non-contact water level meter 145 may be implemented as an ultrasonic sensor.

The ultrasonic sensor emits ultrasonic pulses, the emitted ultrasonic pulses are reflected on the surface of the reloading water, and the ultrasonic pulses are detected. Since the movement time of the reflected ultrasonic signal is directly proportional to the movement distance of the ultrasonic wave and the speed of the ultrasonic wave is a predetermined value, the level of the reloading water can be measured through the movement distance of the ultrasonic wave.

In this embodiment, the water level meter 145 shows a state in which the reloading water is contacted with an electrode having a contact type configuration.

The water level meter 145 is connected to the control unit 149 through a power line.

The controller 149 may receive a detection signal from the water level gauge 145 and control the drain pump 131 according to the reloading water level of the reactor vessel 100 .

The closed circuit camera 147 may be installed to pass through the inside of the instrument housing 141 .

The closed circuit camera 147 is configured to photograph the internal state of the reactor vessel 100 .

The closed circuit camera 147 is connected to the control unit 149 through a signal line.

The control unit 149 may receive a signal from the closed circuit camera 147 and display the internal state of the reactor vessel 100 on a display panel such as a monitor disposed in the workshop. The operator can check the state of the inside of the reactor vessel 100 through the captured image displayed on the display panel.

The lighting lamp 146 is composed of a lamp that receives electric energy and converts it into light energy.

The lighting lamp 146 has a waterproof structure so that it can be used underwater. For example, the exterior of the lighting lamp 146 may be molded with a waterproof material.

The lighting lamp 146 may be installed to pass through the inside of the instrument housing 141 .

The lighting lamp 146 is configured to brightly illuminate the interior of the reactor vessel 100 so that the state inside the reactor vessel 100 can be photographed with the naked eye.

The lighting lamp 146 is connected to the control unit 149 through a signal line. The lighting lamp 146 may receive a control signal from the controller 149 to be turned on/off or its brightness may be adjusted.

The intake pipe 148 may be installed to pass through the inside of the instrument housing 141 .

The intake pipe 148 may be connected in communication with the vicinity of the control unit 149 through the intake tube.

The intake pipe 148 provides an air passage so that a vacuum is not formed inside the reactor vessel 100 .

If a vacuum is formed inside the reactor vessel 100 during operation of the drain pump 131 , it may be impossible to move the reloading water filled in the reactor vessel 100 toward the reloading tank 115 .

The intake pipe 148 may facilitate the operation of the drain pump 131 by allowing the pressure inside the reactor vessel 100 and the control unit 149 to equalize to atmospheric pressure when the drain pump 131 operates. .

The instrument flange 142 may be formed to protrude outward in a radial direction from the outer circumferential surface of the instrument housing 141 .

The instrument flange 142 may be disposed to face the second flange 122 in the longitudinal direction (up and down direction) of the instrument housing 141 .

A plurality of fastening holes may be formed to penetrate in the vertical direction in the measuring instrument flange 142 . A plurality of second fastening members 143 such as screws are configured to be respectively fastened to the second flange 122 of the measuring instrument flange 142 and the sealing plate 120 .

The plurality of fastening holes may be disposed to be spaced apart from each other in the circumferential direction.

Each of the plurality of second fastening members 143 may pass through the fastening hole and be fastened to the fastening groove of the second flange 122 .

According to this configuration, the measuring instrument flange 142 and the second flange 122 are fastened to each other, and the measuring instrument assembly may be installed to pass through the sealing plate 120 .

A meter gasket 144 may be disposed between the meter flange 142 and the second flange 122 .

The instrument gasket 144 is disposed between the instrument flange 142 and the second flange 122 and may be compressed by the fastening force of the second fastening member 143 .

The meter gasket 144 is configured to seal between the meter flange 142 and the second flange 122 .

The instrument gasket 144 may be formed in a disk shape while both sides thereof are flat.

According to this configuration, the instrument gasket 144 can maintain the airtightness between the instrument assembly 140 and the sealing plate 120 .

Hereinafter, a method of separating the reactor coolant pump 105 and the steam generator 103 from the inside of the reactor vessel 100 according to the present invention will be described.

10 is a conceptual diagram illustrating a state in which the nuclear fuel assembly 1041 is removed from the reactor vessel 100 according to the present invention.

