JPS58156Y2 - Shielding structure of reactor shielding wall opening - Google Patents
Shielding structure of reactor shielding wall openingInfo
- Publication number
- JPS58156Y2 JPS58156Y2 JP1978069578U JP6957878U JPS58156Y2 JP S58156 Y2 JPS58156 Y2 JP S58156Y2 JP 1978069578 U JP1978069578 U JP 1978069578U JP 6957878 U JP6957878 U JP 6957878U JP S58156 Y2 JPS58156 Y2 JP S58156Y2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pipe
- opening
- rpv
- shield
- 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
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
- Pressure Vessels And Lids Thereof (AREA)
Description
【考案の詳細な説明】
本考案は原子炉遮蔽壁開口部の遮蔽構造に係り、特に原
子炉圧力容器からのブローダウンが原子炉圧力容器と原
子炉遮蔽壁との間に流れ込まないようにするのに好適な
原子炉遮蔽壁開口部の遮蔽構造に関する。[Detailed description of the invention] The present invention relates to a shielding structure for an opening in a reactor shielding wall, and in particular, to prevent blowdown from the reactor pressure vessel from flowing between the reactor pressure vessel and the reactor shielding wall. The present invention relates to a shielding structure for an opening in a nuclear reactor shielding wall suitable for use in a nuclear reactor shielding wall.
一般に、原子炉圧力容器(以下RPVと称す)の周囲は
、約300ないし400 mm離れて原子炉遮蔽壁(以
下R8Wと称す)に取り巻かれている。Generally, a reactor pressure vessel (hereinafter referred to as RPV) is surrounded by a reactor shield wall (hereinafter referred to as R8W) at a distance of about 300 to 400 mm.
配管破断対策としての破断想定個所であるRPVノズル
と配管との溶接部は、そのほとんどがRPVR8W環状
部内に位置している。Most of the welded parts between the RPV nozzle and the pipe, which are expected to break as a measure against pipe breakage, are located within the annular part of the RPVR8W.
このため、万一破断した場合にRPV側からのブローダ
ウンは、この狭い環状部内に流れ込み、圧力上昇を生じ
させ、R8W基部およびRPV基部に多大なモーメント
と剪断力とを生じさせることになる。Therefore, in the event of a rupture, blowdown from the RPV side will flow into this narrow annular portion, causing a pressure increase and creating a large moment and shear force at the R8W base and the RPV base.
また、R3WのRPVノズル開口部には、溶接部のIS
I (供用期間中検査)のため、着脱可能な環状の遮蔽
体が取付けられており、したがって、遮蔽体のジェット
力に対しての大きなサポートが必要である。In addition, the RPV nozzle opening of R3W has an IS of the welded part.
For In-Service Inspection, a removable annular shield is installed and therefore requires significant support for the jet forces of the shield.
しかし、これは放射線下のISIの作業を考えると、サ
ポートの取外し作業が増大して好ましいことではない。However, considering the ISI work under radiation, this increases the work to remove the support, which is not desirable.
本考案は前記従来の難点を解決し、RPV側からのブロ
ーダウンがRPV−R3W環状部内に流入することがな
く、シたがって遮蔽体、RPVおよびR3Wにジェット
荷重が加わらない原子炉遮蔽壁開口部の遮蔽構造を提供
することを目的とする。The present invention solves the above-mentioned conventional difficulties, and the blowdown from the RPV side does not flow into the RPV-R3W annular part, so no jet load is applied to the shield, RPV, and R3W through the reactor shield wall opening. The purpose is to provide a shielding structure for the area.
本考案は、遮蔽体に配管との間に所要の間隙を有する分
割型のパイプを嵌合し、このパイプを原子炉運転中の熱
膨張を吸収可能なスライド機構を介してノズルに固着さ
れたシールリングに着脱可能に連結し、RPV側からの
ブローダウンが、RPV−R8W環状部内に流入せず、
配管と分割型のパイプとの間を通ってR8W外部に吹き
出されるように構成したものである。The present invention involves fitting a split pipe with a required gap between the shield and the piping, and fixing this pipe to the nozzle via a slide mechanism that can absorb thermal expansion during reactor operation. It is removably connected to the seal ring, and blowdown from the RPV side does not flow into the RPV-R8W annular part.
