JPH06160558A - Reactor core internal structure supporting device for nuclear fusion device - Google Patents

Abstract

PURPOSE:To prolong the life of bellows and improve the operation availability factor of a reactor by separating the inflow area of a driving fluid driving a piston and the arranged area of the vacuum sealing bellows, and indirectly pressurizing the bellows. CONSTITUTION:When a reactor core internal structure is to be fixed to a vacuum vessel, a liquid inlet 14 is pressurized, the inner tube 6a and outer tube 6b of the piston rod of a piston 6 are integrally driven in the direction to shrink vacuum sealing bellows 11, and a cotter 7 is driven into the insertion hole of the reactor core internal structure. The driving liquid 12 leaked to the bellows 11 side is discharged from an atmosphere release port 16. When the reactor core internal structure is to be removed from the vacuum vessel, a liquid inlet 15 is pressurized, the cotter 7 is extracted, and the liquid 12 leaked to the bellows 11 side is discharged from the atmosphere release port 16. The pressure force of the liquid 12 is not directly applied to the bellows 11, and only the differential pressure between the vacuum region and the atmosphere is applied. The life of the bellows 11 repeatedly expanded and shrunk is largely extended, and it can contribute to the improvement of the operation availability factor of a reactor.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a toroidal-type nuclear fusion device used for mounting a sector-shaped reactor internal structure arranged on the inner surface of a toroidal-type vacuum container surrounding plasma. A nuclear fusion device related to the in-reactor structure supporting device, in particular, the life of the bellows for vacuum sealing is repeatedly extended and contracted to significantly extend its life, and the number of maintenance and inspections is greatly reduced to improve the operating rate of the reactor. The present invention relates to a device for supporting the internal structure of a furnace.

[0002]

2. Description of the Related Art FIG. 3 is a cross-sectional view showing a structural example of a reactor internal structure of a general torus-type nuclear fusion device of this type.
In FIG. 3, the vacuum container 1 is of a donut shape surrounding the plasma 2 and maintains the region of the plasma 2 in a high vacuum.

A plasma 2 is formed on the inner surface of the vacuum container 1.
A sector-shaped internal structure 3 such as a diver and a blanket is installed so as to surround the. In order to disassemble and assemble, the sector-shaped furnace internal structure 3 needs to be detached from the vacuum container 1 and taken out of the furnace for each sector, or conversely, brought in from the furnace and attached to the vacuum container 1. Further, these sector-shaped internal structures 3 need a support structure that can withstand a strong electromagnetic force 4.

One of the supporting devices that fulfill these functions is the reactor internal structure supporting device 5. That is, when removing the in-core structure 3, the piston rod 6a of the in-core structure support device 5 is contracted, and the tapered cotter 7 attached to the tip thereof is pulled out. As a result, there is no binding force between the sector-shaped reactor internals 3 and the vacuum vessel 1, so the sector-shaped reactor internals 3 can be remotely removed from the vacuum chamber 1 by a manipulator (not shown). You can

On the other hand, when the sector-shaped reactor internal structure 3 is mounted, it is moved to a predetermined position in the vacuum vessel 1 by the manipulator (not shown), and the positioning plate 8 fixed to the lower surface of the reactor internal structure 3 is attached. After arranging so as to be inserted into the positioning groove 9 on the side of the vacuum vessel 1, the piston rod 6a is extended to insert the tapered cotter 7 into the insertion hole 8a provided in the positioning plate 8 of the reactor internal structure 3. Thus, the sector-shaped furnace internal structure 3 can be fixed to the vacuum container 1. FIG. 4 is a cross-sectional view showing a specific configuration example of the reactor internal structure support device 5 of this type of torus fusion device.

In FIG. 4, piston 6 and cylinder 10
A bellows 11 for vacuum sealing is connected between and. With this vacuum sealing bellows 11, the cylinder 10
The driving liquid 12 for driving the piston inside is prevented from entering the outside vacuum region where the cotter 7 is located.