11 is a conceptual diagram illustrating a state in which the sealing plate 120 descends along the guide pillar 126 to cover the upper end of the reactor vessel 100 in FIG. 10 .

12 is a conceptual diagram illustrating a state in which the pump assembly 130 is mounted on the sealing plate 120 in FIG. 11 .

13 is a conceptual diagram illustrating a state in which the measuring instrument assembly 140 is mounted on the sealing plate 120 in FIG. 12 and an operating state of the reloading water discharge device.

First, the nuclear fuel assembly 1041 of the reactor head 102, the upper guide structure 108, and the core 104 is extracted from the reactor vessel 100 before the reactor coolant pump 105 and the steam generator 103 are separated. and store it in a safe place (S110, see FIG. 10).

Next, a lifting equipment for lifting the nuclear reactor internal structure, for example, a ceiling crane of a nuclear reactor building, is attached to the lifting equipment insertion hole 128 of the sealing plate 120 (S120).

Sealed using the ceiling crane of the nuclear reactor building so that the guide pillar 126 extending vertically upward from the top of the flange portion 101 of the reactor vessel 100 is inserted into the guide pillar insertion hole 127 of the sealing plate 120 . The plate 120 is transferred to the upper end of the guide column 126 .

The overhead crane slowly lowers the sealing plate 120 along the guide column 126 with the guide column insertion hole 127 of the sealing plate 120 inserted into the guide column 126, so that the flange portion of the reactor vessel 100 (101) is installed on the top (S130, see FIG. 11).

Subsequently, after inserting the pump assembly 130 into the first flange 121 of the sealing plate 120 , the pump flange 1321 and the first flange 121 of the pump housing 132 are in contact with each other. By fastening the first fastening member 134 of the pump flange 1321 to the fastening hole of the pump flange 1321 and the fastening groove of the first flange 121 , respectively, the pump assembly 130 is fixed to the sealing plate 120 .

The pump gasket 133 is disposed between the pump flange 1321 and the first flange 121, and is compressed to the pump flange 1321 and the first flange 121 by the first fastening member 134 to the pump assembly ( 130) and the sealing plate 120 may be sealed (S140, see FIG. 12).

Subsequently, after inserting the measuring instrument assembly 140 into the second flange 122 of the sealing plate 120 , the measuring instrument flange 142 and the second flange 122 of the measuring instrument housing 141 are in contact with each other, a plurality of By fastening the second fastening member 143 to the fastening hole of the measuring instrument flange 142 and the fastening groove of the second flange 122 , respectively, the measuring instrument assembly 140 is fixed to the sealing plate 120 .

The instrument gasket 144 is disposed between the open instrument flange and the second flange 122, and is pressed against the instrument flange 142 and the second flange 122 by the second fastening member 143 to the instrument assembly 140. and the sealing plate 120 may be sealed (S150).

Thereafter, the power line, signal line, and intake pipe 148 of each of the pump assembly 130 and the measuring instrument assembly 140 are connected to the control unit 149 ( S160 ).

Next, the control unit 149 receives a detection signal from the water level gauge 145 and controls the operation of the drain pump 131 according to the level of the reloading water inside the reactor vessel 100 .

For example, the drain pump 131 is controlled by receiving a control signal from the controller 149 , and discharges the reloading water inside the reactor vessel 100 to the reloading water tank 115 ( S170 , see FIG. 13 ).

When the electric motor 136 of the drain pump 131 is operated, the impeller 135 connected to the shaft rotates. As the impeller 135 rotates, an axial flow of reloading water may be formed in the pump housing from the reactor vessel 100 toward the reloading water tank 115 .

The reloading water of the reactor vessel 100 rises along the suction pipe 137, flows into the inside of the pump housing 132 through the inlet 1381 of the pump housing 132, and in the inside of the pump housing 132 It flows out to the outside (upper part) of the pump housing 132 through the outlet 1382 of the pump housing 132 through the outer flow path of the impeller 135 and the electric motor 136 , that is, the reloading water tank 115 .

When the level of the reloading water falls below the nozzle of the reactor coolant pump 105 or the nozzle of the steam/feed water header 1032/1031 of the steam generator 103, the reactor coolant pump 105 or the steam generator 103 The sealing flange 114 is opened.

