JPH0350479Y2 - - Google Patents
Info
- Publication number
- JPH0350479Y2 JPH0350479Y2 JP1985067903U JP6790385U JPH0350479Y2 JP H0350479 Y2 JPH0350479 Y2 JP H0350479Y2 JP 1985067903 U JP1985067903 U JP 1985067903U JP 6790385 U JP6790385 U JP 6790385U JP H0350479 Y2 JPH0350479 Y2 JP H0350479Y2
- Authority
- JP
- Japan
- Prior art keywords
- shielding wall
- steel container
- cladding tube
- pipe
- inner shielding
- 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
Links
- 238000005253 cladding Methods 0.000 claims description 26
- 229910000831 Steel Inorganic materials 0.000 claims description 22
- 239000010959 steel Substances 0.000 claims description 22
- 230000035515 penetration Effects 0.000 claims description 5
- 238000000034 method Methods 0.000 description 13
- 239000002826 coolant Substances 0.000 description 6
- 239000012530 fluid Substances 0.000 description 3
- 230000000149 penetrating effect Effects 0.000 description 3
- 238000007789 sealing Methods 0.000 description 3
- 230000008646 thermal stress Effects 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 230000008602 contraction Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000035882 stress Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Installation Of Indoor Wiring (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における配管の壁貫通
部の構造に関するものである。[Detailed Description of the Invention] "Industrial Application Field" The present invention relates to the structure of a wall penetrating portion of piping in a nuclear reactor containment vessel.
「従来の技術」
高速増殖炉（以下FBRという）の格納容器は、
鋼製容器の内側および外側にコンクリート製の遮
蔽壁を設け、内側遮蔽壁の内部にN2ガスを充填
するとともに、内外の遮蔽壁と鋼製格納容器との
間の空間部を減圧状態とすることによつて、万一
の冷却材（金属ナトリウム）の漏洩に対する冷却
材と空気との接触を防止するようにした構造を採
用する計画となつている。"Conventional technology" The containment vessel of a fast breeder reactor (hereinafter referred to as FBR) is
Concrete shielding walls are installed inside and outside the steel container, and the inside of the inner shielding wall is filled with N2 gas, and the space between the inner and outer shielding walls and the steel containment vessel is reduced in pressure. In particular, the plan is to adopt a structure that will prevent the coolant (metallic sodium) from coming into contact with the air in the unlikely event that the coolant (metallic sodium) leaks.
ところで、前記FBRの格納容器の容器壁には、
冷却材を初めとする種々の流体が流される数多く
のプロセス配管を貫通させる必要があり、このプ
ロセス配管の貫通部には、該配管中を流れる高温
の流体の熱が容器壁（特にコンクリート部分）に
伝わるのを防止し、かつ格納容器内外のバウンダ
リーとしての気密性を発揮し得る構造を採用する
ことが必要とされている。 By the way, on the container wall of the FBR containment vessel,
It is necessary to penetrate a large number of process pipes through which various fluids including coolant flow, and the heat of the high temperature fluid flowing through the pipes is transferred to the container wall (particularly the concrete part). It is necessary to adopt a structure that can prevent the air from being transmitted to the inside and outside of the containment vessel and provide airtightness as a boundary between the inside and outside of the containment vessel.
このような条件を満たす配管貫通部の構造とし
て、プロセス配管の壁貫通部にスリーブを被せて
プロセス配管と容器壁との直接接触を避けるよう
にするとともに、プロセス配管およびスリーブと
容器壁とをベローズ継手等によつて相対移動可能
に連結して、プロセス配管の熱伸縮による熱応力
が容器壁に加わることを防止すようことが考えら
れる。 The structure of the pipe penetration part that satisfies these conditions is to cover the wall penetration part of the process pipe with a sleeve to avoid direct contact between the process pipe and the container wall, and to attach a bellows between the process pipe and the sleeve and the container wall. It is conceivable to connect them so that they can move relative to each other using a joint or the like to prevent thermal stress caused by thermal expansion and contraction of the process piping from being applied to the container wall.
