JPS6338111B2 - - Google Patents

Info

Publication number
JPS6338111B2
JPS6338111B2 JP56101620A JP10162081A JPS6338111B2 JP S6338111 B2 JPS6338111 B2 JP S6338111B2 JP 56101620 A JP56101620 A JP 56101620A JP 10162081 A JP10162081 A JP 10162081A JP S6338111 B2 JPS6338111 B2 JP S6338111B2
Authority
JP
Japan
Prior art keywords
containment vessel
main body
sliding
mounting bracket
radial direction
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
JP56101620A
Other languages
Japanese (ja)
Other versions
JPS582781A (en
Inventor
Yutaka Muramatsu
Masanao Sasaki
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
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 by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP56101620A priority Critical patent/JPS582781A/en
Publication of JPS582781A publication Critical patent/JPS582781A/en
Publication of JPS6338111B2 publication Critical patent/JPS6338111B2/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
    • Y02E30/30Nuclear fission reactors

Description

【発明の詳細な説明】 本発明は原子炉圧力容器を収容する原子炉格納
容器に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor containment vessel that houses a nuclear reactor pressure vessel.

従来、原子炉格納容器たとえばオーバアンダ形
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、1は格納容器本体
であつ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内はダイヤフラムフロア3によつて上下
に区画され、上部はドライウエル4に、下部はサ
プレツシヨンチヤンバ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6が立設
されており、このペデスタル6上には原子炉圧力
容器7が据付けられている。そして、この原子炉
圧力容器を囲んで熱遮蔽壁8が設けられている。
そして、この熱遮蔽壁8の上端は支持部材9…を
介して格納容器本体1に支持されており、地震等
の際にこの熱遮蔽壁8に加わる水平方向の荷重を
支持するように構成されている。ところで、従来
これらの支持部材9…は熱遮蔽壁8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、取外しをなすホイストクレーンの走行用の
レール11は上記支持部材9…の下方に設けなけ
ればならなかつた。ところで、このようなレール
11から主蒸気隔離弁10等の機器までの距離は
これら機器の吊り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ある程度の距離を必要
とする。したがつて上記の如くレール11を支持
部材9…の下方に配置するとその分だけ格納容器
本体1が高くなり、耐震設計上不利であつた。ま
た、この支持部材9…と格納容器本体1との取付
部においては、第2図に示す如く格納容器本体1
に比較的大形の支持金具12を埋め込み、支持部
材9…を介して作用する大きな水平方向の荷重を
この格納容器本体1に分散して支持させる必要が
ある。また、このようなコンクリート製の原子炉
格納容器では上蓋13を取付けるためのフランジ
部材14を別に形成し、これを格納容器本体1に
取付けなければならない。ところで、このような
フランジ部材14はこの原子炉格納容器の内圧が
上昇した場合に大きな上向の荷重を受ける。この
ため、格納容器本体1の上部に大形の取付金具1
5を埋め込み、この取付金具15に上記フランジ
部材14を取付ける必要がある。しかし、このよ
うな大形の取付金具15や支持金具12を埋め込
むとその周囲の配筋構造等が複雑となるので、格
納容器本体1に埋め込まれる大形の金具の数は少
ない方がよい。
Conventionally, nuclear reactor containment vessels, such as over-under type reactor containment vessels, have been constructed as shown in FIGS. 1 and 2. That is, 1 is the main body of the containment vessel, which is made of reinforced concrete, for example;
It 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. The inside of the containment vessel main body 1 is divided into upper and lower sections by a diaphragm floor 3, with a dry well 4 formed in the upper part and a suppression chamber 5 formed in the lower part. A pedestal 6 is erected within the containment vessel body 1, and a reactor pressure vessel 7 is installed on the pedestal 6. A heat shielding wall 8 is provided surrounding the reactor pressure vessel.
The upper end of this heat shield wall 8 is supported by the containment vessel main body 1 via support members 9, and is configured to support the horizontal load applied to this heat shield wall 8 in the event of an earthquake or the like. ing. By the way, these support members 9 have conventionally been provided horizontally between the outer periphery of the upper end of the heat shielding wall 8 and the inner peripheral surface of the containment vessel main body 1. For this reason, the rails 11 for the traveling of the hoist crane, which are used to attach and detach the main steam isolation valves 10 and the like, had to be provided below the support members 9 . . . . By the way, a certain distance is required from the rail 11 to equipment such as the main steam isolation valve 10 in order to lift and work on these equipment, and also to install an air conditioning duct. Therefore, when the rail 11 is disposed below the support members 9 as described above, the containment vessel main body 1 becomes higher by that much, which is disadvantageous in terms of seismic design. In addition, at the attachment part between the supporting members 9 and the containment vessel main body 1, as shown in FIG.
It is necessary to embed a relatively large supporting metal fitting 12 in the container body 1 to distribute and support the large horizontal load acting through the supporting members 9 to the main body 1 of the containment vessel. Further, in such a concrete reactor containment vessel, a flange member 14 for attaching the upper cover 13 must be separately formed and attached to the containment vessel main body 1. By the way, such a flange member 14 receives a large upward load when the internal pressure of the reactor containment vessel increases. For this reason, a large mounting bracket 1 is installed on the top of the containment vessel body 1.
5, and the flange member 14 needs to be attached to this mounting fitting 15. However, embedding such large fittings 15 and support fittings 12 complicates the reinforcement structure around them, so it is better to have fewer large fittings embedded in the containment vessel body 1.

