JP2003035792A - Reactor renewal construction method for nuclear power facility - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a reactor renewal construction method for nuclear power facility which facilitates the shipping of a reactor having passed its durability and sending in and placing of a new reactor. SOLUTION: A reactor pressure vessel 10 placed in a reactor building 1 and having passed its durability is combined with a reactor shield wall 20 by an upper combiner 40 and a lower combiner 50 and is lifted with a crane by way of a lifting metal 60 tightened together by fixing bolt 14 of a pressure vessel upper lid 10A.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for replacing an aged reactor in a nuclear power plant, and more particularly to a method for carrying out and carrying in a reactor pressure vessel.

[0002]

2. Description of the Related Art In a nuclear power plant, its service life depends on the service life of the nuclear reactor. Nuclear power generation facilities that have passed the design life of the reactor must be decommissioned by decommissioning the aging reactor.

By the way, when a nuclear power generation facility is abandoned, it is necessary to install a new power generation facility in order to secure the amount of power supply, but recently, a new nuclear power generation facility is newly constructed in a new place. It is expected that it will take a lot of time and cost and that it will be difficult to select the installation site.

In order to upgrade the reactor of the existing facility, it is considered to disassemble the pressure vessel and reactor internals of the decommissioned reactor to a predetermined size and carry them out, and install a new reactor. To be

[0005]

However, there is a problem that the work of dismantling and carrying out a nuclear reactor is extremely troublesome because it must be performed while preventing exposure to radiation.

[0006] The present invention has been made in view of the above-mentioned problems to be solved, and it is possible to easily carry out a reactor whose useful life has expired and carry in and install a new reactor in a nuclear power generation facility. The purpose is to provide a renewal method.

[0007]

Means for Solving the Problems A nuclear reactor renewal method for a nuclear power generation facility according to the present invention which achieves the above object, is a reactor pressure vessel including an internal structure at the time of nuclear reactor renewal of a nuclear power generation facility, It is characterized in that it is connected to the surrounding reactor shield wall by a connecting means and is carried out integrally from the reactor building.

Further, when the nuclear reactor of the nuclear power generation facility is renewed, the reactor pressure vessel including the reactor internals and the surrounding reactor shielding wall are connected by a connecting means, and the reactor pressure vessel is integrally carried into the reactor building. It is characterized by

Further, the coupling means is configured such that the coupling member fixed to the reactor shielding wall is coupled to a stabilizer bracket projecting around the upper portion of the reactor pressure vessel. To do.

Further, in the coupling means, a coupling member fixed to the reactor shielding wall is coupled to a stabilizer bracket projecting around an upper portion of the reactor pressure vessel and is fixed to the reactor pressure vessel. The support member is configured to engage with an upper edge of the conduit passage opening opening in the reactor shield wall.

[0011]

BEST MODE FOR CARRYING OUT THE INVENTION Embodiments of the present invention will be described below with reference to the accompanying drawings.

FIG. 1 is a conceptual diagram for explaining a method for carrying out a reactor pressure vessel to which the nuclear reactor renewal method of the present invention is applied, and FIG. 2 is an enlarged view of the reactor pressure vessel.

In a reactor building 1 of the illustrated nuclear power generation facility, a containment vessel 2 is constructed of concrete, and a reactor pressure vessel 10 is arranged inside the containment vessel 2. Around the reactor pressure vessel 10, a cylindrical reactor shielding wall 20 is installed upright so as to cover the inside of a steel plate outer surface plate with concrete.

The reactor pressure vessel 10 includes a reactor shield wall 2
A plurality of pipelines 11 that are piped through through-holes 21 formed in 0 are connected to the peripheral surface thereof, and the control rod drive mechanism 1 is provided on the lower side.
Two are provided.

A plurality of stabilizer brackets 13 are provided on the outer surface of the upper portion of the reactor pressure vessel 10 at predetermined intervals in the circumferential direction, and the stabilizer brackets 13 and the upper edge of the reactor shield wall 20 are provided with stabilizers. Three
Connected through 0.