A seal ring 13 is provided on the sliding surface of the piston 6 and the cylinder 10 so as to drive the driving liquid 1 on the pressurizing side.
2 is arranged so that the leakage to the opposite side of 2 is as small as possible. When inserting the cotter 7, the first liquid inlet 1
When the piston 4 is pushed out by pushing 4 and the cotter 7 is pulled out, the second liquid inlet 15 is pushed up. The piston rod 6a and the cotter 7 are metallurgically joined together. However, the above-described reactor internal structure supporting device 5 has the following problems.

That is, the sector-shaped reactor internal structure 3 is
When fixed to or removed from the vacuum container 1, the pressurized driving liquid 12 is supplied to either the first liquid inlet 14 or the second liquid inlet 15 to drive the cotter 7. The pressing force of the driving liquid 12 directly acts on the vacuum sealing bellows 11 installed between the piston 6 and the cylinder 10.

The vacuum sealing bellows 11 expands and contracts by the above-mentioned pressurized driving liquid 12 each time when the furnace internal structure 3 is attached to or detached from the vacuum vessel 1, to achieve the purpose. Therefore, the problem of life due to repeated fatigue arises. Generally, the life of this type of bellows is determined by the amount of displacement per mountain and the acting pressure, and the following evaluation formula is used. (A) Stress due to pressure: S _P (kgf / mm ² ) S _P = P (βW) ² / (Α ・ 200 t ² ) (B) Stress due to expansion and contraction Sα (kgf / mm ² ) Sα = 3Etδ / (βW) ²

The calculated life N is the resultant stress S (kgf / mm
² ), (C) S = S _P + Sα (d) N = (700 / S) ⁶ (For material Inconel)

However, P: pressure (kgf / mm ² ) W: Span (mm) t: Plate thickness (mm) α: Pressure mode constant (= 1) β: Nesting constant (determined by pressure range) E: Modulus of longitudinal elasticity (kgf / mm ² ) Δ: Displacement amount per one peak of vacuum sealing bellows (mm) Therefore, the greater the displacement amount per one peak of the vacuum sealing bellows 11 and the higher the pressure, the shorter the life of the vacuum sealing bellows 11. It will be.

On the other hand, in order to avoid making the entire furnace larger,
The reactor internal structure support device 5 installed in the vacuum container 1 is also required to be miniaturized as much as possible, but in order to obtain a predetermined fixing force, the pressure of the driving liquid 12 is increased as the size is reduced. In this case, the life of the vacuum sealing bellows 11, which is the most vulnerable to pressure in the components of the reactor internal structure supporting device 5, is further accelerated.

Therefore, when the vacuum sealing bellows 11 has a short life, for maintenance, disassembly, inspection (replacement),
This requires frequent assembly work, resulting in a significant reduction in the operating rate of the furnace, which is an economically disadvantageous factor.

In addition, if the operating rate is increased,
Since the life margin becomes smaller with respect to the number of times of driving in one operation period, the vacuum sealing bellows 11 breaks during operation, and the driving liquid 12 flows into the vacuum container 1. However, in this case, there is a problem in that the recovery work requires a great deal of time and cost.

[0015]

As described above, in the conventional reactor internal structure supporting device of the nuclear fusion device, the high pressure of the liquid for driving the piston acts directly on the vacuum sealing bellows which is a component. Therefore, there has been a problem that the life of the vacuum sealing bellows is shortened and the operating rate of the furnace is unavoidably reduced due to its maintenance.

An object of the present invention is to prevent the pressurizing force of the driving fluid of the piston from directly acting on the vacuum sealing bellows, thereby significantly extending the life of the vacuum sealing bellows due to repeated expansion and contraction. An object of the present invention is to provide an extremely reliable nuclear reactor internal structure support device capable of significantly reducing the number of inspections and increasing the operating rate of the reactor.

[0017]

In order to achieve the above object, according to the present invention, a doughnut-shaped vacuum container surrounding a plasma is provided with a sector-shaped internal structure arranged on the inner surface of the vacuum container. In the reactor internal structure support device of the fusion device used for, the reactor internal structure support device main body,
It is composed of a piston, a cylinder, a cotter, and a bellows for vacuum sealing, and separates the inflow region of the pressurized driving fluid for driving the piston and the disposition region of the bellows for vacuum sealing.
The anti-vacuum region of the vacuum sealing bellows is open to the atmosphere.