「考案が解決しようとする問題点」
しかしながら、一般のパイプ材に比して強度面
で劣つているベローズ継手は、その信頼性を維持
するため、原子炉の運転開始前はもとより、運転
開始後にも、リークテスト、あるいは種々のメン
テナンス作業を行つて信頼性を維持することが必
要とされるから、工期の短縮、あるいは、運転開
始後の放射線環境下におけるメンテナス作業の軽
減を図るためには、ベローズ継手の設置個数を可
能な限り少なくすることが望ましい。``Problem that the invention aims to solve'' However, bellows joints are inferior in strength to ordinary pipe materials, and in order to maintain their reliability, they must be However, it is necessary to perform leak tests and perform various maintenance work to maintain reliability, so in order to shorten the construction period or reduce maintenance work in a radiation environment after the start of operation, It is desirable to minimize the number of bellows joints installed.
本考案は上記事情に鑑みて提案されたもので、
できるだけ少ない個数のベローズ継手を使用して
プロセス配管と格納容器との間の熱応力の発生を
防止し、かつ、地震等に際して確実に配管を拘束
し得るとともに、構造が簡単で十分な耐久力を持
つた配管貫通部の構造を得ることを目的とするも
のである。 This idea was proposed in view of the above circumstances.
By using as few bellows joints as possible, we can prevent the occurrence of thermal stress between the process piping and the containment vessel, securely restrain the piping in the event of an earthquake, etc., and have a simple structure with sufficient durability. The purpose of this is to obtain a structure for a pipe penetrating part that has the same structure.
「問題点を解決するための手段」
上記目的を達成するため、本考案は、鋼製容器
とコンクリート製の内側遮蔽壁とを貫通する配管
の外周に、前記内側遮蔽壁側で前記配管に一端が
気密に固着されかつ他端の外周部が鋼製容器に気
密に固着された外部被覆管を設け、該外部被覆管
と前記内側遮蔽壁との間に、これらを気密に固定
するアンカー部材を設け、前記外部被覆管におけ
る前記アンカー部材との固着箇所と前記鋼製容器
との固着箇所との間に、これら両固着箇所の間を
相対移動可能にかつ気密に連結するベローズ継手
を設けたことを特徴とする。"Means for Solving the Problems" In order to achieve the above object, the present invention provides a method for attaching an end to the pipe on the outer circumference of the pipe penetrating the steel container and the inner shielding wall made of concrete, on the side of the inner shielding wall. An outer cladding tube is provided, the outer periphery of which is airtightly fixed to the steel container at the other end, and an anchor member is provided between the outer cladding tube and the inner shielding wall to fix these in an airtight manner. and a bellows joint is provided between a fixed point in the outer cladding tube to the anchor member and a fixed point to the steel container, which connects both fixed points in a relatively movable and airtight manner. It is characterized by
「作用」
本考案の構造においては、アンカー部材が外部
被覆管と内側遮蔽壁との間の密閉とこれらの固定
との二つの機能を果しており、外部被覆管が固着
されている配管は、このアンカー部材を介して内
側遮蔽壁に直接的に固定される。また、このアン
カー部材と鋼製容器との間の範囲で外部被覆管に
ベローズ継手が設けられていることにより、該ベ
ローズ継手によつて内側遮蔽壁と鋼製容器との間
の相対移動を吸収することができる。"Function" In the structure of the present invention, the anchor member performs the two functions of sealing between the outer cladding pipe and the inner shielding wall and fixing them, and the piping to which the outer cladding pipe is fixed is It is directly fixed to the inner shielding wall via the anchor member. In addition, since a bellows joint is provided in the outer cladding pipe in the range between this anchor member and the steel container, the relative movement between the inner shielding wall and the steel container is absorbed by the bellows joint. can do.
