JPH0143589Y2 - - Google Patents

Info

Publication number
JPH0143589Y2
JPH0143589Y2 JP1984062126U JP6212684U JPH0143589Y2 JP H0143589 Y2 JPH0143589 Y2 JP H0143589Y2 JP 1984062126 U JP1984062126 U JP 1984062126U JP 6212684 U JP6212684 U JP 6212684U JP H0143589 Y2 JPH0143589 Y2 JP H0143589Y2
Authority
JP
Japan
Prior art keywords
cladding tube
reactor containment
containment vessel
welded
piping
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
JP1984062126U
Other languages
Japanese (ja)
Other versions
JPS60173099U (en
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed filed Critical
Priority to JP1984062126U priority Critical patent/JPS60173099U/en
Publication of JPS60173099U publication Critical patent/JPS60173099U/en
Application granted granted Critical
Publication of JPH0143589Y2 publication Critical patent/JPH0143589Y2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Installation Of Indoor Wiring (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 「産業上の利用分野」 本考案は、原子炉格納容器等の配管貫通部の構
造に係わり、特に、原子炉格納容器とそれを取り
囲む外部遮蔽壁とを貫通する配管周りの構造に関
するものである。
[Detailed description of the invention] "Field of industrial application" The present invention relates to the structure of piping penetrations in reactor containment vessels, etc., and in particular, the invention relates to the structure of piping penetrations in reactor containment vessels, etc. It is about the surrounding structure.

「従来技術」 第1図は、従来の原子炉格納容器とそれを取り
囲む外部遮蔽壁とを貫通する配管周りの一構造例
を示すもので、原子炉格納容器1とそれを取り囲
む外部遮蔽壁2とを貫通する配管3の外周に保温
材4を設け、該保温材4と前記外部遮蔽壁2との
間に閉塞板5を設けるとともに、前記原子炉格納
容器1の内方位置に支持リング6を設け、該支持
リング6と前記閉塞板5との間に、前記保温材4
を周方向に間隙をおいて被覆しかつ複数のベロー
ズ7を有する内部被覆管8を介装するとともに、
該内部被覆管8を周方向に間隔をおいて被覆しか
つ複数のベローズ9を有する外部被覆管10を前
記閉塞板5と原子炉格納容器1との間に介装し、
前記内部被覆管8のベローズ7の間と外部被覆管
10との間に、両被覆管8,10を相互に連結す
るスペーサ11を設けた概略構成となつている。
"Prior Art" Figure 1 shows an example of a structure around a pipe that penetrates a conventional reactor containment vessel and an external shielding wall surrounding it. A heat insulating material 4 is provided on the outer periphery of the piping 3 passing through the reactor containment vessel 1, and a closing plate 5 is provided between the heat insulating material 4 and the external shielding wall 2, and a support ring 6 is provided inside the reactor containment vessel 1. is provided between the support ring 6 and the closure plate 5, and the heat insulating material 4 is provided between the support ring 6 and the closure plate 5.
an inner sheathing tube 8 having a plurality of bellows 7 is interposed therebetween, and
An outer cladding tube 10 that covers the inner cladding tube 8 at intervals in the circumferential direction and has a plurality of bellows 9 is interposed between the closing plate 5 and the reactor containment vessel 1,
A spacer 11 is provided between the bellows 7 of the inner cladding tube 8 and the outer cladding tube 10 to connect the two cladding tubes 8 and 10 to each other.

そして、該従来の配管貫通部の構造は、原子炉
格納容器1と外部遮蔽壁2との相対移動や配管3
の熱伸縮等を複数のベローズ7,9によつて吸収
するとともに、閉塞板5やスペーサ11等によつ
て前記原子炉格納容器1や外部遮蔽壁2の内部と
外部との連通を遮断するようになつている。
The structure of the conventional piping penetration part is such that the relative movement between the reactor containment vessel 1 and the external shielding wall 2 and the piping 3
Thermal expansion and contraction, etc. of It's getting old.

しかしながらこのような従来の配管貫通部の構
造にあつては、なお次のような改善すべき問題点
が残されている。
However, in the structure of such a conventional pipe penetration part, the following problems still remain to be improved.

