JPH0128276B2 - - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a pipe penetration device in a concrete reactor containment vessel. [Conventional technology] Conventionally, a reactor containment vessel is made of steel that has pressure resistance and airtightness, and a concrete shielding wall is provided around it, which prevents coolant from leaking inside. It was used to prevent the spread of radioactive materials and to shield radiation. but,
This type of structure had the disadvantage of having a complicated structure and increasing construction costs. In place of such a steel reactor containment vessel, a concrete reactor containment vessel as shown in FIGS. 1 and 2 has been developed. That is, numeral 1 in the figure is the main body of the containment vessel, which is strongly formed of reinforced concrete or the like and has pressure resistance and radiation shielding ability. A liner 2 made of a relatively thin steel plate is provided in close contact with the inner surface of the containment vessel body 1 to provide airtightness. A reactor pressure vessel 3 is housed within this reactor containment vessel,
Further, a suppression chamber 4 is formed in the lower part. Further, a pipe, for example, a main steam pipe 5 passes through the reactor containment vessel via a pipe penetration device 6 . By the way, such a reactor containment vessel made of concrete has a simple structure, and the reactor containment vessel itself has sufficient strength and rigidity, so piping, etc. can be supported by this reactor containment vessel. There are advantages. In the conventional reactor, a pipe, for example, a main steam pipe 5, is supported in the reactor containment vessel via a pipe penetration device 6 , as shown in FIG. That is, 7 is a penetrating sleeve that is provided to penetrate the containment vessel main body 1 and the liner 2, and is fixed to the containment vessel main body 1 by anchors 8... and anchor plates 9. and,
The main steam pipe 5 is inserted through the through sleeve 7 with a gap therebetween. A closing support member 10 is provided at the end of the penetration sleeve 7 on the outside of the reactor containment vessel (right side in FIG. 2), and this closure support member 10 connects the penetration sleeve 7 and the main steam pipe. 5 is airtightly closed, and this main steam pipe 5 is supported by a through sleeve 7.
Therefore, the axial load and torsional load generated on the main steam pipe 5 due to thermal expansion or the like are supported by the containment vessel main body 1 via the closure support member 10 and the through sleeve 7. [Problems to be Solved by the Invention] However, in such a structure, the load of the main steam pipe 5 is transmitted to the containment vessel main body 1 by the anchors 8 of the penetrating sleeve 7 and the anchor plate 9. 1, a local load will act on this part. Further, since high-temperature steam flows through the main steam pipe 5, the heat is conducted to the through sleeve 7 via the closing support member 10, and is also transmitted to the through sleeve 7 by radiation and convection. Conventionally, the outer end of the penetration sleeve 7, that is, the portion protruding into the reactor building from the outer surface of the containment vessel body 1, is cooled by the low temperature (10 to 40°C) air inside the reactor building. In addition, the portion of the penetration sleeve 7 that penetrates the containment vessel main body 1 flows into the gap between the penetration sleeve 7 and the main steam pipe 5 and is used to circulate gas (nitrogen gas, etc.) in the reactor containment vessel. However, since the gas inside the reactor containment vessel is at a high temperature of about 57℃,
This gas cannot be expected to have much of a cooling effect on the penetrating sleeve 7, and as a result, the temperature of the portion of the penetrating sleeve 7 that penetrates the containment vessel body 1 rises due to the heat from the main steam pipe 5, and the penetrating sleeve 7 Thermal expansion may occur, and the resulting stress may act on the containment vessel body 1, causing cracks or the like to occur in the concrete at the piping penetration portion of the containment vessel body 1. For this reason, the evaluation of the integrity of the containment vessel body 1 in the vicinity of the pipe penetration device 6 has become difficult, and there have been problems such as the need to provide special reinforcement or the like in the vicinity of the pipe penetration device 6 . For this reason, in the past, a heat insulating material was interposed between the main steam pipe 5 and the through sleeve 6 , but the effect was insufficient. In addition, a cooling pipe is provided between the main steam pipe 5 and the through sleeve 6 , and a refrigerant is circulated through this cooling pipe to prevent the temperature of the through sleeve 7 from rising, but such a system has a structure. There were problems such as complications. The present invention was made based on the above circumstances, and its purpose is to provide a pipe penetration device that does not adversely affect the integrity of a concrete reactor containment vessel and has a simple structure. It is in. [Means for Solving the Problems] In order to achieve the above object, the present invention includes a penetrating sleeve provided through a concrete reactor containment vessel, and a penetrating sleeve inserted with a gap in the penetrating sleeve. and a closing member that closes a gap between the through sleeve and the piping,
The closing member is provided at an end of the penetrating sleeve inside the reactor containment vessel, and opens the gap between the penetrating sleeve and the piping into the reactor building. [Function] That is, the present invention provides a closing member that closes the gap between the penetrating sleeve and the piping at the end of the penetrating sleeve inside the reactor containment vessel, so as to close the gap between the penetrating sleeve and the piping. By opening the gap into the reactor building, low-temperature air inside the reactor building can flow into the gap between the penetration sleeve and the piping.
