JPS5861497A - Stabilizer device of reactor container - Google Patents
Stabilizer device of reactor containerInfo
- Publication number
- JPS5861497A JPS5861497A JP56159831A JP15983181A JPS5861497A JP S5861497 A JPS5861497 A JP S5861497A JP 56159831 A JP56159831 A JP 56159831A JP 15983181 A JP15983181 A JP 15983181A JP S5861497 A JPS5861497 A JP S5861497A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor
- stabilizer
- main body
- shielding wall
- 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.)
- Granted
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Transition And Organic Metals Composition Catalysts For Addition Polymerization (AREA)
- Feeding, Discharge, Calcimining, Fusing, And Gas-Generation Devices (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
本発明は原子炉圧力容器を支持する原子炉格納容器スタ
ビライブ装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor containment vessel stabilizer for supporting a nuclear reactor pressure vessel.
従来、原子炉格納容器たとえばオーパアンダ形の原子炉
格納容器は第１図および第２図に示す如く構成されてい
た。すなわち、ＪＦｉ格納容器本体であって、たとえば
鉄筋コンクリートで形成され、耐圧性と放射線の遮蔽能
力を有している．そしてこの格納容器本体１の内面には
ライナー２が張設され、気密性を与えている．そして、
この格納容器本体１内はダイヤ７ラムフロア３によって
上下に区画され、上部はドライフェル４に、下部はサグ
レ，シ．ンチャンバ５に形成されている．そしてこの格
納容器本体１内にはペデスタル−が立設されておシ、こ
のペデスタル６上には原子炉圧力容器１が据付られてい
る．そして、この原子炉圧力容器！ｔー囲んで原子炉遮
蔽壁８が設けられている。そして、仁の原子炉遮蔽壁８
の上部には水平に設けられ喪スタビライデ９・・・ヲ介
して格納容器本体１に支持されておシ、地震等の際にこ
の原子炉遮蔽壁８に加わる水平方向の荷重管支持するよ
うに構成されている。ところで、従来これらのスタビラ
イプ９・・・は原子炉遮蔽壁１の上端部外周と格納容器
本体１の内周面との間に水平方向に設けられていた。こ
のため、主蒸気隔離弁１０等の取付、取外しｔなすホイ
ストクレーンの走行用のレール１１１や配管１ ｌ ｂ
−・等は上記スタビライプ９−・の下方に設けなければ
ならず、格納容器本体１の上部のスペースを有効に利用
できなか−）た。また、このようなレール１１ａから主
蒸気隔離弁１０等の機器までの距離はこれら機器の吊動
上げおよび作業のため、さらには空調ダクトの設置のた
めのある程度の距離を必要とする。したがりて上記の如
くレールＩｌａをスタビライプ９・・・の下方に配置す
るとその分だけ格納容器本体１が高くなシ、耐震設計上
不利であった。ｔた、上記スタビライプｔ・・・は鋼管
を溶接して構成されているが、これらスタビライプ９−
・の剛性が不足すると地震等の際に原子炉遮蔽壁８の共
振を生じる可能性があるため、これらスタビライプ９・
・・の剛性【大きくしなければならず、これらスタぜラ
イプ９・・・を構成する鋼管の径を大きくしなければな
らなかった。Conventionally, a nuclear reactor containment vessel, such as an op-under type reactor containment vessel, has been constructed as shown in FIGS. 1 and 2. That is, the main body of the JFi containment vessel is made of, for example, reinforced concrete, and has pressure resistance and radiation shielding ability. A liner 2 is stretched over the inner surface of the containment vessel body 1 to provide airtightness. and,
The inside of this containment vessel main body 1 is divided into upper and lower parts by a diamond 7 ram floor 3, with the upper part being a dry fell 4, and the lower part being a sagre, sieve, etc. is formed in the chamber 5. A pedestal is erected within the containment vessel main body 1, and the reactor pressure vessel 1 is installed on the pedestal 6. And this reactor pressure vessel! A reactor shielding wall 8 is provided surrounding the reactor. And Jin's reactor shielding wall 8
It is installed horizontally on the upper part of the reactor shield wall 8 and is supported by the containment vessel main body 1 through a stabilizer 9... to support the horizontal load tube that is applied to the reactor shielding wall 8 in the event of an earthquake or the like. It is configured. By the way, these stabilizers 9 have conventionally been provided horizontally between the outer periphery of the upper end of the reactor shielding wall 1 and the inner peripheral surface of the containment vessel body 1. For this reason, installation and removal of the main steam isolation valve 10, etc., rails 111 for hoist crane travel, piping 1 l b
-, etc. had to be provided below the stabilizer bars 9-, and the space above the containment vessel body 1 could not be used effectively. Further, a certain distance is required from the rail 11a to equipment such as the main steam isolation valve 10 for lifting and working of these equipment, and further for installing an air conditioning duct. Therefore, if the rail Ila is arranged below the stabilizer bars 9 as described above, the containment vessel main body 1 will be that much higher, which is disadvantageous in terms of seismic design. In addition, the above-mentioned stabilizer pipes t... are constructed by welding steel pipes, but these stabilizer pipes 9-
If the rigidity of the stabilizer bars 9 and 9 is insufficient, it may cause resonance of the reactor shielding wall 8 during an earthquake, etc.