「実施例」
以下、図面を参照して本考案の一実施例を説明
する。"Embodiment" Hereinafter, an embodiment of the present invention will be described with reference to the drawings.
図中符号１は鋼製容器であつて、この鋼製容器
１の内側および外側には、該鋼製容器１の厚さ方
向に間隔をおいて、コンクリート製の内側遮蔽壁
２および外側遮蔽壁３がそれぞれ設けられてい
る。そして、これら鋼製容器１、内側遮蔽壁２、
および外側遮蔽壁３を貫通する如くプロセス配管
Ｐが設けられている。また、該プロセス配管Ｐ
は、FBRの冷却材等の流体が流通させられる内
管４と、該内管４の内面に漏洩検出用の空間部を
形成する内装板５とからなる二重構造となつてい
る。 Reference numeral 1 in the figure is a steel container, and inside and outside of this steel container 1, an inner shielding wall 2 and an outer shielding wall made of concrete are provided at intervals in the thickness direction of the steel container 1. 3 are provided respectively. These steel containers 1, inner shielding walls 2,
A process pipe P is provided so as to penetrate through the outer shielding wall 3. In addition, the process piping P
has a double structure consisting of an inner tube 4 through which fluid such as FBR coolant flows, and an interior plate 5 that forms a space for leak detection on the inner surface of the inner tube 4.
前記プロセス配管Ｐの外周には、該プロセス配
管Ｐに対して同心状に内部被覆管６と外部被覆管
７とが設けられており、プロセス配管Ｐと内部被
覆管６との間の空間部８（なお、この空間部８に
は、保温材（図示略）が充填されている）、およ
び内部外部の被覆管６，７の間の空間部９は、い
ずれも原子炉格納容器の内側の端部で密閉されて
いる。すなわち、外部被覆管７の内側端部は、プ
ロセス配管Ｐの外周に気密に固着され、一方、内
部被覆管６の内側端部は、外部被覆管７の内周に
気密に固着されている。 An inner cladding tube 6 and an outer cladding tube 7 are provided on the outer periphery of the process piping P concentrically with respect to the process piping P, and a space 8 between the process piping P and the inner cladding tube 6 is provided. (Note that this space 8 is filled with a heat insulating material (not shown)) and the space 9 between the internal and external cladding tubes 6 and 7 is located at the inner end of the reactor containment vessel. The area is sealed. That is, the inner end of the outer cladding tube 7 is hermetically secured to the outer periphery of the process piping P, while the inner end of the inner cladding tube 6 is hermetically secured to the inner periphery of the outer cladding tube 7.
また、外部被覆管７の外側の端部は、その外周
部が鋼製容器１に固着されるとともに、長さ方向
中間部は分割構造とされ、この分割部分は、ベロ
ーズ継手１０，１０によつて気密にかつ相対移動
可能に連結されている。そして、このベローズ継
手１０は、弾性変形可能な薄板からなる本体１１
と該本体１１の外周を覆つてこれを保護するカバ
ー１２とから構成されている。 Further, the outer end of the outer cladding tube 7 is fixed to the steel container 1 at its outer periphery, and has a split structure at the middle part in the length direction, and this split part is connected to the bellows joints 10, 10. and are connected airtightly and relatively movably. This bellows joint 10 has a main body 11 made of an elastically deformable thin plate.
and a cover 12 that covers and protects the outer periphery of the main body 11.
前記外部被覆管７の内側端部と内側遮蔽壁２と
の間には、アンカー部材１３が設けられている。
このアンカー部材１３は、弾性変形可能な図に示
す如き縦断面形状に形成してなるもので、内側遮
蔽壁２の表面を覆うライナープレート２ａに気密
に固着される円盤部１４と、該円盤部１４と一体
にかつ弾性変形可能に形成されて外部被覆管７に
気密に固着されるテーパー部１５とから構成され
ている。 An anchor member 13 is provided between the inner end of the outer cladding tube 7 and the inner shielding wall 2.
