WO2016122103A1

WO2016122103A1 - External air intake plate device below steam generator of pressurized light water reactor

Info

Publication number: WO2016122103A1
Application number: PCT/KR2015/013363
Authority: WO
Inventors: 문인득
Original assignee: 문인득
Priority date: 2015-01-29
Filing date: 2015-12-08
Publication date: 2016-08-04
Also published as: KR101860607B1; KR20160093272A

Abstract

The present invention relates to a device for preventing the vibration of a nuclear reactor by preventing the thermal deformation of a sliding base that supports a steam generator of the nuclear reactor, and provides an external air intake plate device below the steam generator of the nuclear reactor, which comprises: a shim plate that is disposed along the coupling surface between the lower surface of a skirt support of the steam generator and the upper surface of the sliding base and has a plurality of anchor holes formed therein through which stud anchors pass; and a plurality of vent notches radially formed on the upper surface of the shim plate and concavely formed at an equal interval in the circumferential direction of the shim plate, wherein the thermal deformation of the sliding base is prevented by performing natural cooling by introducing air outside the skirt support into the stagnated air area inside the sliding base and the skirt support through the plurality of vent notches.

Description

Outside air suction plate device under the pressurized water reactor type steam generator

The present invention relates to an apparatus for air circulation in a stagnated air area located below a steam generator, and more particularly, between a bottom surface of a skirt support for supporting a reactor steam generator and a mating surface of a sliding base. By placing an air-circulating shim plate to allow the outside air to enter the stagnated air area inside the stay cylinder and skirt support, naturally cooling the hot zone and The present invention relates to an outside air suction plate device under the reactor steam generator for effectively preventing the transfer from the steam generator to the sliding base to prevent vibration of the reactor due to thermal expansion deformation of the sliding base.

In general, nuclear reactors in Korea, for example, Conversetion Engineering (CE) System Plus 80 (Hanbit 3, 4), Korean standard nuclear power plants (Hanul 3, 4, 5, 6 and Hanbit 5, 6) Units), OPR1000 (Shin-Gori 1,2), APR1400 (Shin-Gori 3,4, Shin-Uljin 1,2, UAE Nuclear Power Plants 1-4), 2-loop Pressurized Water Reactor.

In general, a nuclear power plant (hereinafter referred to simply as a “nuclear reactor”) is a reactor coolant system (RCS) in a containment building, as described in Korean Patent Publication No. 10-1473665, "Pipe support device for replacing parts of a nuclear power plant." Reactor Coolant System) is provided.

Such a reactor coolant system has a reactor containing a reactor and at least one heat transfer circuit connected thereto.

Each circuit includes a steam generator and at least one coolant pump for circulating coolant between the reactor and the steam generator.

In addition, the circuit includes a pressurizer to keep the temperature and pressure of the coolant constant.

The first large diameter pipe or hot leg is connected to one side of the reactor and the suction side of the coolant chamber of the steam generator to contact the core in the reactor to transfer the heated coolant to the steam generator.

A circulation pipe called a cross-over leg connects one side of the discharge part of the coolant chamber of the steam generator and one side of the vortex chamber suction part of the coolant pump.

The cold leg connects between the vortex chamber of the coolant pump and the reactor. In addition, the coolant cooled in the steam generator and drawn out by the coolant pump is transferred to the reactor through a circulation pipe and a low temperature pipe to cool the core.

In such a reactor, each steam generator 1 has a substructure as shown in FIG. 1.

That is, the steam generator 1 has a stay cylinder 10 which is maintained at a high temperature, and has a skirt support 20 of a cylindrical structure that supports it at the bottom thereof.

The skirt support 20 is a cylindrical steel structure located on the lower side of the stay cylinder 10, the lower surface 20a of the upper portion of the sliding base 30, as shown in an enlarged view in FIG. It is a structure directly contacting the surface 30a and fixedly supported by the plurality of stud anchors 32.

Such a sliding base 30 is supported to be slidable on a plurality of, for example, four hemispherical sliders 42 provided on the forged anchor plate 40 and the bearing plate 41 during the operation of the reactor. It is designed to accommodate the thermal expansion and fine movement that occur.

In addition, since the steam generator 1 generates high heat during operation, the thermal insulation material 50 for preventing such high heat from being transferred to the sliding base 30 at the lower portion may include a stay cylinder 10 and a skirt support 20. I attach it to) part.

In the conventional sliding base 30, the keys 46 protruding from the forged anchor plate 40 are positioned in the key holes 48, respectively.

The steam generator 1 is a high heat of 300 ° C or more is generated inside the stay cylinder 10 during operation, this high heat is transmitted to the lower side to thermally deform the sliding base (30).