すなわち、前記閉塞板5、支持リング6および
スペーサ11等は、全て溶接によつて一体化され
ているために、内部の補修等を実施する場合にお
いて作業が煩雑になりやすい。また、前記配管3
が熱伸縮等によつてその半径方向に変位した場合
には、前記閉塞板5やスペーサ11によつて前記
変位が拘束されるために、配管3や保温材4に応
力の集中を生じさせてしまいやすい。このような
問題点は、原子力プラントの健全性の面から特に
回避すべき事項に挙げられている。
That is, since the closing plate 5, the support ring 6, the spacer 11, etc. are all integrated by welding, the work tends to become complicated when carrying out internal repairs or the like. In addition, the piping 3
When the piping is displaced in the radial direction due to thermal expansion and contraction, etc., the displacement is restrained by the closing plate 5 and the spacer 11, causing concentration of stress on the piping 3 and the heat insulating material 4. Easy to store. Such problems are listed as matters that should be particularly avoided from the standpoint of the integrity of nuclear power plants.

「考案の目的」 本考案は前述した従来の諸事情に鑑みてなされ
たもので、その目的とするところは、配管等がそ
の半径方向に変位した場合に該変位を吸収し、か
つ、該配管に作用する半径方向の外力を長さ方向
に変換して応力を緩和するとともに、構造を簡略
化して補修作業を簡便にする原子炉格納容器等の
配管貫通部の構造を提供することにある。
"Purpose of the invention" The present invention was made in view of the conventional circumstances mentioned above, and its purpose is to absorb the displacement when piping, etc. is displaced in the radial direction, and to It is an object of the present invention to provide a structure for a piping penetration part of a reactor containment vessel, etc., which reduces stress by converting external force in the radial direction acting on the reactor into the longitudinal direction, and also simplifies the structure and facilitates repair work.

「考案の構成」 本考案は、前述した目的を達成するために、原
子炉格納容器と、該原子炉格納容器を取り囲む外
部遮蔽壁とを貫通する配管の外周に保温材を一体
に設けるとともに、該保温材を覆つて内部被覆管
を一体に設け、該内部被覆管の外周に全周に亘つ
て間隔をおいて外部被覆管を設け、該外部被覆管
の外周面と前記外部遮蔽壁との間に両者間の間隙
を覆う中空円錐台状のスペーサを設けて成り、前
記外部被覆管はその一端が前記内部被覆管および
保温材の一端を覆つて配管に溶接され、他端部が
前記原子炉格納容器に溶接され、かつ、中間に長
さ方向の伸縮を吸収するベローズが設けられ、前
記スペーサはその一端部が前記外部遮蔽壁に全周
に亘つてシール溶接されているとともに、他端部
が前記外部被覆管の外周のシール溶接されている
ことを特徴とする。
"Structure of the invention" In order to achieve the above-mentioned object, the present invention provides a heat insulating material integrally on the outer periphery of the piping that penetrates the reactor containment vessel and the external shielding wall surrounding the reactor containment vessel, and An inner cladding tube is integrally provided to cover the heat insulating material, and outer cladding tubes are provided at intervals around the entire circumference of the inner cladding tube, and the outer circumferential surface of the outer cladding tube and the outer shielding wall are connected to each other. A hollow truncated conical spacer is provided between them to cover the gap between them, one end of the outer cladding tube is welded to the piping so as to cover one end of the inner cladding tube and the heat insulating material, and the other end is welded to the piping, and the other end is welded to the piping, covering one end of the inner cladding tube and one end of the heat insulating material. A bellows is welded to the reactor containment vessel and is provided in the middle to absorb expansion and contraction in the length direction, and one end of the spacer is seal-welded to the external shielding wall over the entire circumference, and the other end is welded to the outer shielding wall. A portion of the outer cladding tube is seal-welded to the outer periphery of the outer cladding tube.

「実施例」 以下、本考案を第2図および第3図に示す一実
施例に基づき説明する。なお、以下の説明中第1
図と共通する部分については同一符号を用いて説
明を簡略化する。
"Example" The present invention will be described below based on an example shown in FIGS. 2 and 3. In addition, in the following explanation, the first
The same reference numerals are used for parts common to the figures to simplify the explanation.