The rigidity of... had to be increased, and the diameter of the steel pipes that make up these staggered pipes 9... had to be increased.
本発明は以上の事情にもとづいてなされたもので、その
目的とするところは内部の空間を有効に利用でき、高さ
を低くして耐震性を向上させることができるとともにス
タビライプの剛性を大きくできる原子炉格納容器を得る
ことにあ ゛る。The present invention was made based on the above circumstances, and its purpose is to make it possible to effectively utilize internal space, reduce the height, improve earthquake resistance, and increase the rigidity of the stabilizer rope. The goal is to obtain a reactor containment vessel.
すなわち本発明の構成は、原子炉遮蔽壁の上端と格納容
器本体とを連結するスタビライプを斜めまたは鉛直に配
置し、格納容器本体内上部のスペース會有効に利用でき
るようにし、またスタビライプの端部間を補助スタビラ
イプで互いに連結して剛性を高めたものである。In other words, the configuration of the present invention is to arrange the stabilizer pipe that connects the upper end of the reactor shielding wall and the containment vessel main body diagonally or vertically, so that the upper space inside the containment vessel main body can be effectively used, and the end of the stabilizer pipe is arranged diagonally or vertically. The rigidity is increased by connecting them with an auxiliary stabilizer rope.
以下本発明の第１実施例を第３図および第４図に示す一
実施例にしたがって説明する０図中１０１は格納容器本
体でありて、鉄筋コンクリートで強固に形成され、耐圧
性および放射線の遮蔽能力を有している。そして、仁の
格納容器本体１０１の内面には鋼板等からなるライナー
１０２が密着して張られておシ、このライナー１０２に
よりて気密性が与えている。そして、この格納容器本体
１０１内はダイヤプラムフロア１０Ｂによって上下に区
画され、上部はドライウェル１０４に、下部はサプレツ
ｅＶｗンチャンパ１０１に形成されている。を九、この
格納容器本体１０１内の中央部にはペデスタル１０６が
立設されておシ、このペデスタル１０ｉ上には原子炉圧
力容器１０１が据付けられている。Embodiment 1 of the present invention will be described below according to an embodiment shown in FIGS. 3 and 4. In FIG. have the ability. A liner 102 made of a steel plate or the like is tightly attached to the inner surface of the containment vessel main body 101, and this liner 102 provides airtightness. The inside of this containment vessel main body 101 is divided into upper and lower sections by a diaphragm floor 10B, with a dry well 104 formed in the upper part and a supplement eVwn chamber 101 formed in the lower part. (9) A pedestal 106 is erected in the center of the containment vessel main body 101, and the reactor pressure vessel 101 is installed on the pedestal 10i.