The penetration sleeve is cooled from the inside by the low-temperature air inside the reactor building that flows in and circulates between the penetration sleeve and the piping, which reduces the temperature rise of the penetration sleeve due to heat from the piping. It can be suppressed. Therefore, according to the present invention, it is possible to reliably prevent the portion of the penetrating sleeve that is penetrated into the reactor containment vessel from thermally expanding and the resulting stress from acting on the containment vessel body. The structure is simple because it does not adversely affect the integrity of the containment vessel, and there is no need to interpose a heat insulating material or provide a cooling pipe between the penetrating sleeve and the piping. [Embodiment] An embodiment of the present invention will be described below with reference to FIGS. 3 and 4. In the figure, 101 is a reactor containment vessel, which is constructed on a mat 102 and housed in a reactor building 103. The reactor containment vessel 101 is composed of a containment vessel main body 104 made of reinforced concrete and a liner 105 stretched on the inner surface of the containment vessel main body 104. This containment vessel main body 104 is strongly formed,
It has pressure resistance and radiation shielding ability. Also,
The liner 105 is formed from a relatively thin steel plate, and provides airtightness to the containment vessel body 104.
It is in close contact with the inner surface of the reactor containment vessel 10.
Even if pressure rises within 1, the structure is such that it will not be deformed by this pressure. A reinforcing member (not shown) made of shaped steel or the like is attached to the inner surface of the liner 105, and due to the difference in thermal expansion with the containment vessel body 104, the liner 105
This prevents local deformation of the liner 105. The inside of this reactor containment vessel 101 is divided into upper and lower parts by a diaphragm floor 106, and the upper part is divided into a dry well 10.
7. The lower part is formed into a suppression chamber 108. And this reactor containment vessel 101
A pedestal 109 is erected from the bottom of the reactor, and a reactor pressure vessel 110 is installed on the pedestal 109. Various types of piping, such as the main steam piping 111, are led out of the reactor containment vessel 101 by a piping penetration device 112 .
The configuration of this pipe penetration device 112 will be explained below.
In the figure, reference numeral 113 denotes a through sleeve, which has a cylindrical shape. The penetrating sleeve 113 is embedded in the containment vessel body 104 and passes through the containment vessel body 104 and the liner 105 in an airtight manner. This penetrating sleeve 113 has anchors 114... and anchor plates 115.
It is fixed to the containment vessel main body 104 by. Note that 116... is a gusset. and,
The end of the penetrating sleeve 113 on the inside of the reactor containment vessel (left side in FIG. 4) protrudes by a predetermined length. A main steam pipe 111 is inserted into this penetrating sleeve 113.
A cooling gap 117 is formed between the outer peripheral surface of the penetrating sleeve 11 and the inner peripheral surface of the through sleeve 113. A closing support member 118 is provided at the end of the penetrating sleeve 113 inside the reactor containment vessel.
This closing support member 118 is welded to the end of the penetrating sleeve 113 and the outer peripheral surface of the main steam pipe 111, and transmits the load in the axial direction and torsional direction acting on the main steam pipe 111 to the penetrating sleeve 113. The cooling gap 117 between the main steam pipe 111 and the through sleeve 113 is hermetically closed. Further, the cooling gap 117 is formed at the outer end of the through sleeve 113 in the reactor building 10.
It is open within 3 days. In one embodiment of the present invention configured as described above, the liner 105, the penetrating sleeve 113, and the closing support member 118 are used in this part of the reactor containment vessel 101.
A boundary is formed and the airtightness of this area is maintained. In addition, axial loads and torsional loads acting on the main steam pipe 111 due to thermal expansion etc. are received by the containment vessel main body 104 via the closure support member 118 and the penetration sleeve 113, causing deformation of the main steam pipe 111. is prevented. The heat of the main steam pipe 111 is then transmitted to the through sleeve 113. However, in this embodiment, the main steam pipe 111
A closing support member 118 is provided at the inner end of the through sleeve 113 to close the space between the through sleeve 113 and the main steam pipe 1.