At this time, even if the sealing flange 114 is opened, the reloading water does not flow out of the reactor vessel 100 through the nozzle.

Next, the reactor coolant pump 105 and the steam generator 103 are separated from the reactor vessel 100 (S180).

Subsequently, a blinder flange is installed in the opened nozzle to block the nozzle (S190).

Next, the sealing plate 120 is removed from the upper portion of the reactor vessel 100 (S200).

Thereafter, the reactor internal structures including the reactor coolant pump 105 and the steam generator 103 are extracted from the reactor vessel 100 ( S210 ).

Subsequently, the reactor assembly including the reactor vessel 100 is inspected, and maintenance work of the extracted reactor coolant pump 105 and the steam generator 103 is performed (S220).

Next, the reactor coolant pump 105 and the steam generator 103 on which the inspection and maintenance work of the reactor assembly have been completed may be installed in the reactor vessel 100 by combining steps S110 to S210 described above.

Therefore, according to the present invention, in an integrated reactor in which the reactor coolant pump 105 and the steam generator 103 are installed to penetrate through the reactor vessel 100, the sealing plate 120 is formed to cover the upper end of the reactor vessel 100. It is mounted on the upper flange portion 101 of the reactor vessel 100 .

The pump assembly 130 is installed to penetrate the first flange 121 formed in the central portion of the sealing plate 120 , and the meter assembly 140 is installed in the second flange 122 eccentrically formed in the central portion of the sealing plate 120 . is installed penetratingly.

The water level meter 145 of the meter assembly 140 measures the level of the reloading water inside the reactor vessel 100 .

The control unit 149 receives a detection signal from the water level meter 145 and controls the drain pump 131 of the pump assembly 130 according to the level of the reloading water.

The drain pump 131 of the pump assembly 130 receives a control signal from the control unit 149 and discharges the reloading water filled in the reactor vessel 100 to the reloading water tank 115 .

Accordingly, when performing maintenance and inspection of the reactor assembly in an integrated reactor in which the reactor coolant pump 105 and the steam generator 103 are installed through the reactor vessel 100, the number of reloads filled in the reactor vessel 100 is prevented from flowing out of the reactor vessel 100 , the water level of the reloading water tank 115 is kept constant, and the reloading water inside the reactor vessel 100 is discharged, so that the reactor coolant pump 105 and the steam generator It is possible to extract (103) from the reactor vessel (100).

In addition, the reloading water discharge device of the present invention is not required in the existing commercial nuclear power plant facility, but in an integrated reactor such as SMART, the steam generator 103 and the reactor coolant pump 105 are installed so as to be penetrated into the reactor vessel 100 or the reactor It is absolutely necessary to perform inspection and maintenance work on the assembly.

Therefore, according to the present invention, during maintenance of the integrated reactor, reloading water is supplied to and filled in the reactor vessel 100 and the reloading water tank 115 disposed at the upper end thereof, and the nuclear fuel assembly 1041 is placed in the reactor vessel 100 . After removal from the reactor, before separating the steam generator 103 and the reactor coolant pump 105, the sealing plate 120 descends along the guide column and is mounted to cover the upper opening of the reactor vessel.

Then, the drain pump 131 and the water level gauge 145 are mounted on the sealing plate.

The water level gauge 145 detects the level of the reloading water of the reactor vessel 100 , and the drain pump 131 is controlled by the controller according to the detected level of the reactor vessel 100 .

The drain pump 131 allows the level of the reloading water inside the reactor vessel 100 to be lower than the lower end of the steam generator 103 through a suction pipe 137 extending directly downwardly from the lower part of the sealing plate 120 toward the core. The reloading water may be pumped up until it is discharged and discharged to the reloading water tank 115 .

Accordingly, while maintaining the water level of the reloading water tank 115 constant, the reloading water level of the reactor vessel 100 is lowered below the lower end of the steam generator 103 , thereby generating the steam generator 103 and the reactor coolant pump 105 . ), even if the sealing flange 114 installed in the nozzle of the reactor vessel 100 is opened to separate and install the reactor vessel 100 , it is possible to prevent the radioactively contaminated reloading water from leaking to the outside of the reactor vessel 100 .