また、このペデスタル１０＃上には上記原子炉遮蔽壁＠
ｘｏｒ’を囲んで円筒状の原子炉遮蔽壁１０８が立設さ
れている。そして、この原子炉圧力容器Ｊａｒの上部と
原子炉遮蔽壁１０ｇとは原子炉圧力容器スタビライプＪ
Ｏ＃−”を介して連結されている。ｔた、１１０は主蒸
気配管であってその途中には主蒸気隔離弁１１１が設け
られている。また、仁の格納容器本体１０１の上部開口
には鋼製の７ラング部材１１１が設けられておシ、この
７ラング部材１１２には上蓋１１Ｊが着脱自在に取付け
られている。そして、上記原子炉遮蔽壁１ｏＪの上端部
と格納容器本体１０１との間には複数のスタビライプ１
１＃・・・が架は渡されている。そして、これらのスタ
ビライプ１１ｇ−・・の一端部は取付金具１１１・・・
を介して原子炉遮蔽壁１０ｇの上端部に取付けられ、ま
た他端部は半径方向に摺動自在なシアキー１１１−・・
會介して格納容器本体１０１の内面に取付けられている
。そして、これらスタビライプ１１６・−は第４図に示
す如くトラス状に組まれているとともに、これらスタビ
ライザＩ１ｇ−・・の他端部が上方に位置するように水
平方向に対して傾斜して配置されている。In addition, above this pedestal 10#, the above reactor shielding wall @
A cylindrical reactor shielding wall 108 is erected surrounding xor'. The upper part of the reactor pressure vessel Jar and the reactor shielding wall 10g are the reactor pressure vessel stabilizer pipe J.
In addition, 110 is a main steam pipe, and a main steam isolation valve 111 is provided in the middle of the main steam pipe. A seven rung member 111 made of steel is provided, and an upper cover 11J is detachably attached to this seven rung member 112.The upper end of the reactor shielding wall 1oJ and the containment vessel main body 101 are connected to each other. There are multiple stabilizer lines 1 between
1#... has been handed over. One end of these stabilizer bars 11g... is attached to the mounting bracket 111...
The shear key 111 is attached to the upper end of the reactor shielding wall 10g via the shear key 111, and the other end is slidable in the radial direction.
It is attached to the inner surface of the containment vessel main body 101 through an intermediary. These stabilizers 116.- are assembled in a truss shape as shown in FIG. 4, and are arranged at an angle with respect to the horizontal direction so that the other ends of the stabilizers I1g-- are positioned upward. ing.
また、これらスタビライプ１１６・・・の他端部は格納
容器本体１０１の内面のうち原子炉遮蔽壁１０１１の上
端との距離が最も小さい箇所に取付けられてお夛、これ
らスタビライザ１１６・・・の長さが最も短かくなるよ
うに構成されている。In addition, the other ends of these stabilizers 116 are attached to the inner surface of the containment vessel main body 101 at the point where the distance from the upper end of the reactor shielding wall 1011 is the smallest, and the length of these stabilizers 116... It is configured so that the length is the shortest.
壇た、スタビライプ１１６・・・の他端部間にはこれら
他端部を互いに連結する補助スタビライプ１１９・・・
が設けられてお夛、これらスタビライプＩ１ｇ−・・で
構成されるトラスの剛性を高めるように構成されている
。また、前記格納容器本体１０１内の上部には環状のホ
イスト走行レール１２０および配管１ ｊ Ｊ −・・
等が配置されている。Between the other ends of the stabilizer strips 116, there are auxiliary stabilizer bars 119 that connect these other ends to each other.
are provided in order to increase the rigidity of the truss made up of these stabilizers I1g. Further, in the upper part of the containment vessel main body 101, an annular hoist running rail 120 and piping 1 j J -...
etc. are arranged.
以上の如く構成された本発明の第１実施例は地震等によ
って原子炉圧力容器１０１に水平方向の荷重が生じると
、この水平方向の荷重は原子炉圧力容器スタビライプ１
０９−を介して原子炉遮蔽壁１０１１に伝えられ、さら
にこの荷重の方向と９０°ずれた位置にあるスタビライ
プ１１６・−１介して格納容器本体１０１に伝えられて
支持される。したがりて、このｙＸ子炉圧力容器１０１
の上端部の振れが防止される。また、これらスタビライ
プＪ １ ｇ−・・は水平方向に対して傾斜して設けら
れているので、格納容器本体１０１内上部のスペース【
有効に利用でき、ホイスト走行用レールＸＸＯ等管格納
容器本体１＃１内上部一杯に配置できるので格納容器本
体１０１の高さを低くでき、この格納容器本体１０１の
耐震性を向上させることがで龜る。壇良、これらスタビ
ライプ１１ｇ・・・の端部は補助スタビ２イデ７７ ｍ
ｌ−・・によって互いに連結されているので、これらス
タビライプ１１６・・・によって構成されるトラスの剛
性を高めることがで自る。In the first embodiment of the present invention configured as described above, when a horizontal load is generated on the reactor pressure vessel 101 due to an earthquake or the like, this horizontal load is applied to the reactor pressure vessel stabilizer 101.
