JPS607388A - Supporter for nuclear reactor containing vessel - Google Patents
Supporter for nuclear reactor containing vesselInfo
- Publication number
- JPS607388A JPS607388A JP58115247A JP11524783A JPS607388A JP S607388 A JPS607388 A JP S607388A JP 58115247 A JP58115247 A JP 58115247A JP 11524783 A JP11524783 A JP 11524783A JP S607388 A JPS607388 A JP S607388A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- containment vessel
- shear lug
- reactor containment
- support structure
- 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.)
- Pending
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
- 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】
〔発明の技術分野〕
本発明は、原子力発電所の原子炉建屋内に原子炉格納容
器を支持する原子炉格納容器の支持構１６に係り、特に
原子炉建屋のシールド壁に加わる水平方向の地震力の影
響を緩４１１させる原子炉、１省納容器の支持装置に関
する。Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a reactor containment vessel support structure 16 that supports a reactor containment vessel within a reactor building of a nuclear power plant, and particularly relates to a reactor containment vessel support structure 16 that supports a reactor containment vessel within a reactor building of a nuclear power plant. This invention relates to a support device for a nuclear reactor and a storage vessel that reduces the influence of horizontal seismic forces applied to walls.
〔発明の技術的背景とその間；但、【よ〕一般に、沸騰
水型原子力発電所の原子炉建屋１内に第１図に示すよう
に原子炉格納容器２が支持され、この原子炉格納容器２
内に原子炉圧力６ Ｂ３３が収納される。原子炉圧力容
器３は、原子炉圧力容器ペグイスタル上に保持され、筒
状の原子炉遮蔽壁４により炉心部が憶われる。具体的に
は、第２図に示すように、原子炉圧力容器３は原子炉遮
蔽壁４に原子炉スタビライザ６を介して支持される一方
、原子炉遮蔽壁５は、原子炉格納容器スタビライザ７お
よび内側シアラグ８を介して原子炉・にも納容器２に支
持される。内側シアラグ８は原子炉格納容器スタビライ
ザ７の先端部と原子炉格納容器２の内周壁面とを、原子
炉イ６納谷器２の上下方向および法線方向に変位可能に
連結している。[Technical Background of the Invention and the Period; However, in general, a reactor containment vessel 2 is supported within a reactor building 1 of a boiling water nuclear power plant as shown in Figure 1, and this reactor containment vessel 2
The reactor pressure 6B33 is housed inside. The reactor pressure vessel 3 is held on a reactor pressure vessel pegistal, and a cylindrical reactor shielding wall 4 protects the reactor core. Specifically, as shown in FIG. 2, the reactor pressure vessel 3 is supported by the reactor shielding wall 4 via the reactor stabilizer 6, while the reactor shielding wall 5 is supported by the reactor containment vessel stabilizer 7. The nuclear reactor is also supported by the containment vessel 2 via the inner shear lug 8. The inner shear lug 8 connects the tip of the reactor containment vessel stabilizer 7 and the inner circumferential wall surface of the reactor containment vessel 2 so as to be displaceable in the vertical direction and the normal direction of the reactor container 2.
一方、原子炉格納容器２は原子炉建屋１のシールド、ｕ
ｌａに外側シアラグ９を介して支持される。On the other hand, the reactor containment vessel 2 is the shield of the reactor building 1,
la through an outer shear lug 9.
外側シアラグ９は第２図および渠３図に示すようにシー
ルド壁１ａの内周壁に基礎ボルト１０により固定される
フイメイルシアラグ９ａと原子炉格納容器２の外周壁に
取付けられるメイル７アラグ９ｂとを有し、フイメイル
シアラグ９ａの中央四部にメイルシアラグ９ｂがスライ
ド可能に係付しており、原子炉格納容器２をその上下方
向および法線方向に変位可能に支持している。外側シア
ラグ９は原子炉格納容器２の上部に周方向に被数個設置
される。As shown in FIGS. 2 and 3, the outer shear lug 9 includes a female shear lug 9a fixed to the inner peripheral wall of the shield wall 1a by foundation bolts 10, and a male shear lug 9b attached to the outer peripheral wall of the reactor containment vessel 2. The female shear lug 9b is slidably engaged with the four central parts of the female shear lug 9a, and supports the reactor containment vessel 2 so as to be movable in the vertical direction and the normal direction thereof. Several outer shear lugs 9 are installed in the upper part of the reactor containment vessel 2 in the circumferential direction.