In order to prevent this, the heat insulating material 50 is mounted on the lower portion of the stay cylinder 10, but the heat insulating material 50 does not completely block heat, and the phenomenon of heat conduction directly through the skirt support 20, etc. The sliding base 30 is heated and thermally deformed by various factors.

In particular, the skirt support 20 of the steam generator 1 is a cylindrical support steel structure, in which a stagnated air area 80 is formed.

This air stagnation zone 80 is located on the upper side of the heat insulating material 50 of the stay cylinder 10, around the skirt support 20 in the form of a cylindrical wall, the sliding base 30 on the lower side The central area of the upper surface of the) is arranged, resulting in a closed space.

This air stagnation zone 80 acts as a space for radiating high heat of the steam generator 1, thereby causing a serious thermal deformation of the sliding base 30.

Problems related to this are described in detail below.

That is, thermal deformation of the sliding base 30 may suppress free movement due to thermal expansion of the sliding base 30 generated during operation of the power plant, or may cause interference with surrounding structures on the upper part of the steam generator 1. This results in structural vibration of the steam generator 1 and the coolant pump.

This structural vibration causes the tubular wear and vibration stress of the steam generator 1, and when operated at a long cycle, boric acid leakage causes the fatigue of boron embrittlement in small diameter pipes due to boric acid accumulation.

In addition, as a construction factor of the reactor piping, the final connection welding of the intermediate tube and the steam generator 1 nozzle is left as a residual load on the sliding base 30 and the pump vertical support due to the welding shrinkage. As a result of this residual load, settlement of the sliding base 30 due to welding shrinkage occurs, and settlement typically occurs in the range of about 1 mm after installation of the steam generator 1 and after final connection welding.

This settlement can be seen as a load remaining on the sliding base 30, the residual load is characterized by increasing the frictional force on the sliding base 30 in the initial stage of the reactor to inhibit the sliding operation in the lateral direction.

In addition, when the sliding base 30 is thermally deformed in this manner, the steam generator 1 is inclined to operate as a result of this, and even after stopping at room temperature, a phenomenon in which components are displaced may appear successively.

As a result, if the sliding base 30 is deformed and not level, the steam generator 1 is tilted and the vibration stress of the reactor due to the deformation and interference of the reactor coolant pump and the associated support structure of the steam generator 1 increase stress).

This vibration stress not only causes the tubular wear of the steam generator (1), but also causes the wear of internal parts of the reactor coolant pump and the fatigue cracking caused by the fatigue of pipes connected to the RCS system. have.

Long periods of operation in this state lead to leakage of the mechanical seal and small diameter piping of the reactor coolant pump.

Therefore, in the art, it is possible to prevent thermal deformation of the sliding base 30 of the reactor to develop a technology capable of preventing the tubular wear of the steam generator 1 due to the structural vibration of the reactor and the wear of the reactor coolant system equipment. This situation is desperately needed.

SUMMARY OF THE INVENTION An object of the present invention is to solve the above problems, and is formed in the inner space of the sliding base and the skirt support by applying an air circulation shim plate between the lower surface of the skirt support and the upper surface of the sliding base. It is to provide an outside air suction plate device under the reactor steam generator by reducing the high heat transferred from the steam generator to the sliding base by natural cooling by introducing the outdoor air into the air stagnation zone, and effectively prevent the thermal deformation of the sliding base.

In addition, another object of the present invention is to reduce the phenomenon of high heat directly from the skirt support of the steam generator to the sliding base directly, thereby reducing the outside air suction plate device of the reactor steam generator to effectively prevent thermal deformation of the sliding base In providing.

In order to achieve the above object, the present invention, in the device for preventing the thermal deformation of the sliding base 30 for supporting the reactor steam generator 1, the lower portion of the skirt support 20 of the steam generator (1) A shim plate 110 disposed along an engagement surface between the surface 20a and the upper surface 30a of the sliding base 30 and having a plurality of anchor holes 112 through which the stud anchors 32 respectively pass; It is formed to pass through the shim plate 110 in the radial direction from the upper surface (30a) of the shim plate 110 so that the air outside the skirt support 20 is inside the sliding base 30 and the skirt support 20 A plurality of vent notches 120 recessed to form an air passage into the air stagnation zone 80 of the plurality of vent notches 120; And at least one vent 140 formed in the skirt support 20 such that an air stagnation zone 80 inside the sliding base 30 and the skirt support 20 is exposed to the outside atmosphere of the skirt support 20. Including the; through the plurality of vent notches 120, the air outside the skirt support 20 is introduced into the air stagnation zone 80, and is discharged through the vent 140 to achieve a natural circulation of air By being configured, it is characterized in that configured to prevent the thermal deformation of the sliding base (30).