09- to the reactor shielding wall 1011, and is further transmitted to and supported by the containment vessel main body 101 via the stabilizer bars 116 and -1, which are located 90 degrees apart from the direction of this load. Therefore, this yX child reactor pressure vessel 101
This prevents the upper end from swinging. In addition, since these stabilizer bars J 1 g-... are provided at an angle with respect to the horizontal direction, the upper space inside the containment vessel main body 101 [
It can be used effectively and the hoist running rail XXO etc. can be placed completely in the upper part of the containment vessel main body 1#1, so the height of the containment vessel main body 101 can be lowered and the earthquake resistance of this containment vessel main body 101 can be improved. It's cloudy. Danyoshi, the end of these stabilizers 11g... is auxiliary stabilizer 2ide 77m.
Since they are connected to each other by the stabilizers 116, the rigidity of the truss constituted by these stabilizers 116 can be increased.
オた、この第１実施例のものはスタビライプ１１ｇ−・
・の他端部が格納容器本体１０１内面のうち原子炉遮蔽
壁Ｏ上端に最も近い箇所Ｋｊｌ付けられているので、ス
タビライプ１１６・・・Ｏ長さが煙かく、剛性を一層高
めることができる。Oh, this first example has stabilizer 11g-.
- Since the other end is attached at the point Kjl closest to the upper end of the reactor shielding wall O on the inner surface of the containment vessel main body 101, the length of the stabilizer pipe 116...O is longer and the rigidity can be further increased.
なお、本発明は上記のｗｉ１実施例には限定されない・
たとえば第５図および＠６図には本発明の第２実施例を
示す、この第２実施例は前記原子炉遮蔽壁１０８の上端
面から上方に向けて複数のスタビライプ１１６′・・・
を鉛直に突設し、これらのスタビライプ１１６′・・・
の上端は格納容器本体１＃１０土壁部九と見ば前記の取
付金具１１４に取付けられている。なお％ＪＪＪ−・・
はこれらスタビライプ１１６′・・・會原子炉鐘蔽壁１
０１の上端に取付けるための取付金具であり工、原子炉
遮蔽壁１０Ｂの上端部に埋め込まれている。Note that the present invention is not limited to the above-mentioned wi1 embodiment. For example, FIG. 5 and @6 show a second embodiment of the present invention. A plurality of stabilizer lines 116' upward from the...
are vertically protruding, and these stabilizers 116'...
The upper end of the containment vessel main body 1 #10 soil wall part 9 is attached to the above-mentioned mounting bracket 114. In addition, %JJJ-・・
These stabilizer pipes 116'...Reactor bell shield wall 1
This is a mounting bracket for attaching to the upper end of the nuclear reactor shielding wall 10B.
そして、これらスタビライプ１１６′・・・は第６図に
示す如く局方向に連続し九トラス状に組まれてお夛、周
方向の荷重に対して耐えるように構成されている。した
がって、上記原子炉遮蔽壁１０８に作用する水平方向の
荷重はその荷重の方向と直交する方向の位置にあるスタ
ビライプ１１Ｃ・−によって受けられ、格納容器本体１
０１に伝えられるように構成されている。なお、この第
２実施例は上記の点以外は前記第１実施例と同様の構成
であシ、第５図および第６図中第１実施例に対応する部
分は同符号を附してその説明を省略する。そして、この
第２実施例はスタビライプ１１ ＩＩ’・・・が鉛直方
向に設けられているので格納容器本体１０１内上部のス
ペースを一層有効に利用できるものである。As shown in FIG. 6, these stabilizer strips 116' are arranged in a nine-truss configuration that continues in the central direction, and are constructed to withstand loads in the circumferential direction. Therefore, the horizontal load acting on the reactor shielding wall 108 is received by the stabilizer bars 11C, which are located in a direction perpendicular to the direction of the load, and the containment vessel main body 1
01. This second embodiment has the same structure as the first embodiment except for the above points, and the parts in FIGS. 5 and 6 that correspond to the first embodiment are denoted by the same reference numerals. The explanation will be omitted. In this second embodiment, since the stabilizer bars 11 II' are provided in the vertical direction, the upper space inside the containment vessel main body 101 can be used more effectively.