Here, in particular, the inflow region of the pressurized drive fluid for driving the piston and the disposition region of the vacuum sealing bellows are separated, and the anti-vacuum region of the vacuum sealing bellows is opened to the atmosphere. As the configuration, the piston rod has a double cylinder structure, the vacuum sealing bellows is disposed between the outer cylinder and the inner cylinder, and the space area between the vacuum sealing bellows and the outer cylinder of the piston rod is formed. A pipe is connected to the atmosphere side.

[0019]

Therefore, in the reactor internal structure supporting device of the nuclear fusion device of the present invention, the inflow region of the pressurized drive fluid for driving the piston and the disposition region of the vacuum sealing bellows are separated, By releasing the anti-vacuum region of the vacuum sealing bellows to the atmosphere, the pressure of the piston driving fluid does not act directly on the vacuum sealing bellows. On the other hand, it becomes possible to significantly reduce the stress S _P due to pressure.

As a result, when the displacement amount per peak of the vacuum sealing bellows is the same, the pressure of the driving fluid is applied to the vacuum sealing bellows (for example, 65 kg ^f). / Cm ² In the present invention, the atmospheric pressure (1 kg ^f /
cm ² ), It is possible to calculate the extension of life by several tens of times. Therefore, it is possible to obtain an extremely reliable in-core structure support device that contributes to a significant improvement in the operating rate of the furnace as compared with the conventional case.

[0021]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention is a pressurized piston driving piston so that the pressure of the piston driving fluid does not directly act on the vacuum sealing bellows which constitutes the reactor internal structure supporting device in the nuclear fusion device. The greatest feature is that the drive fluid inflow region and the vacuum sealing bellows arrangement region are separated and the anti-vacuum region of the vacuum sealing bellows is opened to the atmosphere. An embodiment of the present invention based on the above concept will be described in detail with reference to the drawings.

FIG. 1 is a sectional view showing an example of the structure of a reactor internal structure supporting device in a torus-type nuclear fusion device according to the present invention when the cotter is pulled out, and FIG. 2 is the same structure of the reactor internal structure supporting device. It is sectional drawing which shows an example in the state in a cotter insertion position. 1 and 2, the same elements as those in FIG. 4 are designated by the same reference numerals, and detailed description thereof will be omitted, and only different portions will be described here.

In FIG. 1, a piston rod 6a having a cotter 7 metallurgically joined to the tip is an inner cylinder side, and a piston rod outer cylinder 6b similarly fixed to the piston 6 side is arranged. A vacuum sealing bellows 11 that seals a vacuum region outside the cotter 7 is attached between the cylinder 10 and the piston rod inner cylinder 6a.

A seal ring 13a is provided on the sliding surface of the piston 6 and the cylinder 10 for the liquid 12 on the pressurizing side.
It is arranged so that the leakage to the opposite side of a is as small as possible. Similarly, on the sliding surface between the piston rod outer cylinder 6 b and the cylinder 10, the seal ring 13 is provided on the cylinder 10 side.
b is arranged so as to minimize the leakage of the liquid 12b to the side of the vacuum sealing bellows 11.

Further, the region formed by the vacuum sealing bellows 11 and the piston rod outer cylinder 6b is the atmosphere release port 1
6 leads to (releases) the atmosphere. As shown in FIG. 2, when the cotter 7 is inserted, the piston 6 is pushed out by pressurizing the first liquid inlet 14, and conversely, when the cotter is pulled out, the second liquid inlet 15 side is pressurized. There is. In this embodiment, for example, water is used as the driving liquid 12, and manganese bronze is used as the seal ring 13.

Next, in the reactor internal structure support device 5 of the nuclear fusion device of the present embodiment configured as described above, when the sector reactor internal structure 3 is fixed at a predetermined position of the vacuum vessel 1. To pressurize the first liquid inlet 14 to move the piston 6
Is integrally driven with the piston rod inner cylinder 6a and the piston rod outer cylinder 6b in the direction of contracting the vacuum sealing bellows 11, and the cotter 7 at the tip is driven into the predetermined cotter insertion hole 8a of the counterpart in-core structure 3. .