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
とができる原子炉格納容器を得ることにある。
The present invention has been made based on the above circumstances, and its purpose is to provide a reactor containment vessel that can effectively utilize the internal space, reduce its height, and improve earthquake resistance. It is in.

以下本発明を第3図ないし第6図に示す一実施
例にしたがつて説明する。図中101は格納容器
本体であつて、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、この格納容器本体101の内面には
鋼板からなるライナー102が密着して張られて
おり、このライナー102によつて気密性が与え
られている。そして、この格納容器本体101内
はダイヤフロア103によつて上下に区画され、
上部はドライウエル104に、下部はサプレツシ
ヨンチヤンバ105に形成されている。また、こ
の格納容器本体101内の中央部にはペデスタル
106が立設されており、このペデスタル106
上には原子炉圧力容器107が据付けられてい
る。また、このペデスタル106上には上記原子
炉圧力容器107を囲んで円筒状の熱遮蔽壁10
8が立設されている。そして、この原子炉圧力容
器107と熱遮蔽壁108とは連結部材109…
を介して連結されている。また、110は主蒸気
配管であつてその途中には主蒸気隔離弁111が
設けられている。また、この格納容器本体101
の上部開口には鋼製のフランジ部材112が設け
られており、このフランジ部材112には上蓋1
13が着脱自在に取付けられている。そして、こ
の格納容器本体101の上端開口の周囲には環状
の取付金具114が埋め込まれている。そして上
記フランジ部材112はこの取付金具114に取
付けられ、内圧が上昇した場合に上記フランジ部
材112に作用する上向の荷重はこの取付金具1
14を介して格納容器本体101に伝えられるよ
うに構成されている。そして、前記熱遮蔽壁10
8の上端面からは上方に向けて複数の支持部材1
15…が突設され、これらの支持部材115…の
上端は格納容器本体101の上壁部たとえば上記
取付金具114に取付けられている。なお、11
6…はこれら支持部材115…を熱遮蔽壁108
の上端に取付けるための取付金具であつて、熱遮
蔽壁108の上端部に埋め込まれている。そし
て、これら支持部材115…は第5図に示す如く
周方向に連続したトラス状に組まれており、周方
向の荷重に対して耐えるように構成されている。
したがつて、上記熱遮蔽壁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
置にある支持部材115…によつて受けられ、格
納容器本体101に伝えられるように構成されて
いる。また、上記支持部材115…の上端部は摺
動機構117…を介して前記取付金具114に取
付けられている。これら摺動機構117…は受部
材117a…と摺動子117b…とから構成され
ており、受部材117a…には摺動溝117c…
が形成されている。そして、これら受部材117
a…はその摺動子117b…がいずれも径方向を
向くように取付けられている。そして、上記摺動
子117b…はそれぞれ上記受部材117a…の
摺動溝117c…内に摺動自在に嵌合しており、
上記支持部材115…の上端部はこれら摺動子1
17bに取付けらている。したがつてこれら摺動
機構117…は支持部材115…に作用する周方
向の荷重は格納容器本体101に伝えるが、径方
向の荷重は格納容器本体101に伝えないように
構成されている。したがつて熱遮蔽壁108の熱
変形はこれら摺動子117b…が径方向に摺動す
ることによつて逃がされ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
環状のレール118が設けられており、主蒸気隔
離弁111等の機器の取付、取外し等に使用する
ホイストクレーン(図示せず)はこのレール11
8に沿つて走行するように構成されている。
The present invention will be explained below with reference to an embodiment shown in FIGS. 3 to 6. In the figure, 101 is the main body of the containment vessel, which is strongly formed of reinforced concrete and has pressure resistance and radiation shielding ability. A liner 102 made of a steel plate is tightly attached to the inner surface of the containment vessel main body 101, and the liner 102 provides airtightness. The inside of this containment vessel main body 101 is divided into upper and lower parts by a diamond floor 103,
The upper part is formed into a dry well 104, and the lower part is formed into a suppression chamber 105. In addition, a pedestal 106 is erected at the center of the containment vessel main body 101, and this pedestal 106
A reactor pressure vessel 107 is installed above. Further, on this pedestal 106, a cylindrical heat shielding wall 10 is provided surrounding the reactor pressure vessel 107.
8 are erected. The reactor pressure vessel 107 and the heat shielding wall 108 are connected to a connecting member 109...
are connected via. Further, 110 is a main steam pipe, and a main steam isolation valve 111 is provided in the middle thereof. In addition, this containment vessel main body 101
A steel flange member 112 is provided at the upper opening of the upper lid 1.
13 is detachably attached. An annular mounting fitting 114 is embedded around the upper end opening of the containment vessel main body 101. The flange member 112 is attached to this mounting bracket 114, and when the internal pressure increases, the upward load acting on the flange member 112 is absorbed by the mounting bracket 114.
14 to the containment vessel main body 101. And the heat shield wall 10
A plurality of support members 1 are arranged upwardly from the upper end surface of 8.
15 are provided in a protruding manner, and the upper ends of these supporting members 115 are attached to the upper wall portion of the containment vessel main body 101, for example, to the above-mentioned mounting bracket 114. In addition, 11
6... connects these support members 115... to the heat shielding wall 108.
It is a mounting bracket for attaching to the upper end, and is embedded in the upper end of the heat shield wall 108. As shown in FIG. 5, these support members 115 are assembled in a continuous truss shape in the circumferential direction, and are configured to withstand loads in the circumferential direction.
Therefore, the horizontal load acting on the heat shielding wall 108 is received by the support members 115 located in a direction perpendicular to the direction of the load, and is transmitted to the containment vessel body 101. ing. Further, the upper end portions of the supporting members 115 are attached to the mounting fittings 114 via sliding mechanisms 117 . These sliding mechanisms 117 ... are composed of receiving members 117a... and sliders 117b..., and the receiving members 117a... have sliding grooves 117c...
is formed. And these receiving members 117
a... are attached so that their sliders 117b... all face in the radial direction. The sliders 117b are each slidably fitted into the sliding grooves 117c of the receiving members 117a,
The upper end of the support member 115...
It is attached to 17b. Therefore, these sliding mechanisms 117 are configured to transmit the circumferential load acting on the support members 115 to the containment vessel body 101, but not to transmit the radial load to the containment vessel body 101. Therefore, the structure is such that thermal deformation of the heat shielding wall 108 is relieved by sliding these sliders 117b in the radial direction. Further, an annular rail 118 is provided at the upper part of the containment vessel main body 101, and a hoist crane (not shown) used for installing and removing equipment such as the main steam isolation valve 111 is attached to this rail 118.
It is configured to run along 8.