しかして、原子炉格納容器２の内外に設置される内側シ
アラグ８および外側シアラグ９は原子炉格納容器２の熱
膨張を吸収するため、−にＦ力方向よび原子炉格納容器
２の半径方向にフリーに移動できる宿造となっている。Therefore, the inner shear lug 8 and the outer shear lug 9 installed inside and outside the reactor containment vessel 2 absorb thermal expansion of the reactor containment vessel 2, so that they are It is a dormitory where you can move freely.
しかも、原子炉建屋１のシールド壁１８ＫＩＩ！！］定
される外側フイメイルシアラグ９ａは個々のシアジグエ
レメントが各々独立して基礎ボルト１０等で設置される
ため、シールＦ′壁１ａへの埋込面積を大きくとれない
。このため、大地震時に、水平方向の地震力が原子炉建
屋１のシールド壁１ａに局部的にｌＦｆ候作用しｌこ用
台、大きな悪影響が及ぶ１工能性が存在する。Moreover, the shield wall of reactor building 1 is 18KII! ! ] In the outer female shear lug 9a, each of the individual shear jig elements is installed independently using foundation bolts 10, etc., so that a large area for embedding in the seal F' wall 1a cannot be secured. For this reason, in the event of a major earthquake, the horizontal seismic force acts locally on the shield wall 1a of the reactor building 1, resulting in a significant adverse effect.
ところで、大地震が発生した場合、原子炉圧力容器２や
原子炉遮蔽壁４からの水平方向の地震力（ｙＡ子炉格納
谷器２の接線方向の力）が、原子炉格納容器スタビライ
ザ７、Ｉ’ｌｉ則シアラグ８、原子炉格納容器２および
外１１１１１シアラグ９を胆次介して原子炉建屋ｌのシ
ールド壁１ａに伝達される。その際、水平方向の地質力
が局部的にシールド°壁に作用しても、この水平方向の
地震力に充分に耐えるだめには、シアラグ榴造、シール
ド壁１ａのコンクリート強度、個々のシアラグ９０間隔
を考慮する必要がある。しかし、シアラグ９を個々に独
立して設置した場合、シアラグ９の設置約数はおのずと
制限を受ける。このため、面・ｊ震構造上の問題があっ
た。By the way, when a major earthquake occurs, the horizontal seismic force from the reactor pressure vessel 2 and the reactor shielding wall 4 (force in the tangential direction of the yA reactor containment vessel 2) is applied to the reactor containment vessel stabilizer 7, It is transmitted to the shield wall 1a of the reactor building 1 via the I'li rule shear lug 8, the reactor containment vessel 2, and the outer 11111 shear lug 9. At that time, even if horizontal geological forces act locally on the shield wall, in order to sufficiently withstand this horizontal seismic force, the strength of the shear rug structure, the concrete strength of the shield wall 1a, the individual shear lag 90 Spacing needs to be considered. However, when the shear lugs 9 are individually installed, the number of shear lugs 9 to be installed is naturally limited. For this reason, there were problems with the surface/j earthquake structure.
本発明は上述した点を考慮し、原子炉建屋のシール）′
壁に局所的に作用する水平方向の地震力の影響を大幅に
緩オロさせ、原子炉格納容器の耐展性を向上式せた原子
炉格納容器の支持装置を提供することを目的とする。The present invention has been developed in consideration of the above-mentioned points.
It is an object of the present invention to provide a support device for a reactor containment vessel that significantly reduces the influence of horizontal seismic forces acting locally on walls and improves the expansion resistance of the reactor containment vessel.
上述した目的（ｉ−達成するために、本発明に係る原子
炉格納容器の支持装置は、原子炉建屋のシー）’）′壁
ＩＫ・フイメイ″′アラグとメイ″ア宅グからなるシア
ラグを介して原子炉格納容器を支坤させたものにおいて
、上記シールド壁の内周面呻帯状の支持構造物を周方向
に装着し、この支持構造物に前記フイメイルシアラグお
よびメイルシアラグの一方を設け、その他方を原子炉格
納容器の外周壁に設けたものである。In order to achieve the above-mentioned object (i-), the support device for the reactor containment vessel according to the present invention is designed to provide a support device for a reactor containment vessel in accordance with the present invention, which includes a shear lug consisting of a wall IK/female lug and a metal lug of a reactor building. A nuclear reactor containment vessel is supported through the shield wall, and a belt-shaped support structure is installed on the inner peripheral surface of the shield wall in the circumferential direction, and one of the female shear lug and the mail shear lug is provided on the support structure, The other side is installed on the outer peripheral wall of the reactor containment vessel.