本実施例の原子炉格納容器等の配管貫通部の構
造は、原子炉格納容器1と、該原子炉格納容器1
を取り囲む外部遮蔽壁2とを貫通する配管3の外
周に保温材4を一体に設けるとともに、該保温材
4を覆つて内部被覆管12を一体に設け、該内部
被覆管12の外周に全周に亘つて間隔をおいて外
部被覆管13を設け、該外部被覆管13の外周面
と前記外部遮蔽壁2との間に両者間の間隙gを覆
う中空円錐台状のスペーサ14を設けて成り、前
記外部被覆管13はその一端が前記内部被覆管1
2および保温材4の一端を覆つて配管3に溶接さ
れ、他端部が前記原子炉格納容器1に溶接され、
かつ、中間に長さ方向の伸縮を吸収するベローズ
15が設けられ、前記スペーサ14はその一端部
が前記外部遮蔽壁2に全周に亘つてシール溶接さ
れているとともに、他端部が前記外部被覆管13
の外周にシール溶接された概略構成と成つてい
る。
The structure of the pipe penetration part of the reactor containment vessel etc. in this embodiment is as follows: the reactor containment vessel 1 and the reactor containment vessel 1
A heat insulating material 4 is integrally provided on the outer periphery of the piping 3 that penetrates the external shielding wall 2 surrounding the pipe 3, and an inner cladding tube 12 is integrally provided to cover the heat insulating material 4. An outer cladding tube 13 is provided at intervals over the outer cladding tube 13, and a hollow truncated conical spacer 14 is provided between the outer peripheral surface of the outer cladding tube 13 and the external shielding wall 2 to cover the gap g therebetween. , the outer cladding tube 13 has one end connected to the inner cladding tube 1.
2 and one end of the heat insulating material 4 is welded to the piping 3, and the other end is welded to the reactor containment vessel 1,
A bellows 15 is provided in the middle to absorb expansion and contraction in the length direction, and one end of the spacer 14 is seal-welded to the external shielding wall 2 over the entire circumference, and the other end is sealed to the external shielding wall 2. Cladding tube 13
It has a general structure with a seal welded to the outer periphery.

次いでこれらの詳細について説明すれば、前記
内部被覆管12は保温材4の外周に接触状態に設
けられており、その一端部が前記外部遮蔽壁2の
貫通部分に位置させられて、外部被覆管13の一
端部内周面に溶接されているとともに、他端部が
原子炉格納容器1の内部へ突出させられている。
Next, to explain these details in detail, the inner cladding tube 12 is provided in contact with the outer periphery of the heat insulating material 4, and one end thereof is located at the penetrating portion of the outer shielding wall 2, so that the outer cladding tube 12 13 is welded to the inner circumferential surface of one end thereof, and the other end thereof is made to protrude into the inside of the reactor containment vessel 1.

前記外部被覆管13は原子炉格納容器1および
外部遮蔽壁2を貫通して該外部遮蔽壁2の外部へ
突出させられており、その一端部すなわち突出端
部が漸次小径となされて前記保温材4および内部
被覆管12の一端を覆うようにして前記配管3に
溶接されている。また、長さ方向の中間、すなわ
ち原子炉格納容器1と外部遮蔽壁2との間には、
前記ベローズ15が間隔をおいて2個設けられて
いる。
The external cladding tube 13 penetrates the reactor containment vessel 1 and the external shielding wall 2 and protrudes to the outside of the external shielding wall 2, and one end, that is, the protruding end, is gradually made smaller in diameter and is connected to the heat insulating material. 4 and one end of the inner cladding tube 12 is welded to the piping 3 so as to cover one end of the inner cladding tube 12. In addition, in the middle in the length direction, that is, between the reactor containment vessel 1 and the external shielding wall 2,
Two bellows 15 are provided at an interval.

前記スペーサ14は、大径部に半径方向外方に
向かう鍔14aが設けられ、該鍔14aが第3図
に示すようにアンカーボルト16によつて前記外
部遮蔽壁2の外面に固着されるとともにシール溶
接されることによつて、外部遮蔽壁2の内外間を
気密に分離している。また、該スペーサ14の小
径部は前記外部被覆管13の一端部外周面にシー
ル溶接によつて一体化されている。
The spacer 14 is provided with a radially outward flange 14a on the large diameter portion, and the flange 14a is fixed to the outer surface of the external shielding wall 2 by an anchor bolt 16 as shown in FIG. By seal welding, the inside and outside of the external shielding wall 2 are airtightly separated. Further, the small diameter portion of the spacer 14 is integrated with the outer peripheral surface of one end of the outer cladding tube 13 by seal welding.