As described above, the reactor pressure vessel 10 installed in the reactor building 1 is joined and integrated with the reactor shield wall 20 by the upper joining portion 40 and the lower supporting portion 50 as joining means after the end of its useful life. Then, it is hoisted and carried out by a crane (not shown) via a hoisting metal fitting 60 which is fastened and fixed together with the fixing bolt 14 of the pressure vessel upper lid 10A. still,
At that time, the periphery is covered with a curing sheet 15 (not shown in FIG. 1).

The upper coupling portion 40 is shown in plan view in FIG.
As shown in the front view in FIG. 4B and the side view in FIG. 4, a joint fitting 41 as a joint member fixed to the reactor shield wall 20.
Is connected to a stabilizer bracket 13 protruding from the reactor pressure vessel 10.

The stabilizer bracket 13 is provided at the tip of a base portion 13A protruding from the outer surface of the reactor pressure vessel 10.
It is formed by including a plate-shaped portion 13B which projects vertically and horizontally, and the coupling fitting 41 is engaged with the left-right projected portion of the plate-shaped portion 13B.

The coupling fitting 41 is an inverted U-shaped engaging portion 41A.
The fixing portion 41B is formed by extending laterally from the lower end of one (outer) arm, and is fixed to the upper surface of the reactor shielding wall 20 by welding with the fixing portion 41B, and the engaging portion 41A is fixed to the stabilizer bracket 13. The plate-shaped portion 13B is engaged with from above. Incidentally, 41C and 41D in the figure are bolts for adjustment.

As shown in the sectional view of the relevant portion in FIG. 5, the lower support portion 50 is a plate-like support fitting 51 as a support member welded and fixed to the outer peripheral surface of the reactor pressure vessel 10, and the reactor shield wall 20. Is configured to support the upper inner surface of the opening 21 that penetrates the recirculation system pipeline 11. That is, on the outer peripheral surface of the reactor pressure vessel 10, the support fitting 51 is firmly welded and fixed by bringing its upper surface into contact with the upper inner surface of the opening 21 of the recirculation system conduit 11 of the reactor shielding wall 20, Furnace pressure vessel 1
The reactor shield wall 20 can be supported by lifting 0. Further, the reactor shield wall 20 is horizontally cut at a position corresponding to the opening 21: X, and the upper side of the cut portion is integrated with the reactor pressure vessel 10. In this configuration, the base portion below the cut portion of the reactor shielding wall 20 remains, but if it is possible in terms of weight and structure, the base portion should be carried out without cutting in the middle. Is also good.

In this way, by connecting the reactor pressure vessel 10 and the reactor shield wall 20 and carrying them out integrally,
The reactor pressure vessel 10 and the reactor shielding wall 20 including the internal structure can be carried out in a short time, the work efficiency can be improved, and the exposure dose during the work can be significantly reduced. Further, by using the existing stabilizer bracket 13 for connecting the reactor pressure vessel 10 and the reactor shield wall 20, the work time such as welding at the site can be shortened,
A reliable connection is possible.

On the other hand, after the reactor pressure vessel 10 and the reactor shield wall 20 have been removed, the loading of a new reactor pressure vessel and the construction of the reactor shield wall are carried out at a different location from the atoms in which the internal structures are set. The reactor pressure vessel is connected to the reactor pressure vessel in the same way as the above-mentioned unloading, the reactor shielding wall is integrally supported, and the crane is lifted by a crane to be loaded into the reactor building for installation. As a result, the installation time can be shortened, and the installation work in the remaining radiation environment can be reduced to prevent the exposure.