以下、本発明の好ましい実施例について＋２ｉ’ｉ （
’１図面を参照して説明する。Hereinafter, preferred embodiments of the present invention will be described +2i'i (
'1 This will be explained with reference to the drawing.
第４図において、符号２０は沸１１．＃水型原子力発電
所の原子炉建屋を示し、この原子炉建屋２０内に原子炉
格納容器２１が収容される。原子炉格納容器２１内には
原子炉圧力容器２２が収納され、収納された原子炉圧力
容器２２は、原子炉圧力容器ペディスクル乙上に保持さ
れ、このペデイスタルＺ３上に形成された原子炉遮蔽壁
２４により炉心部が憶われる。In FIG. 4, reference numeral 20 indicates boiling point 11. #A reactor building of a water-type nuclear power plant is shown, and a reactor containment vessel 21 is housed within this reactor building 20. A reactor pressure vessel 22 is housed in the reactor containment vessel 21, and the housed reactor pressure vessel 22 is held on a reactor pressure vessel pedicle B, and a reactor shielding wall formed on this pedestal Z3. 24 memorizes the reactor core.
原子炉圧力容器２２は原子炉スタビライザ（図示せず）
を介して従前のものと同様、原子炉ａ藪壁罰に支持され
る。The reactor pressure vessel 22 is a reactor stabilizer (not shown)
As with the previous one, the reactor is supported by a bush wall punishment.
原子炉遮蔽壁Ｕは原子炉格納容器スタビライザがおよび
内側シアラグ２７ヲ介して原子炉格納容器２１に支持さ
れる。原子炉格納容器スタビライザ２６は全体として星
形形状をなし、その相部に１）旧１１リゾアラグ２７が
装着される。内側シアラグ２７は原子炉格納容器２１の
内周壁に固定されるフイメイルシアラグ（シアラグエレ
メント）２７ａと、原子炉格納容器スタビライザ２６の
先端に、フイメイルシアラグに対向して装着されるメイ
ルシアラグ（シアラグエレメント）２７ｂとを有し、こ
の内側シアラグｎにより原子炉格納容器２１とそのスタ
ビライザあとの上下方向および半径方向（法線方向）の
相対的変位を吸収するように支持している。原子炉格納
容器２１０法線方向の変位はフイメイルシアラグ２７ａ
とメイルシアラグ２７ｂとの法線方向ギャップδ（第６
図参照）により、上下方向の変位は両７アラグ２７ａ、
２７ｂのスライＰにより吸収される。一方、原子炉格納
容器２１の接線方向には、メイルシアラグ２７ｂがフイ
メイルシアラグ２７ａの凹部に密に保合していることに
より拘束される。両シアラグ２７ａ、２７ｂを原子炉格
納容器２１の接線方向に密に係合させる代りに遊嵌させ
、そのギャップにラバーベアリング（図示せず）を介装
して、接線方向ギャップ′ｆ：％’Ｆ消するようにして
もよい。ラバ−ベアリングはザム板と鋼板とを交互に順
次積層して一体化されること孔より構成される。The reactor shielding wall U is supported by the reactor containment vessel 21 via a reactor containment vessel stabilizer and an inner shear lug 27 . The reactor containment vessel stabilizer 26 has a star shape as a whole, and 1) the former 11 reso-arug 27 is attached to the phase thereof. The inner shear lug 27 includes a female shear lug (shear lug element) 27a fixed to the inner circumferential wall of the reactor containment vessel 21, and a female shear lug (shear lug element) mounted on the tip of the reactor containment vessel stabilizer 26 opposite to the female shear lug. This inner shear lug n supports the reactor containment vessel 21 and its stabilizer so as to absorb relative displacements in the vertical direction and the radial direction (normal direction). The displacement in the normal direction of the reactor containment vessel 210 is the female shear lug 27a.