The anchor member 13 is elastically deformable and has a longitudinal cross-sectional shape as shown in the figure, and includes a disk portion 14 that is airtightly fixed to a liner plate 2a that covers the surface of the inner shielding wall 2, and 14 and a tapered portion 15 that is formed integrally with the outer cladding tube 7 so as to be elastically deformable and hermetically fixed to the outer cladding tube 7.
そして、前記アンカー部材１３によつて、内側
遮蔽壁２内の空間部１６と、内側遮蔽壁２〜鋼製
容器１間の空間部１７との間のバウンダリー（境
界）が形成され、さらに、ベローズ継手１０によ
つて、鋼製容器１〜外側遮蔽壁３間の空間部１８
（および内外の被覆管６，７間の空間部９）と前
記空間部１７との間のバウンダリーが形成されて
いる。 The anchor member 13 forms a boundary between a space 16 within the inner shielding wall 2 and a space 17 between the inner shielding wall 2 and the steel container 1, and furthermore, a bellows The space 18 between the steel container 1 and the outer shielding wall 3 is formed by the joint 10.
A boundary is formed between the space 17 (and the space 9 between the inner and outer cladding tubes 6 and 7) and the space 17.
なお、前記配管Ｐは、図示する貫通部以外の箇
所においても屈曲部（ベンド）等が設けられるこ
とにより、熱伸縮による応力の発生を緩和し得る
ようになつている。 Note that the pipe P is provided with bends and the like at locations other than the illustrated through-holes, so that stress caused by thermal expansion and contraction can be alleviated.
さらに、外側遮蔽壁３と内部被覆管６との間に
は、シール部材１９が設けられており、このシー
ル部材１９は、前記空間部１８と容器外の空間部
２０との間を気密に仕切るとともに、これらの間
で弾性変形可能な構造とされている。 Further, a sealing member 19 is provided between the outer shielding wall 3 and the inner cladding tube 6, and this sealing member 19 airtightly partitions the space 18 and the space 20 outside the container. In addition, it has a structure that can be elastically deformed between these.
前述の如き構造が配管貫通部に採用された原子
炉格納容器においては、内側遮蔽壁２の内側の空
間部１６にN2ガスを充填するとともに、この鋼
製容器１と内側外側の遮蔽壁２，３それぞれとの
間の空間部１７，１８を大気圧に対してマイナス
50〜150mmAq程度に減圧することにより、空間部
１６内への空気の侵入を防止して、万一の冷却材
漏洩に際しての冷却材の急激な化学反応を防止す
ることができ、さらには、放射性物質の格納容器
外への漏洩を確実に防止することができる。 In a reactor containment vessel in which the above-mentioned structure is adopted for the pipe penetration part, the space 16 inside the inner shielding wall 2 is filled with N 2 gas, and the steel vessel 1 and the inner and outer shielding walls 2 are filled with N2 gas. , 3, the spaces 17 and 18 between them are negative with respect to atmospheric pressure.
By reducing the pressure to about 50 to 150 mmAq, it is possible to prevent air from entering the space 16 and prevent a rapid chemical reaction of the coolant in the event of a coolant leak. Furthermore, it is possible to prevent radioactive It is possible to reliably prevent substances from leaking out of the containment vessel.
「考案の効果」
以上の説明で明らかなように、本考案の配管貫
通部構造によれば次のような効果を奏する。"Effects of the Invention" As is clear from the above explanation, the pipe penetration structure of the present invention provides the following effects.
配管に固着した外部被覆管にアンカー部材を
設けたことによつて、配管を内側遮蔽壁に直接
的に固定し得て、地震等に際して確実に拘束す
ることができる。 By providing the anchor member on the outer sheathing tube fixed to the piping, the piping can be directly fixed to the inner shielding wall and can be securely restrained in the event of an earthquake or the like.