In this configuration example, the reactor pressure vessel 20 and the reactor shield wall 20 are coupled and supported above and below the upper coupling portion 40 and the lower support portion 50, which enables stable coupling and supporting. Become. However, it is not always necessary to provide the upper and lower parts, and only the upper coupling part 40 may be provided. In addition, the reactor pressure vessel 20 and the reactor shield wall 2
The connection structure of 0 is not limited to the above-mentioned configuration example, and can be changed as appropriate.

[0024]

As described above, according to the nuclear reactor renewal method for nuclear power generation facilities according to the present invention, the reactor pressure vessel including the reactor internals and the surrounding reactor shield wall are connected by the connecting means. By connecting and integrally carrying out from the reactor building, the reactor pressure vessel and the reactor shielding wall can be carried out in a short time, work efficiency can be improved, and exposure dose during work can be greatly reduced.

Further, the reactor pressure vessel including the reactor internals and the surrounding reactor shielding wall are coupled by coupling means, and the reactor pressure vessel is integrally carried into the reactor building, so that the reactor pressure vessel can be delivered in a short time. Also, the reactor shield wall can be brought in, and the exposure work can be prevented by reducing the installation work in the remaining radiation environment.

Further, the above-mentioned connecting means is configured such that the connecting member fixed to the reactor shield wall is connected to the stabilizer bracket projecting around the upper portion of the reactor pressure vessel, so that the existing stabilizer is provided. By using the bracket, the work time such as welding at the site can be shortened, the exposure dose can be reduced, and a reliable connection can be achieved.

Further, in the coupling means, a coupling member fixed to the reactor shielding wall is coupled to a stabilizer bracket projecting around an upper portion of the reactor pressure vessel and is fixed to the reactor pressure vessel. Since the supporting member is configured to engage with the upper edge of the pipe passage opening opening to the reactor shielding wall, the existing stabilizer bracket can be used to reduce the work time of welding at the site. Can be shortened, the amount of exposure can be reduced, reliable coupling can be achieved, and stable support can be achieved.

[Brief description of drawings]

FIG. 1 is a conceptual diagram illustrating a method of unloading a reactor pressure vessel to which a nuclear reactor renewal method of a nuclear power generation facility according to the present invention is applied.

FIG. 2 is an enlarged view of a reactor pressure vessel.

FIG. 3A is a plan view of an upper coupling portion, and FIG. 3B is a front view thereof.

FIG. 4 is a side view of an upper coupling portion.

FIG. 5 is a cross-sectional view showing a lower support part.

[Explanation of symbols]

1 reactor building 10 Reactor pressure vessel 13 Stabilizer bracket 20 Reactor shield wall 21 Opening (Pipe passage opening) 40 Upper coupling part (coupling means) 41 Coupling hardware (coupling member) 50 Lower support (lower support) 51 Support bracket (support member)

Claims (4)

[Claims] 1. When a nuclear reactor of a nuclear power generation facility is renewed, a reactor pressure vessel including internal reactor structures and a surrounding reactor shield wall are joined by a joining means, and the reactor pressure vessel is carried out integrally from the reactor building. Reactor renewal method for nuclear power generation facilities characterized by the following. 2. When a nuclear reactor of a nuclear power generation facility is being renewed, the reactor pressure vessel including the reactor internals and the surrounding reactor shielding wall are connected by a connecting means, and the reactor pressure vessel is integrally carried into the reactor building. Reactor renewal method for nuclear power generation facilities characterized by the following. 3. The coupling means is configured such that a coupling member fixed to the reactor shielding wall is coupled to a stabilizer bracket projecting around an upper portion of the reactor pressure vessel. The nuclear reactor renewal method of claim 1 or 2. 4. The connecting means is such that a connecting member fixed to the reactor shielding wall is connected to a stabilizer bracket projecting around an upper portion of the reactor pressure vessel and is fixed to the reactor pressure vessel. 3. The nuclear reactor renewal method for a nuclear power generation facility according to claim 1 or 2, wherein the supporting member is configured to engage with an upper edge of the pipe passage opening opening to the nuclear reactor shielding wall. .