In addition, since leakage of radioactivity to the outside of the reactor vessel 100 is prevented, the safety of the nuclear power plant can be secured.

In addition, during maintenance of the reactor assembly, installation and disassembly of the reactor coolant pump 105 and the steam generator 103 are easy, and inspection and maintenance work on the reactor assembly can be performed.

10: water supply system 11: water supply valve
12: main water pipe 13: turbine system
14: chief complaint engine 15: steam valve
100: reactor vessel 101: flange portion
102: reactor head 103: steam generator
1031: water header 1032: steam header
104: core 1041: nuclear fuel assembly
105: reactor coolant pump 106: pressurizer
107: core support barrel 108: upper guide structure
109: control rod driving device 110: control rod
111: first nozzle 112: second nozzle
113: third nozzle 114: sealing flange
115: reload tank 120: sealing plate
121: first flange 122: second flange
123: mounting portion 124: sealing gasket
125: reinforcing bar 126: guide column
127: guide post insertion hole 128: lifting equipment insertion hole
130: pump assembly 131: drain pump
132: pump housing 1321: pump flange
133: pump gasket 134: first fastening member
135: impeller 136: electric motor
137: suction pipe 1381: inlet
1382: outlet 139: non-return valve
140: instrument assembly 141: instrument housing
142: measuring instrument flange 143: second fastening member
144: instrument gasket 145: water level instrument
146: lighting lamp 147: closed circuit camera
148: intake pipe 149: control unit

Claims (19)