At this time, the pressurized driving liquid 12 has a slight leak on the side of the vacuum sealing bellows 11 through the seal rings 13a and 13b, but the leak amount passes through the atmosphere opening port 16, A pipe connected to the atmosphere release port 16 (not shown) leads to a predetermined tank of a water leakage treatment device (not shown) installed under atmospheric pressure.

On the other hand, conversely, when removing the sector-shaped furnace internals 3 from the vacuum vessel 1, the second liquid inlet 15 is pressurized to pull out the cotter 7. At this time, the pressurized driving liquid 12 passes through the slide surface between the seal ring 13b and the piston rod outer cylinder 6b, and then the vacuum sealing bellows 1
Although it leaks to the No. 1 side, the amount of leak is discharged from the atmosphere opening port 16 to the external tank (not shown) as in the case of inserting the cotter 7 described above.

Therefore, the pressure of the driving liquid 12 does not act directly on the vacuum sealing bellows 11, but only on the pressure difference between the vacuum region and the atmospheric pressure. Therefore, the calculated life N in the above-mentioned evaluation formula of the vacuum sealing bellows is N.
The stress S _P due to pressure, which is one of the determinants of, can be significantly reduced.

As a result, when the displacement amount per peak of the vacuum sealing bellows is the same, the pressure of the driving fluid is applied to the vacuum sealing bellows (for example, 65 kg ^f). / Cm ² In this embodiment, the atmospheric pressure (1 kg
^f / Cm ² ), It is possible to calculate the extension of life by several tens of times. Therefore, it is possible to obtain an extremely reliable in-core structure support device that contributes to a significant improvement in the operating rate of the furnace as compared with the conventional case.

Needless to say, the diameter of the atmosphere release port 16 is designed to have a sufficiently large value with respect to the amount of leakage of the driving liquid 12 so that the pressure does not increase due to the amount of leakage. Further, the tank (not shown) to which the leaked liquid is introduced is a closed tank which is kept at the atmospheric pressure and is not discharged directly into the atmosphere.

As described above, in the reactor internal structure supporting device 5 of the nuclear fusion device of this embodiment, the piston rod 6 has a double cylinder structure, and a vacuum is provided between the outer cylinder 6b and the inner cylinder 6a. By arranging the sealing bellows 11 and providing a pipe portion that connects the space area between the vacuum sealing bellows 11 and the piston rod outer cylinder 6b to the atmosphere side, the pressurized driving drive of the piston 6 is performed. The inflow region of the liquid 12 and the disposition region of the vacuum sealing bellows 11 are separated, the anti-vacuum region of the vacuum sealing bellows 11 is opened to the atmosphere, and the pressurized driving liquid 12 is directly vacuum sealed. The bellows 11 does not act on the bellows 11.

Therefore, it is possible to significantly reduce the stress generation value due to pressure, which is one of the determining factors of the life of the vacuum sealing bellows 11, and the displacement of the vacuum sealing bellows 11 which is another determining factor of the life. It is possible to significantly extend the life of the vacuum sealing bellows 11, which is calculated from the total value of the stress value (which does not change) depending on the amount, which contributes to a significant improvement in the operating rate of the furnace. It is possible to obtain the in-core structure supporting device 5 having extremely high reliability.

That is, unlike the above-described conventional example, since the high pressure of the driving liquid 12 for the piston 6 does not directly act on the vacuum sealing bellows 11, the life of the vacuum sealing bellows 11 due to repeated expansion and contraction. Can be significantly extended, the number of maintenance and inspections can be significantly reduced, and a safety factor for the required number of drivings can be increased.

Further, in order to obtain a predetermined fixing force, it is possible to further increase the pressure of the driving liquid 12, and thereby the reactor internal structure supporting device 5 can be further downsized. There is a large contribution to the improvement of economic efficiency and safety by downsizing and improvement of operating rate. The present invention is not limited to the above embodiment, but can be implemented in the same manner as described below.