このように構成された本実施例の配管貫通部の
構造にあつては、外部被覆管13や該外部被覆管
13と原子炉格納容器1との溶接部W1およびス
ペーサ14によつて原子炉格納容器1および外部
遮蔽壁2の内外部を気密に分離することができる
とともに、前記スペーサ14がアンカーボルト1
6とシール溶接によつて外部遮蔽壁2に固着され
ているから、その着脱が容易で補修作業を簡便に
する。また、内部被覆管12の他端が自由端とな
されているから、原子炉格納容器1と外部遮蔽壁
2との相対移動や外部被覆管13の熱変位等に起
因した該外部被覆管13の長さ方向の伸縮をベロ
ーズ15によつて吸収するとともに、前記配管3
等に半径方向の変位が生じたとしても、その変位
にともなつて、前記スペーサ14が第3図鎖線で
示すように湾曲するように変形し、配管3に作用
する外力を吸収するとともに配管の長さ方向に変
換する。したがつて配管3への応力の集中を防止
し該配管3の損傷を阻止することができる。
In the structure of the pipe penetration part of this embodiment configured in this way, the reactor containment is carried out by the outer cladding tube 13, the welded part W1 between the outer cladding tube 13 and the reactor containment vessel 1, and the spacer 14. The interior and exterior of the container 1 and the external shielding wall 2 can be airtightly separated, and the spacer 14
6 and is fixed to the external shielding wall 2 by seal welding, making it easy to attach and detach and simplify repair work. In addition, since the other end of the inner cladding tube 12 is a free end, the outer cladding tube 13 may be damaged due to relative movement between the reactor containment vessel 1 and the outer shielding wall 2 or thermal displacement of the outer cladding tube 13. The expansion and contraction in the length direction is absorbed by the bellows 15, and the piping 3
Even if a radial displacement occurs in the piping 3, the spacer 14 deforms in a curved manner as shown by the chain line in FIG. Convert in length direction. Therefore, concentration of stress on the pipe 3 can be prevented and damage to the pipe 3 can be prevented.

なお、前記実施例において示した各構成部材の
諸形状は一例であつて、設計要求等に基づき種々
変更可能である。
Note that the shapes of each component shown in the above embodiments are merely examples, and can be variously changed based on design requirements and the like.