Preferably, the vent notches 120 are each formed as grooves having a “V” -shaped cross section, and a plurality of vent notches 120 are formed at equal intervals circumferentially between the anchor holes 112 of the shim plate 110.

More preferably, the vent notches 120 are each formed as grooves having a “V” shaped cross section, and are circumferentially between the anchor holes 112 of the shim plate 110 and on the respective anchor holes 112. Many are formed at equal intervals.

Most preferably, the shim plate 110 is divided into several pieces are configured to facilitate assembly.

According to the present invention, a shim plate is disposed between the lower surface of the skirt support of the steam generator and the upper surface of the sliding base, and a plurality of vent notches are formed on the upper surface of the shim plate, so that the air outside the skirt support is the sliding base. And a natural circulation path for the air to be introduced into the stagnant air region inside the skirt support and to exhaust the air through at least one vent formed in the skirt support.

Therefore, according to the present invention, it is possible to eliminate the high heat congestion in the air stagnation zone, thereby greatly lowering the temperature, and to cool the high temperature heat conducting directly from the skirt support under the steam generator to the sliding base to cool the cold air passing through the notches of the simple rate. As a result, the thermal deformation of the sliding base can be effectively prevented, and structural vibration of the reactor can be prevented, thereby effectively preventing the tubular wear of the steam generator and the wear of the reactor coolant system equipment.

1 is a cross-sectional view showing a structure in which the lower structure of the reactor steam generator according to the prior art, in particular the lower surface of the skirt support is in direct surface contact with the upper surface of the sliding base.

FIG. 2 is an exploded cross-sectional view illustrating a structure in which a shim plate is disposed between a skirt support and a sliding base in the outside air suction plate device below the reactor steam generator according to the present invention.

3 is an external perspective view showing a shim plate provided in an outside air suction plate device below the reactor steam generator according to the present invention.

4 is a plan view and an enlarged view illustrating a structure in which a plurality of vent notches of a shim plate are formed at equal circumferential intervals between anchor holes of a shim plate in an outside air suction plate device below the reactor steam generator according to the present invention.

FIG. 5 is a plan view illustrating a structure in which a plurality of vent notches of a shim plate are formed between the anchor holes of the shim plate and circumferentially equally spaced on each anchor hole in the air suction plate device below the reactor steam generator according to the present invention. And enlarged view.

FIG. 6 is a cross-sectional view illustrating an operation in which air is introduced through vent notches with a shim plate disposed between a skirt support and a sliding base in an outside air suction plate device below the reactor steam generator according to the present invention.

Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the drawings.

The outside air suction plate device 100 under the reactor steam generator according to the present invention is a device for preventing the vibration of the reactor by preventing thermal deformation of the sliding base 30 supporting the reactor steam generator (1).

The outside air suction plate device 100 of the reactor steam generator bottom according to the present invention, as shown in Figure 2, the lower surface 20a of the skirt support 20 of the steam generator, and the upper surface of the sliding base 30 Shim plate 110 is disposed along the coupling surface between the (30a).

The structure of the shim plate 110 is shown in detail in FIG. 3.

That is, the shim plate 110 has a circular annular structure, and is formed on a coupling surface formed between the lower surface 20a of the skirt support 20 and the upper surface 30a of the sliding base 30. It has a coincidence planar structure, and a plurality of anchor holes 112 through which the stud anchors 32 respectively pass are formed at equal circumferential intervals.

In addition, such shim plate 110 has a plurality of vent notches 120 on its upper surface.

Such vent notches 120, as shown in the enlarged view in FIG. 4, are preferably each formed of grooves having a “V” shaped cross section, and are circumferentially between the anchor holes 112 of the shim plate 110. Many are formed at equal intervals in the direction.

Each of the vent notches 120 is formed in the upper surface of the shim plate 110 to be concave in a radial direction. The plurality of vent notches 120 are air inside the sliding base 30 and the skirt support 20. It functions as an air passage for introducing air outside the skirt support 20 into the stagnation zone.

On the other hand, the vent notches 120 as a modified embodiment thereof, as shown in Figure 5, between the anchor hole 112 of the shim plate 110 and the circumference on each anchor hole 112 It may be a structure formed a plurality of at equal intervals in the direction.

In such a structure, the vent notches 120 formed on the respective anchor holes 112 expose the stud anchors 32 to the outside, and thus, from the skirt support 20 to the sliding base 30 through the stud anchors 32. It is possible to cool the high heat of heat conduction.

In addition, the outside air suction plate device 100 of the lower portion of the steam generator according to the present invention includes at least one ventilation hole 140 on one side of the skirt support 20, so that the sliding base 30 and the skirt support 20 are located inside. The air stagnation zone is exposed to the outer atmosphere of the skirt support 20.