It is configured so that it passes between the piping and the split pipe and is blown out to the outside of the R8W.
以下本考案を図示する一実施例に基づいて説明する。The present invention will be described below based on an illustrated embodiment.
第1図において1はRPVであり、このRPVlの所要
位置にはRPVノズル2が一体に設けられ、またRPV
1外周にはR8W3がRPVlを被覆するように立設さ
れている。In FIG. 1, 1 is an RPV, and an RPV nozzle 2 is integrally provided at a required position of this RPVl.
1, R8W3 is erected on the outer periphery so as to cover RPV1.
そして、R3W3のRPVノズル2に対向する位置には
開口部4が設けられ、この開口部4には環状の遮蔽体5
が着脱可能に埋設されている。An opening 4 is provided at a position facing the RPV nozzle 2 of R3W3, and an annular shield 5 is provided in this opening 4.
is removably embedded.
遮蔽体5内には、第1図に示すように先端がRPVノズ
ル2に溶着された配管6が遊嵌され、また遮蔽体5には
、配管6との間に所要の間隙を有し、かつ先端がRPV
ノズル2まで達する分割型(本実施例においては二つ割
り)のパイプ7が嵌合されている。A pipe 6 whose tip end is welded to the RPV nozzle 2 is loosely fitted into the shield 5 as shown in FIG. 1, and the shield 5 has a required gap between it and the pipe 6. And the tip is RPV
A split pipe 7 (split into two in this embodiment) that reaches the nozzle 2 is fitted.
そして、このパイプ7は、スライド機構8を介してRP
Vノズル2に固着されたシールリング9に着脱可能に連
結されている。Then, this pipe 7 is connected to the RP via a slide mechanism 8.
It is removably connected to a seal ring 9 fixed to the V nozzle 2.
このシールリング9は、原子炉運転中の熱膨張による伸
びを吸収するため上下方向のラップ代が充分取られてい
る。This seal ring 9 has a sufficient amount of overlap in the vertical direction to absorb elongation due to thermal expansion during nuclear reactor operation.
スライド機構8は、第2図に示すようにパイプ7に固着
され、かつシールリング9との対向側にあり溝を有する
連結部8aと、シールリング9に固着され、前記あり溝
にスライド係合可能な保合部8bとから形成され、原子
炉運転中の熱膨張による伸びを吸収できるように構成さ
れている。As shown in FIG. 2, the slide mechanism 8 has a connecting portion 8a that is fixed to the pipe 7 and has a groove on the side opposite to the seal ring 9, and a connecting portion 8a that is fixed to the seal ring 9 and slides into the dovetail groove. It is formed from a possible retaining portion 8b, and is configured to absorb elongation due to thermal expansion during reactor operation.
なお第1図において10は、RPvノズル2と配管6と
の溶接線、11はRPVlとR3W3との間に形成され
たRPV−R8W環状部である。In FIG. 1, 10 is a weld line between the RPv nozzle 2 and the pipe 6, and 11 is an RPV-R8W annular portion formed between RPVl and R3W3.
以上の構成において、万−RPVノズル2溶接部で破断
が生じた場合には、RP■ノズル2からのジェットは、
RPV−R8W環状部11内へのルートが絶たれている
ため、配管6とパイプ7との間を通ってR3W3外部へ
排出される。In the above configuration, if a break occurs at the welded part of the RPV nozzle 2, the jet from the RP nozzle 2 will
Since the route into the RPV-R8W annular portion 11 is cut off, it passes between the pipe 6 and the pipe 7 and is discharged to the outside of the R3W3.
なお、原子炉運転中の熱膨張による伸びは、シールリン
グ9を上下方向に移動させるように作用するが、シール
リング9とパイプ7との連結は、スライド機構8を介し
てなされているため、RPv−R3W環状部11内への
ジェット流入はほとんどなくなる。Note that elongation due to thermal expansion during reactor operation acts to move the seal ring 9 in the vertical direction, but since the seal ring 9 and the pipe 7 are connected via the slide mechanism 8, The jet inflow into the RPv-R3W annular portion 11 is almost eliminated.