外部被覆管におけるアンカー部材との固着箇
所と鋼製容器との固着箇所との間にベローズ継
手が設けられているから、内側遮蔽壁と鋼製容
器間の相対移動を吸収し得て、熱応力の発生を
抑制することができる。 Since a bellows joint is provided between the anchor member and the steel container in the outer cladding, the relative movement between the inner shielding wall and the steel container can be absorbed and thermal stress can be absorbed. The occurrence of can be suppressed.
外部被覆管は一端が配管に気密に固着されて
いるから、これら両管の間のリング状の空間部
と、内側遮蔽壁の内部の空間部との間を区画
し、また、アンカー部材は外部被覆管と内側遮
蔽壁との間を気密に接続しているから、内側遮
蔽壁と鋼製容器との間の空間部と、内側遮蔽壁
の内部の空間部との間を区画することができ、
これら外部被覆管とアンカー部材とによつて確
実にバウンダリーを構成することができる。 Since one end of the outer cladding tube is airtightly fixed to the piping, a ring-shaped space between these two tubes and a space inside the inner shielding wall are partitioned, and the anchor member is attached to the outside. Since the cladding pipe and the inner shielding wall are connected airtightly, it is possible to partition the space between the inner shielding wall and the steel container and the space inside the inner shielding wall. ,
A boundary can be reliably formed by these outer cladding tubes and anchor members.
図面は本考案の一実施例を示す縦断面図であ
る。
１……鋼製容器、２……内側遮蔽壁、３……外
側遮蔽壁、１０……ベローズ継手、１３……アン
カー部材、１４……円盤部、１５……テーパー
部、Ｐ……配管。
The drawing is a longitudinal sectional view showing an embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Steel container, 2... Inner shielding wall, 3... Outer shielding wall, 10... Bellows joint, 13... Anchor member, 14... Disc part, 15... Taper part, P... Piping.
Claims (1)
通する配管の外周に、前記内側遮蔽壁側で前記配
管に一端が気密に固着されかつ他端の外周部が鋼
製容器に気密に固着された外部被覆管を設け、該
外部被覆管と前記内側遮蔽壁との間に、これらを
気密に固定するアンカー部材を設け、前記外部被
覆管における前記アンカー部材との固着箇所と前
記鋼製容器との固着箇所との間に、これら両固着
箇所の間を相対移動可能にかつ気密に連結するベ
ローズ継手を設けたことを特徴とする原子炉格納
容器の配管貫通部構造。 On the outer periphery of a pipe that penetrates a steel container and an inner shielding wall made of concrete, one end is hermetically fixed to the pipe on the side of the inner shielding wall, and the outer periphery of the other end is hermetically fixed to the steel container. An outer cladding tube is provided, and an anchor member is provided between the outer cladding tube and the inner shielding wall to fix these in an airtight manner, and a portion of the outer cladding tube where the anchor member is fixed is connected to the steel container. A piping penetration structure for a nuclear reactor containment vessel, characterized in that a bellows joint is provided between the fixed locations and the fixed locations are relatively movably and airtightly connected.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985067903U JPH0350479Y2 (en) | 1985-05-08 | 1985-05-08 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1985067903U JPH0350479Y2 (en) | 1985-05-08 | 1985-05-08 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61182899U JPS61182899U (en) | 1986-11-14 |
| JPH0350479Y2 true JPH0350479Y2 (en) | 1991-10-28 |
Family
ID=30602157
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1985067903U Expired JPH0350479Y2 (en) | 1985-05-08 | 1985-05-08 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0350479Y2 (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56137197A (en) * | 1980-03-28 | 1981-10-26 | Tokyo Shibaura Electric Co | Pipe through portion structure for nuclear reactor container |
-
1985
- 1985-05-08 JP JP1985067903U patent/JPH0350479Y2/ja not_active Expired
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56137197A (en) * | 1980-03-28 | 1981-10-26 | Tokyo Shibaura Electric Co | Pipe through portion structure for nuclear reactor container |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61182899U (en) | 1986-11-14 |
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