Normal direction gap δ (sixth
(see figure), the vertical displacement is caused by both 7 lug 27a,
It is absorbed by Sly P of 27b. On the other hand, in the tangential direction of the reactor containment vessel 21, the male shear lug 27b is restrained by tightly fitting into the recessed portion of the female shear lug 27a. Instead of closely engaging both shear lugs 27a and 27b in the tangential direction of the reactor containment vessel 21, they are loosely fitted, and a rubber bearing (not shown) is inserted in the gap to create a tangential gap 'f:%'. F may be erased. Rubber bearings are made up of holes made by laminating alternately laminated rubber plates and steel plates.
原子炉格納容器２１は外側シアラグ（ト）を介して原子
炉建屋加のシールド壁２０ａに支持される。外側シアラ
グＩは内側シアラグ２７に対向して原子炉格納容器２１
の外側に、かつ周方向に適宜間隔をおいて複数個設置さ
れる。外側シアラグ刃は帯状の支持構造物３１に取付け
られたフイメイルシアラグ３０ａと、このシアラグに対
向して原子炉格納容器２１の外周壁に装着されたメイル
シアラグ３０ ｂとを有し、メイルシアラグ３０ｂはフ
イメイルシアラグ３０ａの上下方向に延びる中央四部に
係合している。The reactor containment vessel 21 is supported by a shield wall 20a of the reactor building via an outer shear lug (G). The outer shear lug I faces the inner shear lug 27 and is attached to the reactor containment vessel 21.
A plurality of them are installed at appropriate intervals in the circumferential direction on the outside of the The outer shear lug blade has a female shear lug 30a attached to a belt-shaped support structure 31, and a female shear lug 30b attached to the outer peripheral wall of the reactor containment vessel 21 opposite to this shear lug. It engages with four central portions of the lucia lug 30a extending in the vertical direction.
一方、フイメイルシアラグ３０ａを固設する支持構造物
３１は、プレート状の鋼板で帯状に形成され、原子炉建
屋加のシールド壁２０ ａに周方向にわたって埋設され
、基礎ボルト（またはアンカーボルト）３２により固定
される。この支持構造物３１にフイメイルシアラグ３０
ａが溶接等により一体あるいは取付ボルト等により一体
的に取付けられる。フイメイルシアラグ３０ ａを取付
ボルトにより一体的に取付けた場合には、フイメイルシ
アラグ３０ａの交換を容易に行なうことができる。On the other hand, the support structure 31 for fixing the female shear lug 30a is formed into a belt shape from a plate-like steel plate, is buried in the shield wall 20a of the reactor building in the circumferential direction, and is attached to foundation bolts (or anchor bolts) 32. Fixed by A female shear lug 30 is attached to this support structure 31.
(a) is integrally attached by welding or the like or by a mounting bolt or the like. When the female shear lug 30a is integrally attached with a mounting bolt, the female shear lug 30a can be easily replaced.
また、フイメイルシアラグ３０ａは上下方向に延びる中
央四部を有し、この中央凹部にメイルシアラグ３０ｂが
挿入され、係合される。外側シアラグ３０は原子炉格納
容器２１ｆ：その法線方向および上下方向に変位可能に
支持するもので、法線方向変位は両７アラグエレメント
３０ ａ ＋ ３０ ｂ間の法線方向ギャップにより吸
収され、上下方向変位は両シアラグエレメント３０ ａ
、 ３０ ｂ間相互のスライドにより吸収される。両
シアラグエレメント３０ ａ ＋ ３０ ｂは原子炉格
納容器２１の接線方向のギャップが小さいため、この接
線方向には拘束される。フイメイルシアラグ３０ａの凹
部にメイルシアラグ３０ｂを遊嵌させ、両７アラグエレ
メント３０ ａ ｅ ３０ ｂ間の接線方向ギャップを
大きくとった場合には、接線方向ギャップに上述したラ
バ−ベアリング（図示せず）を介装し、接線方向ギャッ
プを解消するようにしてもよい。Further, the female shear lug 30a has four central portions extending in the vertical direction, and the male shear lug 30b is inserted into and engaged with this central recess. The outer shear lug 30 supports the reactor containment vessel 21f so that it can be displaced in its normal direction and in the vertical direction, and displacement in the normal direction is absorbed by the normal direction gap between both seven shear lug elements 30a + 30b. , vertical displacement is determined by both shear lug elements 30 a
, 30 b are absorbed by mutual sliding. Since the gap in the tangential direction of the reactor containment vessel 21 is small, both shear lug elements 30 a + 30 b are restrained in this tangential direction. When the female shear lug 30b is loosely fitted into the recess of the female shear lug 30a and the tangential gap between both seven lug elements 30a and 30b is made large, the above-mentioned rubber bearing (not shown) is attached to the tangential gap. ) may be inserted to eliminate the tangential gap.