(A) In the above embodiment, the case where the reactor internal structure supporting device is used for the reactor internal structure supporting device of the nuclear fusion device has been described, but the present invention is not limited to this, and the piston and the cylinder can be used. And all of the mechanism that consists of a bellows and is driven by a pressurized fluid,
The present invention can be similarly applied.

(B) In the above embodiment, the case where water is used as the driving liquid 12 and manganese bronze is used as the seal ring 13 has been described, but the present invention is not limited to this, and other materials are used. It is also possible.

(C) In the above embodiment, the case where the liquid is used as the fluid for driving the piston has been described, but the present invention is not limited to this, and a fluid other than the liquid may be used.

[0039]

As described above, according to the present invention, the main body of the reactor internal structure supporting device is composed of the piston, the cylinder, the cotter, and the bellows for vacuum sealing, and the pressurized drive for driving the piston. Separates the inflow area of the working fluid and the installation area of the vacuum sealing bellows, releases the anti-vacuum area of the vacuum sealing bellows to the atmosphere, and the pressure of the piston driving fluid does not act directly on the vacuum sealing bellows. Since it is configured so that the pressure of the piston driving fluid does not directly act on the vacuum sealing bellows, the life of the vacuum sealing bellows due to repeated expansion and contraction can be greatly extended, and the number of maintenance and inspections can be reduced. It is possible to provide a highly reliable internal structure support device for a nuclear fusion device capable of significantly reducing the operating rate of the reactor.

[Brief description of drawings]

FIG. 1 is a sectional view showing an embodiment of a reactor internal structure supporting device in a nuclear fusion device of the present invention in a cotter-pulled-out state.

FIG. 2 is a cross-sectional view showing a configuration example of a reactor internal structure supporting device in the same embodiment, with a part of the state when a cotter is inserted being omitted.

FIG. 3 is a sectional view showing a structural example of a reactor internal structure of a general torus fusion device.

FIG. 4 is a cross-sectional view showing a configuration example of a conventional in-core structure supporting device in a nuclear fusion device.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Vacuum container, 3 ... Sector-shaped furnace internal structure, 5 ... Furnace internal structure support device, 6 ... Piston, 6a ... Piston rod, 7 ... Cotter, 10 ... Cylinder, 11 ... Vacuum sealing bellows, 12 ... Drive liquid, 13 ... Seal ring, 14
... first liquid inlet, 15 ... second liquid inlet, 16 ... atmosphere opening port.

 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Kiyoshi Shiwanuma Kiyoshi Shimanuma No. 801, Mukayama, Naka-machi, Naka-gun, Naka-gun, Ibaraki Prefecture 1 of the Naka Research Institute, Japan Atomic Energy Research Institute (72) Makotoyama, Naka-machi, Naka-cho, Naka-gun, Ibaraki Prefecture No. 1 Inside the Naka Institute of Japan Atomic Energy Research Institute (72) Hisashi Fukushima 2-4 Suehiro-cho, Tsurumi-ku, Yokohama-shi, Kanagawa Toshiba Keihin Office

Claims (2)

[Claims] 1. A reactor internal structure supporting device of a nuclear fusion device used for mounting a sector-shaped reactor internal structure arranged on an inner surface of a vacuum container of a donut type surrounding a plasma, The furnace internal structure support device main body is composed of a piston, a cylinder, a cotter, and a vacuum sealing bellows, and an inflow region of a pressurized drive fluid for driving the piston and an arrangement of the vacuum sealing bellows. A reactor internal structure support device for a nuclear fusion device, characterized in that it is configured so as to be separated from a site and to open the anti-vacuum region of the vacuum sealing bellows to the atmosphere. 2. The inflow region of the pressurized drive fluid for driving the piston and the disposition region of the vacuum sealing bellows are separated, and the anti-vacuum region of the vacuum sealing bellows is opened to the atmosphere. As the configuration, the piston rod has a double cylinder structure, the vacuum sealing bellows is disposed between the outer cylinder and the inner cylinder, and the vacuum sealing bellows and the outer cylinder of the piston rod are 2. The in-reactor structure support device for a nuclear fusion device according to claim 1, wherein a pipe portion is provided to connect the space region of the above to the atmosphere side.