Since the cooling space 117 between the reactor building 103 and the reactor building 11 is open to the outside, that is, inside the reactor building 103,
low temperature air flows in. Therefore, the penetrating sleeve 113 is cooled from the inside by the low-temperature air inside the reactor building 103 that flows into the cooling chamber 117 and circulates, so that the penetrating sleeve 113 is cooled by the heat from the main steam pipe 111. 113 temperature rise can be suppressed to a low level. That is, conventionally, the gap between the penetration sleeve and the main steam piping was closed at the outer end of the penetration sleeve, and the gap was opened into the reactor containment vessel to open the reactor containment vessel of the penetration sleeve. The penetrated part is cooled by the gas inside the reactor containment vessel that flows into the above-mentioned space and circulates, but during reactor operation, the temperature inside the reactor containment vessel is 57°C. Since the temperature will be around 30°F, high-temperature gas of around 57°C inside the reactor containment vessel will flow in and circulate within the above-mentioned interval, so the cooling effect of the through-sleeve by the above gas cannot be expected to be very high. Therefore, the temperature of the portion of the penetrating sleeve that penetrates the reactor containment vessel body increases due to the heat from the main steam piping, causing thermal expansion of the penetrating sleeve. However, in this embodiment, the closing support member 118 is provided at the inner end of the penetrating sleeve 113, and this position is used as the boundary of the reactor containment vessel 101 , and the main steam pipe 111 and the penetrating sleeve 1 are connected to each other.
13 is opened to the outside, that is, inside the reactor building 103, as a cooling gap 117, so that the air at a low temperature of 10 to 40°C in the reactor building 103 flows between the penetration sleeve 113 and the main steam pipe 111. The low-temperature air flows into and circulates through the cooling pipe 117 and effectively cools the penetrating sleeve 113 from the inside, making it possible to suppress the rise in temperature of the penetrating sleeve 113 due to heat from the main steam pipe 111. . Therefore, according to the above embodiment, the portion of the penetrating sleeve 113 that is penetrated into the containment vessel body 104 thermally expands, and the stress is transferred to the containment vessel body 104.
Therefore, the integrity of the concrete reactor containment vessel 101 is not adversely affected. Further, according to the above embodiment, there is no need to interpose a heat insulating material or provide a cooling pipe between the penetrating sleeve 113 and the main steam pipe 111, so the structure is simple. Note that the present invention is not limited to the above embodiment. For example, the support of the pipe and the closure between the pipe and the penetration sleeve may be performed by separate members, for example, a support member that only supports the pipe is provided at the outer end of the penetration sleeve, and a support member that only supports the pipe is provided at the inner end of the penetration sleeve. Alternatively, a closing member such as a metal bellow may be provided to close the space between the pipe and the penetrating sleeve. However, in this case, it is necessary to provide holes for air circulation in the support member. Furthermore, it goes without saying that the present invention is applicable not only to main steam piping penetration devices but also to other general pipe penetration devices. [Effects of the Invention] As described above, the present invention provides a penetrating sleeve that penetrates the reactor containment vessel, a pipe that is inserted into the penetrating sleeve with a gap, and a pipe that is inserted into the inner end of the reactor containment vessel of the penetrating sleeve. A closing member is provided to close the space between the pipe and the through sleeve, and the gap between the through sleeve and the pipe is opened to the outside, that is, into the reactor building, as a cooling gap. Therefore, according to the present invention, the penetration sleeve is cooled from the inside by the low-temperature air inside the reactor building that flows in and circulates between the penetration sleeve and the pipe, and the pipe is cooled from the inside. It is possible to suppress the temperature rise of the penetrating sleeve due to the heat of Because it can be used, it does not adversely affect the integrity of the concrete reactor containment vessel, and the structure is simple because there is no need to interpose insulation material or provide cooling pipes between the penetration sleeve and the piping. It is.

[Brief explanation of drawings]

1 and 2 show a conventional example, with FIG. 1 being a longitudinal cross-sectional view of the whole, and FIG. 2 being a longitudinal cross-sectional view of a pipe penetration device. 3 and 4 show an embodiment of the present invention, with FIG. 3 being a longitudinal cross-sectional view of the whole, and FIG. 4 being a longitudinal cross-sectional view of a pipe penetration device. 101 ...Reactor containment vessel, 104...Containment vessel main body, 105...Runner, 111...Main steam piping (piping), 112 ...Piping penetration device, 113
...Throughout sleeve, 117...Cooling gap, 11
8... Closure support member (closure member).

Claims (1)

[Scope of Claims] 1. A penetrating sleeve provided to penetrate a concrete reactor containment vessel, a pipe inserted into the penetrating sleeve with a gap, and between the penetrating sleeve and the piping. and a closing member for closing the gap between the through-sleeve and the piping, and the closing member is provided at an end of the through-sleeve inside the reactor containment vessel to close the gap between the through-sleeve and the piping. A piping penetration device for a nuclear reactor containment vessel, characterized in that it is opened indoors. 2. The atom according to claim 1, wherein the closing member serves both to close the gap between the penetrating sleeve and the pipe and to fix the pipe to the penetrating sleeve. Reactor containment vessel piping penetration device.