次に、本発明の作用について説明する。Next, the operation of the present invention will be explained.
原子炉の運転により、原子炉圧力容器ｎ等からの放熱作
用を受けて原子炉格納容器２Ｊが熱膨張する。この原子
炉格納容器２１の熱膨張による変位は外側シアラグ加お
よび内側シアラグ２７により吸収される。具体的には外
側シアラグ３０は原子炉建屋加のシールド壁２０ａに対
する原子炉格納容器２１０法線方向および上下方向の変
位を吸収するようになっており、内側７アラグ２７は原
子炉格納容器２１とそのスタビライザ２６との相対的な
上下方向および法線方向の変位を吸収し、原子炉の運転
が安全に行なわれるように配慮されている。When the nuclear reactor is operated, the reactor containment vessel 2J thermally expands due to heat radiation from the reactor pressure vessel n and the like. This displacement of the reactor containment vessel 21 due to thermal expansion is absorbed by the outer shear lug and the inner shear lug 27. Specifically, the outer shear lug 30 is adapted to absorb displacement in the normal direction and vertical direction of the reactor containment vessel 210 with respect to the shield wall 20a of the reactor building, and the inner seven shear lug 27 is adapted to absorb displacement in the normal direction and vertical direction of the reactor containment vessel 210 with respect to the shield wall 20a of the reactor building. It is designed to absorb vertical and normal displacements relative to the stabilizer 26 so that the reactor can operate safely.
また、大地６時には、原子炉圧力容器２２や原子炉遮蔽
壁Ｕからの水平方向の地震力は、原子炉格納容器スタビ
ライザ２６、内側シアラグ２７、原子炉格納容器２１お
よび外側シアラグ３０を介して原子炉建屋加のシールド
９：２０ ａに伝達される。その際、内側シアラグ２７
および外側シアラグ関は原子炉格納容器２１の接線方向
の変位を拘束するように取付けられているから、水平方
向の地震力は原子炉格納容器２１の接続方向の変位とな
ってシールド壁２ｆＪａに伝達される。Furthermore, at 6:00 a.m., the horizontal seismic force from the reactor pressure vessel 22 and reactor shielding wall U is transferred to the reactor containment vessel stabilizer 26, inner shear lug 27, reactor containment vessel 21, and outer shear lug 30. It is transmitted to the shield 9:20a in the furnace building. At that time, the inner shear lug 27
Since the outer shear lug is installed so as to restrain the displacement of the reactor containment vessel 21 in the tangential direction, the horizontal seismic force becomes a displacement of the reactor containment vessel 21 in the connection direction and is transmitted to the shield wall 2fJa. be done.
しかし、シールド壁２０ａには帯状の支持構造物３１が
全周にわたって埋設され、基礎ボルト３２等で固定され
ており、この支持構造物３２に外側シアラグ力のフイメ
イルシアラグ３０ａが一体あるいは一体的に取付けられ
ているから、特定の外側シアラグ３０を介して伝達され
る水平方向の地震力（原子炉格納容器２１の接線方向の
力）を支持構造物３１で局所的に（特に、直径方向に対
向する部分）で強く受ける。しかし、支持構造物３１は
シールド壁２０！ｌ全周にわたって埋設されているから
、支持構造物３１に伝達された地震力は分散され、シー
ルド壁２ｏａに作用する単位面積当りの地震力は小さく
なり、従来のように特定のクイメイルシア２グを固着し
たシールド壁２０ａ部分に地震力が集中的に作用するこ
とを未然にかつ確芙に解消することができる。However, a band-shaped support structure 31 is buried in the shield wall 20a over the entire circumference and fixed with foundation bolts 32, etc., and a female shear lug 30a of the outer shear lug force is integrally or integrally attached to this support structure 32. Because it is attached to (part) that is strongly affected. However, the supporting structure 31 is the shield wall 20! Because it is buried all around the perimeter, the seismic force transmitted to the support structure 31 is dispersed, and the seismic force per unit area acting on the shield wall 2 oa becomes smaller, making it possible to It is possible to prevent and reliably prevent seismic force from acting intensively on the fixed shield wall 20a portion.