「考案の効果」 以上説明したように、本考案に係わる原子炉格
納容器等の配管貫通部の構造によれば、配管貫通
部を簡素化しかつ取り付けや離脱を容易にして配
管貫通部の補修作業を簡便にすることができると
ともに、配管への応力の集中を防止して原子力プ
ラントの健全性を大幅に向上させることができる
等の優れた効果を奏する。
"Effects of the Invention" As explained above, the structure of the piping penetration part of the reactor containment vessel, etc. according to the present invention simplifies the piping penetration part and makes it easy to attach and detach, thereby making it possible to repair the piping penetration part. In addition to simplifying the process, it also has excellent effects such as preventing the concentration of stress on the piping and greatly improving the health of the nuclear power plant.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は従来の原子炉格納容器等の配管貫通部
の一構造例を示す縦断面図、第2図および第3図
は本考案の一実施例を示すもので、第2図は縦断
面図、第3図は第2図の部分の拡大図である。 1……原子炉格納容器、2……外部遮蔽壁、3
……配管、4……保温材、12……内部被覆管、
13……外部被覆管、14……スペーサ、14a
……鍔、15……ベローズ、16……アンカーボ
ルト。
Fig. 1 is a longitudinal cross-sectional view showing an example of the structure of a pipe penetration part of a conventional reactor containment vessel, etc. Fig. 2 and Fig. 3 are a longitudinal cross-sectional view showing an example of an embodiment of the present invention. FIG. 3 is an enlarged view of the portion shown in FIG. 2. 1... Reactor containment vessel, 2... External shielding wall, 3
... Piping, 4 ... Insulating material, 12 ... Internal cladding pipe,
13...Outer cladding tube, 14...Spacer, 14a
...Tsuba, 15...Bellows, 16...Anchor bolt.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 原子炉格納容器と該原子炉格納容器を取り囲む
外部遮蔽壁とを貫通する配管の外周に保温材を一
体に設けるとともに、該保温材を覆つて内部被覆
管を一体に設け、該内部被覆管の外周に全周に亘
つて間隔をおいて外部被覆管を設け、該外部被覆
管の外周面と前記外部遮蔽壁との間に両者間の間
隙を覆う中空円錐台状のスペーサを設けて成り、
前記外部被覆管はその一端が前記内部被覆管およ
び保温材の一端を覆つて配管に溶接され、他端部
が前記原子炉格納容器に溶接され、かつ、中間に
長さ方向の伸縮を吸収するベローズが設けられ、
前記スペーサはその一端部が前記外部遮蔽壁に全
周に亘つてシール溶接されているとともに、他端
部が前記外部被覆管の外周にシール溶接されてい
ることを特徴とする原子炉格納容器等の配管貫通
部の構造。
A heat insulating material is integrally provided on the outer periphery of the piping that penetrates the reactor containment vessel and an external shielding wall surrounding the reactor containment vessel, and an internal cladding tube is integrally provided to cover the heat insulating material. An outer cladding tube is provided on the outer periphery at intervals over the entire circumference, and a hollow truncated conical spacer is provided between the outer peripheral surface of the outer cladding tube and the external shielding wall to cover the gap therebetween,
One end of the outer cladding tube covers one end of the inner cladding tube and the heat insulating material and is welded to the piping, the other end is welded to the reactor containment vessel, and the intermediate portion absorbs expansion and contraction in the length direction. A bellows is provided,
A nuclear reactor containment vessel, etc., characterized in that one end of the spacer is seal-welded to the outer shielding wall over the entire circumference, and the other end is seal-welded to the outer periphery of the outer cladding tube. structure of pipe penetrations.
JP1984062126U 1984-04-26 1984-04-26 Structure of piping penetrations in reactor containment vessels, etc. Granted JPS60173099U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1984062126U JPS60173099U (en) 1984-04-26 1984-04-26 Structure of piping penetrations in reactor containment vessels, etc.

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1984062126U JPS60173099U (en) 1984-04-26 1984-04-26 Structure of piping penetrations in reactor containment vessels, etc.

Publications (2)

Publication Number Publication Date
JPS60173099U JPS60173099U (en) 1985-11-16
JPH0143589Y2 true JPH0143589Y2 (en) 1989-12-18

Family

ID=30591042

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1984062126U Granted JPS60173099U (en) 1984-04-26 1984-04-26 Structure of piping penetrations in reactor containment vessels, etc.

Country Status (1)

Country Link
JP (1) JPS60173099U (en)

Also Published As

Publication number Publication date
JPS60173099U (en) 1985-11-16

Similar Documents

Publication Publication Date Title
JPH0678799B2 (en) Pressure vessel with connecting short tube with heat shield
US3712012A (en) Reinforced-concrete pressure vessel with lining
JPH0143589Y2 (en)
US3710857A (en) Pressure-retentive vessel, e.g. for pressurized-fluid nuclear reactors
US4356144A (en) Closure hold-down system for a reactor vessel
US5047201A (en) Seal for a vessel connection of a hot pipeline
CN211574249U (en) Steel lining tetrafluoro tower section sealing structure
JPH0343517Y2 (en)
JPH05626Y2 (en)
JPH0336781Y2 (en)
JPH0350479Y2 (en)
JPS6355496A (en) Nuclear reactor
FR2400682B1 (en)
JPH0249440Y2 (en)
JPH0241419Y2 (en)
JPH048397Y2 (en)
JPS6339676Y2 (en)
JPS6018698Y2 (en) non-return valve
JPH0350480Y2 (en)
JPS5838754Y2 (en) gas insulated equipment
JPS596288Y2 (en) Internal mounting structure of pressure vessel
JP3935811B2 (en) Metal gasket, manufacturing method thereof, and radioactive substance storage container
JPS6342398Y2 (en)
JPS6234287U (en)
JPS58200197A (en) Structure for supporting pipe of reactor container