The vent 140 may be configured in the form of an opening formed along the circumference of the skirt support 20, through which the operator enters the inside of the skirt support 20 (man-way) It also functions as).

Therefore, the vent 140 is such that the air outside the skirt support 20 introduced into the air stagnation zone through the vent notches 120 is discharged through the vent 140 so that natural circulation of the air is achieved. do.

The outside air suction plate device 100 of the reactor steam generator lower portion according to the present invention configured as described above is between the lower surface 20a of the skirt support 20 of the steam generator and the upper surface 30a of the sliding base 30. The shim plate 110 is disposed along the engaging surface of the skirt support 20, the shim plate 110, and the sliding base 30 are integrally fixed through the stud anchor 32.

An enlarged cross section of the structure thus joined is shown in FIG. 6.

That is, the outside air suction plate device 100 under the reactor steam generator according to the present invention is disposed between the lower surface 20a of the skirt support 20 of the steam generator and the upper surface 30a of the sliding base 30. A plurality of vent notches 120 are formed on the upper surface of the shim plate 110 so that the air outside the skirt support 20 flows into the air stagnation zone inside the sliding base 30 and the skirt support 20, A natural circulation path of the air is discharged through the at least one vent 140 formed in the skirt support 20.

In such a structure, the plurality of vent notches 120 may be formed in circumferential equal intervals between the anchor holes 112 of the shim plate 110 and / or on each anchor hole 112.

In such a structure, the plurality of vent notches 120 formed between the respective anchor holes 112 serve to cool and block the high heat that is conducted from the skirt support 20 to the sliding base 30. The vent notches 120 formed on the hole 112 function to cool the high heat thermally conducted from the skirt support 20 to the sliding base 30 through the stud anchors 32.

In addition, according to the present invention, the air outside the skirt support 20 introduced into the air stagnation zone through the vent notches 120 forms a path through which the natural circulation of air is discharged through the vent 140. It is possible to significantly lower the temperature of the air stagnation zone under the stay cylinder.

Therefore, according to the present invention, it is possible to effectively prevent thermal deformation of the sliding base 30, and to prevent structural vibration of the reactor.

Although the present invention has been described in detail with reference to the accompanying drawings, the present invention is not limited to such a specific structure. Those skilled in the art may variously modify or change the present invention without departing from the spirit and scope of the present invention as set forth in the claims below. For example, the vent notches 120 may be formed in various cross-sections, for example, "U" -shaped cross sections or other cross-sections, rather than "V" -shaped cross sections. In addition, the shim plate may be divided into a plurality of parts may be configured to facilitate assembly. On the other hand, without using a separate shim plate may be configured by forming a plurality of vent notches (concave in the radial and circumferential direction on the lower surface of the skirt support or the upper surface of the sliding base). Nevertheless, such simple design modifications or variations will be made clear in advance that all obviously fall within the scope of the present invention.

Claims

In the device for preventing the thermal deformation of the sliding base (30) for supporting the reactor steam generator (1),

A plurality of stud anchors 32 are disposed along the mating surface between the lower surface 20a of the skirt support 20 of the steam generator 1 and the upper surface 30a of the sliding base 30, respectively passing through the stud anchors 32. Shim plate 110 having anchor holes 112 formed therein;

It is formed to pass through the shim plate 110 in the radial direction from the upper surface (30a) of the shim plate 110 so that the air outside the skirt support 20 is inside the sliding base 30 and the skirt support 20 A plurality of vent notches 120 recessed to form an air passage into the air stagnation zone 80 of the plurality of vent notches 120; And

At least one ventilation opening 140 formed in the skirt support 20 so that an air stagnation zone 80 inside the sliding support 30 and the skirt support 20 is exposed to the outside atmosphere of the skirt support 20; Including air through the plurality of vent notches 120, the outside of the skirt support 20 is introduced into the air stagnation zone 80, and is discharged through the vent 140 to configure the natural circulation of air Thereby, the outside air suction plate device (100) below the reactor steam generator, characterized in that configured to prevent thermal deformation of the sliding base (30).
According to claim 1, wherein the vent notches 120 are each formed as a groove of the "V" shaped cross section, characterized in that formed in the circumferential equal intervals between the anchor holes 112 of the shim plate (110) The outside air suction plate device 100 at the bottom of the reactor steam generator.
2. The vent notches 120 are each formed as grooves of a “V” shaped cross section, and are circumferentially between the anchor holes 112 of the shim plate 110 and on the respective anchor holes 112. External air suction plate device 100 of the reactor steam generator lower, characterized in that formed in a plurality of equal intervals in the direction.
The outside air suction plate device (100) according to any one of claims 1 to 3, wherein the shim plate (110) is divided into several pieces and configured to facilitate assembly.