したがって、原子炉遮蔽壁のシールド壁２０ａに伝達さ
れる地震力の恣影響を充分に緩和することができ、シー
ルド壁２０ａの耐真性を大幅に改善することができる。Therefore, the arbitrary influence of seismic force transmitted to the shield wall 20a of the reactor shielding wall can be sufficiently alleviated, and the truth resistance of the shield wall 20a can be significantly improved.
なお、本発明の一実施例の説明においては、帯状の支持
構造物を周設した例について説明したが、支持構造物を
周方向に予め数分割して複数の支持構造物エレメントを
構成し、各支持１・ｊ９造物エレメントをシールド壁の
内周壁面に設置した後、各支持構造物エレメントを互い
に接合し、帯状に一体化させてもよい。In addition, in the description of one embodiment of the present invention, an example in which a band-shaped support structure is provided around the circumference has been described, but it is also possible to divide the support structure into several parts in advance in the circumferential direction to configure a plurality of support structure elements, After installing each support structure element 1 and j9 on the inner peripheral wall surface of the shield wall, each support structure element may be joined to each other and integrated into a band shape.
また、本発明の一実施例の説明においては、ＭＡＲＫ−
Ｕ型原子炉の原子炉格納容器２１の上部に周方向に外側
および内側シアラグをそれぞれ対向させて複数設置した
例について説明したが、第７図に示すように原子炉遮蔽
壁のシールド壁２０ａの上部および下部に帯状の支持構
造物３１ａ、３１ｂを埋設して固定し、この支持構造物
に外側シアラグ３０を装着し、原子炉格納容器を支持さ
せてもよい。In addition, in the description of one embodiment of the present invention, MARK-
An example has been described in which a plurality of outer and inner shear lugs are installed facing each other in the circumferential direction in the upper part of the reactor containment vessel 21 of a U-type reactor. Band-shaped support structures 31a and 31b may be embedded and fixed in the upper and lower parts, and the outer shear lug 30 may be attached to these support structures to support the reactor containment vessel.
支持構造物３１．ａ、３１１）はシールド壁２０ａの中
１ｔ］部に埋設してもよい。さらに、第８図に示すＭＡ
ＲＫ−Ｉ型原子炉において、原子炉建屋２０Ａの７−ル
ド壁の上部に帯状の支持構造物３１ ｃを周方向に埋設
するようにしてもよい。Support structure 31. a, 311) may be buried in the middle part 1t of the shield wall 20a. Furthermore, MA shown in FIG.
In the RK-I type nuclear reactor, a band-shaped support structure 31c may be buried in the circumferential direction in the upper part of the seven-fold wall of the reactor building 20A.
さらに、本発明の一実施例においては、原子炉建屋のシ
ールド壁に埋設される帯状の支持構造物に外側シアラグ
のフイメイルシアラグを設けた例について説明したが、
フイメイルシアラグを設ける代りに、メイルシアラグを
支持構造物に設けるようにしてもよい。この場合には、
フイメイルンアラグは原子炉格納容器の外周壁にメイル
シアラグに対向して装着される。Furthermore, in one embodiment of the present invention, an example was described in which a female shear lug of the outer shear lug was provided in a band-shaped support structure embedded in the shield wall of a nuclear reactor building.
Instead of providing a female shear lug, a male shear lug may be provided on the support structure. In this case,
The female lug is mounted on the outer peripheral wall of the reactor containment vessel, facing the mail shear lug.
以上述べたように本発明に係る原子炉格納容器の支持装
置は原子炉建屋のシールド壁の内周面に帯状の支持構造
物を周方向に装着し、この支持構造物にフイメイルシア
ラグおよびメイルシアラグの一方を設け、その他方を原
子炉格納容器の外周壁に設けたから、大地震等により水
平方向の地震力が生じ、この地震力がシアラグを介して
原子炉建屋のシールド壁に作用するようになっても、帯
状の支持構造物を介してシールド壁に伝達されるため、
水平方向の地震力（原子炉格納容器接線方向の力）を支
持構造物で分散させることができ、シールド壁に局所的
に作用するのを押えることができる。したがって、原子
炉建屋のシールド壁に作用する水平方向の地震力を充分
に緩和させることができ、耐震性が向上する。As described above, the reactor containment vessel support device according to the present invention includes a belt-shaped support structure installed in the circumferential direction on the inner peripheral surface of the shield wall of the reactor building, and a female shear lug and a male shear lug attached to the support structure. Since one side was installed and the other side was installed on the outer peripheral wall of the reactor containment vessel, when a horizontal seismic force is generated due to a large earthquake, this seismic force acts on the shield wall of the reactor building via the shear lug. Even if the
Horizontal seismic force (force in the tangential direction of the reactor containment vessel) can be dispersed by the support structure and can be suppressed from acting locally on the shield wall. Therefore, the horizontal seismic force acting on the shield wall of the reactor building can be sufficiently alleviated, improving earthquake resistance.