以上の如く構成された本発明の一実施例は、地
震によつて原子炉圧力容器107や熱遮蔽壁10
8に作用する水平方向の荷重はこの荷重の方向と
直交する位置にある支持部材115…によつて格
納容器本体101に伝えられ、支持される。そし
てこのものは支持部材115…が熱遮蔽壁108
の上端から上方に向けて配置されているので、こ
の熱遮蔽壁108の外周面と格納容器本体101
の内面との間には邪魔な部材が存在しない。よつ
て前記レール118は格納容器本体101内の最
上部に設けることができ、その分だけ格納容器本
体101の高さを低くでき、この格納容器本体1
01の耐震性が向上する。また、このように支持
部材115…を上方に突設したので、これら支持
部材115…の上端部は格納容器本体101の上
端開口の周囲に位置する。よつてこれら支持部材
115…の荷重を受ける取付金具114はフラン
ジ部材112の荷重を受ける取付金具と共用で
き、このような取付金具114が1個ですむので
格納容器本体101の構造が簡単となり、建築コ
ストを低減することができる。
In one embodiment of the present invention configured as described above, the reactor pressure vessel 107 and the heat shield wall 10 can be damaged by an earthquake.
8 is transmitted to and supported by the containment vessel main body 101 by support members 115 located perpendicular to the direction of this load. And in this case, the support member 115... is the heat shield wall 108
Since it is arranged upward from the upper end, the outer peripheral surface of this heat shielding wall 108 and the containment vessel body 101
There are no obstructive members between the inner surface and the inner surface. Therefore, the rail 118 can be provided at the top of the containment vessel main body 101, and the height of the containment vessel main body 101 can be reduced accordingly.
The earthquake resistance of 01 is improved. Further, since the support members 115 are provided to protrude upward in this way, the upper ends of these support members 115 are located around the upper end opening of the containment vessel main body 101. Therefore, the mounting fittings 114 that receive the loads of these supporting members 115 can be used in common with the mounting fittings that receive the loads of the flange members 112, and since only one such mounting fitting 114 is required, the structure of the containment vessel main body 101 is simplified, Construction costs can be reduced.