上述の如く本発明は原子炉遮蔽壁の上端と格納容器本体
との関を連結するスタビライプを水平向に対して斜めま
たは鉛直に配置したので、格納容器本体内上部のスペー
スを有効に利用でき、格納容器本体の高さを低くして耐
震性を向上させることができ、ｔたスタビライプ端部間
に補助スタビライプな設けてこれらスタビライプで構成
されるトラスの剛性を高めたので耐震性を一層向上させ
ることができる等その効果は大である。As described above, in the present invention, the stabilizer pipe connecting the upper end of the reactor shielding wall and the containment vessel main body is arranged diagonally or vertically with respect to the horizontal direction, so that the space above the containment vessel main body can be used effectively. Earthquake resistance can be improved by lowering the height of the main containment vessel, and auxiliary stabilizer strips are provided between the ends of the stabilizer strips to increase the rigidity of the truss made up of these stabilizer strips, further improving earthquake resistance. The effect is great.
＃Ｉ１図および第２図は従来例を示し第１図は縦断面図
、第２図は第１図の■−■矢視図である。第３図および
第４図は本発明の第１実施例を示し、第３図は縦断面図
、第４図は菖３図の■−■矢視図である。第５図および
第６図は本発明の第２実施例を示し、第５図は縦断面図
、第６図は第５図のＭ−Ｖ！矢視図である。
１０１・−格納容器本体、１０７／・・・原子炉圧力容
器、１０Ｂ−・・原子炉遮蔽壁、１１１ｊ ＃ １１６
’−・スタビライプ、１１９−・・補助スタビライプ。
第１図
第２図
第３図
第４図#I1 and FIG. 2 show a conventional example, in which FIG. 1 is a longitudinal cross-sectional view and FIG. 2 is a view taken along the line ■-■ in FIG. 1. 3 and 4 show a first embodiment of the present invention, in which FIG. 3 is a longitudinal cross-sectional view and FIG. 4 is a view taken along the arrows ■-■ of the irises 3. 5 and 6 show a second embodiment of the present invention, in which FIG. 5 is a longitudinal sectional view and FIG. It is an arrow view. 101--Containment vessel main body, 107/... Reactor pressure vessel, 10B-- Reactor shielding wall, 111j # 116
'-・Stabilipe, 119-・・Auxiliary stabilizeripe. Figure 1 Figure 2 Figure 3 Figure 4
Claims (2)
れた原子炉圧力容器を囲んで設けられた円筒状の原子炉
遮蔽壁と、一端がこの原子炉遮蔽壁の上端部に取けられ
他端が上記格納容器内向上部に取付けられ他端が一端よ
シ上方に位置するように水平方向に対して傾斜してまた
は鉛直に配置されトラス状に組まれた複数のスタビライ
プと、これらスタビライプの端部間を互いに連結する補
助スタビライプと會具備したことを特徴とする原子炉格
納容器スタビライプ装置。(1) A containment vessel body, a cylindrical reactor shielding wall provided surrounding the reactor pressure vessel housed in the containment vessel body, and one end of which is attached to the upper end of the reactor shielding wall. A plurality of stabilizers arranged in a truss-like manner, arranged inclined or vertically with respect to the horizontal direction so that one end is attached to the upper part of the inside of the containment vessel and the other end is located above the other end; 1. A reactor containment vessel stabilizer rope device, characterized in that it is equipped with an auxiliary stabilizer rope that connects end portions to each other.
の上端に最も近い位置の格納容器本体の内面に取付けら
れているヒとを特徴とする特許許鯖求の範囲第１項記載
の原子炉格納容器スタビライブ装置。(2) The reactor according to item 1 of the scope of the patent application, wherein the other end of the stabilizer strip is attached to the inner surface of the containment vessel body at a position closest to the upper end of the reactor shielding wall. Containment vessel stabilizer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56159831A JPS5861497A (en) | 1981-10-07 | 1981-10-07 | Stabilizer device of reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56159831A JPS5861497A (en) | 1981-10-07 | 1981-10-07 | Stabilizer device of reactor container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5861497A true JPS5861497A (en) | 1983-04-12 |
| JPS6257238B2 JPS6257238B2 (en) | 1987-11-30 |
Family
ID=15702196
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56159831A Granted JPS5861497A (en) | 1981-10-07 | 1981-10-07 | Stabilizer device of reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5861497A (en) |
-
1981
- 1981-10-07 JP JP56159831A patent/JPS5861497A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6257238B2 (en) | 1987-11-30 |
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