また、原子炉建屋のシールド壁に帯状支持構造物全装着
したから、この帯状支持構造物に固設されるシアラグの
間隔を小さくシ、多数のシアラグを周方向に適宜間隔を
おいて取付けることができる。さらに、支持構造物の材
質強度を増加させた場合には、原子炉建屋のシールド壁
の耐震性をより一層大きく向上させることができる。シ
ールド壁の耐震性が向上することにより、原子炉格納容
器の耐震性が向上し、ひいては原子炉遮蔽壁や原子炉圧
力容器の耐震性の向上を図ることができる。In addition, since all the band-shaped support structures are attached to the shield wall of the reactor building, the intervals between the shear lugs fixed to the band-shaped support structures can be reduced, and a large number of shear lugs can be installed at appropriate intervals in the circumferential direction. can. Furthermore, when the material strength of the support structure is increased, the earthquake resistance of the shield wall of the reactor building can be further improved. By improving the seismic resistance of the shield wall, the seismic resistance of the reactor containment vessel is improved, and by extension, the seismic resistance of the reactor shielding wall and the reactor pressure vessel can be improved.
第１図は従来の原子炉格納容器の支持装置を組み込んだ
原子炉の平断面図、第２図は上記支持装置を示す側面図
、第３図は第２図のＡ部の拡大平面図、第４図は本発明
に係る原子炉格納容器の支持装置を組み込んだ沸騰水型
原子炉の断面図、第５図は第４図のＢ部の拡大側面図で
あって、原子炉格納容器の支持装置を示す側面図、８６
図は第５図のＶｌ −Ｖｌ線に沿う断面図、第７図は第
４図の■−■線に沿う一部省略平断面図、第８図は本発
明の第１変形例を示す原子戸建１風の断面図、第９図は
本発明の第２斐形例を示す原子炉建屋の断面図である。
加・・・原子炉り−ｕ屋、２ｏａ・・・シールド壁、２
１・・・原子炉格納容器、２２・・・原子炉圧力容器、
る・・・原子炉圧力容器ペデスタル、２４・・・原子炉
遮蔽壁、２６・・・原子炉４・６納容器スタビライザ、
２７・・・内側シアラグ、２７ａ、３０ａ・・・フイメ
イルゾアラブ（シアラグエレメント）、２７ｂ、３０ｂ
・・・メイルシアラグ（シアラグエレメント）、３０・
・・外側シアラグ、３］・・・支持構造１勿、３２・・
・基礎ボルト。
出願人代理人 波多野 久
第１図
第２図
第３図
第４図
第５図 第６図
０FIG. 1 is a plan sectional view of a nuclear reactor incorporating a conventional reactor containment vessel support device, FIG. 2 is a side view showing the support device, and FIG. 3 is an enlarged plan view of section A in FIG. FIG. 4 is a sectional view of a boiling water reactor incorporating the reactor containment vessel support device according to the present invention, and FIG. 5 is an enlarged side view of section B in FIG. Side view showing the support device, 86
The figure is a sectional view taken along the line Vl--Vl in FIG. 5, FIG. 7 is a partially omitted plan sectional view taken along the line ■-■ in FIG. 4, and FIG. 8 is an atomic diagram showing the first modification of the present invention. FIG. 9 is a sectional view of a nuclear reactor building showing a second example of the present invention. Ka... Nuclear reactor - u shop, 2oa... Shield wall, 2
1... Reactor containment vessel, 22... Reactor pressure vessel,
Reactor pressure vessel pedestal, 24... Reactor shielding wall, 26... Reactor 4/6 containment vessel stabilizer,
27...Inner shear lug, 27a, 30a...Female Zoarab (shear lug element), 27b, 30b
... Mail Shear Rag (Shear Rag Element), 30.
...Outer shear lug, 3]...Support structure 1 course, 32...