a sealing plate mounted on the upper flange portion of the reactor vessel to cover the upper opening of the reactor vessel;
a water level meter mounted on the sealing plate and measuring the level of reloading water filled in the reactor vessel;
a drain pump mounted on the sealing plate and discharging the reloading water to a reloading water tank installed at an upper portion of the reactor vessel; and
and a control unit controlling an operation of the drain pump according to the level of the reloading water detected by the water level meter. According to claim 1,
The drain pump is
a pump housing extending in the vertical direction to pass through the sealing plate;
an impeller rotatably installed in the pump housing and sucking the reloading water;
an electric motor installed inside the pump housing so as to be connected to the impeller and driving the impeller; and
and a suction pipe extending from the pump housing to an inner lower portion of the reactor vessel to suck the reload water. 3. The method of claim 2,
A first flange is formed to penetrate in the vertical direction in the central portion of the sealing plate,
The drain pump is
a pump flange that protrudes in a radial direction from an outer circumferential surface of the pump housing passing through the first flange, and is disposed to overlap the first flange in a vertical direction; and
Reloading water discharge device including a plurality of first fastening members fastening the pump flange and the first flange. 4. The method of claim 3,
The drain pump is
and a pump gasket disposed between the pump flange and the first flange to seal between the sealing plate and the drain pump. 3. The method of claim 2,
The drain pump is
and a non-return valve installed inside the pump housing to prevent a reverse flow of the reload water from the reload tank to the reactor vessel. According to claim 1,
A second flange is formed eccentrically through the sealing plate,
The water level meter,
a meter housing installed to pass through the second flange and accommodating the water level meter;
a measuring flange protruding in a radial direction from the outer circumferential surface of the measuring instrument housing and disposed to overlap the second flange in a vertical direction; and
A reloading water discharge device including a plurality of second fastening members for fastening the meter flange and the second flange. 7. The method of claim 6,
A meter gasket is disposed between the meter flange and the second flange to seal between the sealing plate and the meter housing. 7. The method of claim 6,
an illumination lamp installed inside the instrument housing to illuminate the inside of the reactor vessel; and
The reloading water discharge device further comprising a closed circuit camera installed inside the instrument housing to photograph the internal state of the reactor vessel. 7. The method of claim 6,
The reloading water discharging device further comprising an intake pipe installed inside the instrument housing to equalize the pressure between the reactor vessel and the reloading water tank. According to claim 1,
The sealing plate is
a mounting portion protruding from a lower portion of the sealing plate to an upper flange portion of the reactor vessel; and
and a sealing gasket installed on a bottom surface of the mounting part to seal between the sealing plate and an upper flange part of the reactor vessel. reactor vessel;
a reload tank installed on the upper part of the reactor vessel;
a steam generator installed inside the reactor vessel;
a reactor coolant pump installed to pass through the reactor vessel;
a sealing plate disposed between the reload tank and the reactor vessel to seal between the reload tank and the reactor vessel;
a water level meter mounted on the sealing plate and measuring the level of reloading water filled in the reactor vessel;
a drain pump mounted on the sealing plate and discharging the reloading water to a reloading water tank installed at an upper portion of the reactor vessel; and
and a control unit controlling an operation of the drain pump according to the level of the reloading water detected by the water level meter. 12. The method of claim 11,
The sealing plate is
formed in the form of a disk,
It includes a plurality of guide pillar insertion holes formed to penetrate in the thickness direction at the edge of the sealing plate,
The reactor vessel,
The integrated reactor further comprising a plurality of guide pillars extending upwardly from the upper flange of the reactor vessel to the inner side of the reloading tank to guide the vertical movement of the sealing plate so as to be inserted through the guide pillar insertion hole. 13. The method of claim 12,
An integrated reactor in which a plurality of lifting equipment insertion holes are formed to protrude from an upper surface of the sealing plate so as to be coupled with a lifting equipment for lifting the sealing plate. 12. The method of claim 11,
The sealing plate is
a first flange formed to penetrate vertically in a central portion of the sealing plate so that the drain pump can penetrate the sealing plate;
a second flange disposed to be spaced apart from the first flange in a radial direction so that the water level gauge can penetrate the sealing plate and formed to penetrate vertically through the sealing plate; and
and a plurality of reinforcing bars extending radially from the outer peripheral surface of the first flange to the outermost end of the sealing plate and protruding upward from the upper surface of the sealing plate. 12. The method of claim 11,
A first flange is formed to penetrate in the vertical direction in the central portion of the sealing plate,
The drain pump is
a pump housing extending to protrude in the vertical direction of the sealing plate through the first flange;
an impeller rotatably installed in the pump housing and sucking the reloading water;
an electric motor installed inside the pump housing so as to be connected to the impeller and driving the impeller;
a suction port positioned lower than the sealing plate and formed at a lower end of the pump housing so that the reloading water is sucked into the pump housing;
a discharge port positioned higher than the sealing plate so that the reloading water flows out from the pump housing to the reloading water tank and formed at an upper end of the pump housing; and
and a suction pipe extending vertically downward from the suction port of the pump housing so that the reloading water rises to the suction port. 16. The method of claim 15,
The steam generator is disposed lower than the reactor coolant pump,
The steam generator,
a heat transfer tube capable of flowing inside the cooling water supplied from the water supply system and generating steam by exchanging the cooling water with the reactor coolant circulated inside the reactor vessel;
a water supply header provided at the lower end of the steam generator and installed to pass through the reactor vessel to deliver the cooling water to the heat transfer tube;
An integrated reactor comprising a steam header provided at the upper end of the steam generator and installed to pass through the reactor vessel, the steam generated from the heat transfer tube being delivered to the turbine system. 17. The method of claim 16,
The lower end of the suction pipe extends to be lower than the water supply header. A nuclear reactor vessel having a core loaded with a nuclear fuel assembly, a reloading water tank installed on an upper portion of the reactor vessel, a steam generator installed inside the reactor vessel, and a reactor coolant pump installed through the reactor vessel In the method for discharging reload water of a nuclear reactor,
supplying reloading water to the reactor vessel and the reloading tank during maintenance to fill the reloading tank to a certain height;
removing the nuclear fuel assembly from the reactor vessel;
inserting a sealing plate into a plurality of guide pillars extending vertically from the upper flange portion of the reactor vessel, and lowering the sealing plate along the plurality of guide pillars to cover the upper opening of the reactor vessel;
mounting a drain pump through a first flange formed to pass through the sealing plate;
mounting a water level gauge through a second flange formed to pass through the sealing plate;
The operation of the drain pump is controlled according to the level of the reloading water level of the reactor vessel detected by the water level meter to maintain a constant water level in the reloading tank, and the reloading water of the reactor vessel is transferred to the reloading tank. A method of discharging the reloading water of an integrated nuclear reactor comprising the step of discharging. 19. The method of claim 18,
and separating and extracting the reactor coolant pump and the steam generator when the water level of the reactor vessel is lower than that of the steam generator.

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