以上説明したように本実施例によれば、R3WおよびR
PVの設計荷重を低減することができ、これにより基部
アンカーボルトの本数および構造材が削減できる。As explained above, according to this embodiment, R3W and R
The design load of the PV can be reduced, thereby reducing the number of base anchor bolts and structural materials.
また、開口部遮蔽体のサポートを省略することができる
ことからISI時の取外し作業が削減され、被爆低減化
を企図することができる。Furthermore, since support for the opening shield can be omitted, removal work during ISI can be reduced, and radiation exposure can be reduced.
以上本考案を好適な実施例に基づいて説明したが、本考
案によれば、RPV側からのブローダウンがRPV−R
8W環状部内に流入することがなく、したがって遮蔽体
、RPVおよびR8Wにジェットの荷重が加わらないよ
うにすることができる。The present invention has been explained above based on the preferred embodiments. According to the present invention, blowdown from the RPV side
There is no flow into the 8W annular portion, thus preventing the jet load from being applied to the shield, RPV and R8W.
第1図は本考案の一実施例を示す縦断面図、第2図は第
1図II −II線矢視図である。
1・・・・・・RPV、2・・・・・・RPVノズル、
3・・・・・・R3W、4・・・・・・開口部、5・・
・・・・遮蔽体、6・・・・・・配管、7・・・・・・
パイプ、8・・・・・・スライド機構、9・・・・・・
シールリング。FIG. 1 is a longitudinal sectional view showing an embodiment of the present invention, and FIG. 2 is a view taken along the line II--II in FIG. 1...RPV, 2...RPV nozzle,
3...R3W, 4...Opening, 5...
...shield, 6...piping, 7...
Pipe, 8...Slide mechanism, 9...
Seal ring.
Claims (1)
炉圧力容器ノズルに対向する位置に開口部を設け、この
開口部に環状の遮蔽体を配置し、かつ原子炉容器ノズル
に溶着された配管を前記遮蔽体に挿嵌してなる原子炉遮
蔽壁開口部の遮蔽構造において、遮蔽体に、配管との間
に所要の間隙を有する分割型のパイプを嵌合し、このパ
イプは、ノズルに固着されたシールリングに、原子炉運
転中の熱膨張を吸収可能なスライド機構を介して着脱可
能に連結されてなることを特徴とする原子炉遮蔽壁開口
部の遮蔽構造。An opening is provided in a reactor shielding wall provided around the reactor pressure vessel at a position facing the reactor pressure vessel nozzle, and an annular shield is placed in this opening and is welded to the reactor vessel nozzle. In the shielding structure for the opening of the reactor shielding wall, in which the piping is inserted into the shield, a split pipe having a required gap between the pipe and the pipe is fitted into the shield, and the pipe has the following features: A shielding structure for an opening in a nuclear reactor shielding wall, characterized in that it is removably connected to a seal ring fixed to a nozzle via a slide mechanism capable of absorbing thermal expansion during nuclear reactor operation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1978069578U JPS58156Y2 (en) | 1978-05-23 | 1978-05-23 | Shielding structure of reactor shielding wall opening |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1978069578U JPS58156Y2 (en) | 1978-05-23 | 1978-05-23 | Shielding structure of reactor shielding wall opening |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS54171099U JPS54171099U (en) | 1979-12-03 |
| JPS58156Y2 true JPS58156Y2 (en) | 1983-01-05 |
Family
ID=28978527
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1978069578U Expired JPS58156Y2 (en) | 1978-05-23 | 1978-05-23 | Shielding structure of reactor shielding wall opening |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58156Y2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP6526391B2 (en) * | 2014-06-30 | 2019-06-05 | 三菱重工業株式会社 | Piping protection device and nuclear equipment |
-
1978
- 1978-05-23 JP JP1978069578U patent/JPS58156Y2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS54171099U (en) | 1979-12-03 |
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