・Foundation bolts. Applicant's agent Hisashi Hatano Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 0
Claims (1)
とメイルシアラグからなるシアラグを介して原子炉格納
容器を支持させた原子炉格納容器の支持装置において、
上記ゾール「壁の内周面に帯状の支持構造物全周方向に
装着し、この支持構１に遺物に前記フイメイルシアラグ
およびメイルシアラグの一方を設け、その他方を原子炉
格納容器の外周壁に設けたこと全特徴とする原子炉格納
容器の支持装置。 ２、支持構造物は、プレート状の鋼材で形成され、原子
炉建屋の７−ルド壁の内周面に周方向全周にわたって埋
設され、基礎ボルト等で固定された特許請求の範囲第１
項に記載の原子炉格納容器の皮付装置１０ ３、支持構造物は復叔の支持４゛１４造物エレメントか
らなり、各支持構造物ニレメントラ原子炉建屋のシール
ド壁に周方向に設置し、この設置後裔支持構造物エレメ
ントを互いに接合して帯状に一体化させた特許請求の範
囲第１頃に記載の原子炉格納容器の支持装置。[Scope of Claims] 1. A support device for a reactor containment vessel in which the reactor containment vessel is supported by a seal h7Q of a reactor building via a shear lug consisting of a female shear lug and a male shear lug,
A belt-shaped support structure is attached to the inner peripheral surface of the wall in the entire circumferential direction, and one of the female shear lug and mail shear lug is attached to the relic on this support structure 1, and the other is attached to the outer peripheral wall of the reactor containment vessel. A support device for a reactor containment vessel having all the features provided. 2. The support structure is formed of a plate-shaped steel material, and is buried in the inner circumferential surface of the wall of the reactor building over the entire circumferential direction. , Claim 1 fixed with foundation bolts etc.
The reactor containment vessel skinning device 103 described in Section 3, the support structure is composed of Fushu's support 4 and 14 structural elements, and each support structure is installed in the circumferential direction on the shield wall of the reactor building. A support device for a nuclear reactor containment vessel according to claim 1, wherein the descendant support structure elements are joined to each other and integrated into a band shape after installation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58115247A JPS607388A (en) | 1983-06-28 | 1983-06-28 | Supporter for nuclear reactor containing vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58115247A JPS607388A (en) | 1983-06-28 | 1983-06-28 | Supporter for nuclear reactor containing vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS607388A true JPS607388A (en) | 1985-01-16 |
Family
ID=14657974
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58115247A Pending JPS607388A (en) | 1983-06-28 | 1983-06-28 | Supporter for nuclear reactor containing vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS607388A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1992000194A1 (en) * | 1990-05-22 | 1992-01-09 | Mcgourty Thomas K | Thermal printing system with encoded sheet set |
| JPH07280974A (en) * | 1992-06-24 | 1995-10-27 | Westinghouse Electric Corp <We> | Supporter of pressurizer tank |
| CN103231169A (en) * | 2013-04-19 | 2013-08-07 | 上海第一机床厂有限公司 | Laser welding method for reactor core wrapping tube |
| US10349993B2 (en) | 2008-08-13 | 2019-07-16 | Smed-Ta/Td, Llc | Drug delivery implants |
| US10842645B2 (en) | 2008-08-13 | 2020-11-24 | Smed-Ta/Td, Llc | Orthopaedic implant with porous structural member |
-
1983
- 1983-06-28 JP JP58115247A patent/JPS607388A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1992000194A1 (en) * | 1990-05-22 | 1992-01-09 | Mcgourty Thomas K | Thermal printing system with encoded sheet set |
| JPH07280974A (en) * | 1992-06-24 | 1995-10-27 | Westinghouse Electric Corp <We> | Supporter of pressurizer tank |
| US10349993B2 (en) | 2008-08-13 | 2019-07-16 | Smed-Ta/Td, Llc | Drug delivery implants |
| US10357298B2 (en) | 2008-08-13 | 2019-07-23 | Smed-Ta/Td, Llc | Drug delivery implants |
| US10842645B2 (en) | 2008-08-13 | 2020-11-24 | Smed-Ta/Td, Llc | Orthopaedic implant with porous structural member |
| CN103231169A (en) * | 2013-04-19 | 2013-08-07 | 上海第一机床厂有限公司 | Laser welding method for reactor core wrapping tube |
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