以上詳述したように本発明による原子炉格納容
器は、コンクリート製の格納容器本体と、この格
納容器本体内に収容された原子炉圧力容器を囲ん
で設けられた円筒状の熱遮蔽壁と、上記格納容器
本体の上壁部内に埋設され格納容器本体の上蓋を
取付けるフランジ部を支持する環状取付金具と、
上記熱遮蔽壁の上端と上記環状取付金具とを連結
し周方向に連続してトラス状に組まれ支持部材
と、上記環状取付金具及び上記支持部材のいずれ
か一方に形成され半径方向に延長された摺動突部
を備えた摺動子と、上記環状取付金具及び上記支
持部材の他方に形成され上記摺動子の摺動突部に
係合し半径方向に延長された摺動溝を有し摺動子
との間で半径方向への相対的摺動を許容するとと
もに周方向への摺動を規制する受部材とを具備し
たことを特徴とするものである。したがつて地震
等により熱遮蔽壁に作用する水平方向の荷重はこ
の荷重の作用方向と直交する位置の支持部材を介
して格納容器本体に受けられるので、従来と同様
にこの熱遮蔽壁の水平方向の荷重を支持すること
ができる。そして、これら支持部材は熱遮蔽壁の
上端から上方に向けて配置されるので、熱遮蔽壁
と格納容器本体との間には邪魔な部材が存在しな
い。よつてホイストクレーン走行用のレールを格
納容器内の最上部に設ける等、この熱遮蔽壁と格
納容器本体との間の空間を有効に利用でき、その
分だけ格納容器本体の高さを低くすることがで
き、耐震性が向上する。また本発明にあつては、
格納容器の上蓋を取付けるフランジ部を支持する
ために格納容器本体の上壁部に埋設された取付金
具を支持部材の支持用としても共用することがで
きるので、構成の簡略化を図ることができる。
又、半径方向への熱膨張については少なくとも摺
動子と受部材との摺動範囲内では必要な機能を維
持した状態で吸収可能であり、高い熱膨張吸収能
力を提供することができる。さらに本発明の場合
には支持部材が熱遮蔽壁と格納容器本体の上壁と
の比較的短い距離の間に設置されているので、地
震時に作用するモーメントも小さなものとなり、
その健全性の維持を効果的に図ることができると
ともに、支持部材及びそれに附随する各種構造物
も小型のもので事足り、物量の低減を図ることが
できる。
As detailed above, the reactor containment vessel according to the present invention includes a containment vessel main body made of concrete, a cylindrical heat shielding wall provided surrounding the reactor pressure vessel housed in the containment vessel main body, an annular mounting bracket that is embedded in the upper wall of the containment vessel body and supports a flange portion to which the upper cover of the containment vessel body is attached;
a support member that connects the upper end of the heat shielding wall and the annular mounting bracket and is assembled in a truss shape continuously in the circumferential direction, and a supporting member that is formed on either the annular mounting bracket and the support member and extends in the radial direction a slider having a sliding protrusion, and a sliding groove formed on the other of the annular mounting bracket and the support member and engaging with the sliding protrusion of the slider and extending in the radial direction. It is characterized by comprising a receiving member that allows relative sliding in the radial direction with the slider and restricts sliding in the circumferential direction. Therefore, the horizontal load that acts on the heat shield wall due to earthquakes, etc. is received by the containment vessel main body via the support member at a position perpendicular to the direction of action of this load. It can support loads in different directions. Since these support members are arranged upward from the upper end of the heat shield wall, there are no obstructive members between the heat shield wall and the containment vessel main body. Therefore, the space between this heat shielding wall and the containment vessel body can be used effectively by providing rails for hoist crane travel at the top of the containment vessel, and the height of the containment vessel body can be reduced by that amount. This improves earthquake resistance. Furthermore, in the present invention,
The mounting bracket embedded in the upper wall of the containment vessel body to support the flange to which the upper lid of the containment vessel is attached can also be used to support the support member, so the configuration can be simplified. .
Furthermore, thermal expansion in the radial direction can be absorbed while maintaining necessary functions at least within the sliding range between the slider and the receiving member, and a high thermal expansion absorption capacity can be provided. Furthermore, in the case of the present invention, since the support member is installed between a relatively short distance between the heat shielding wall and the upper wall of the containment vessel main body, the moment acting during an earthquake is also small.
The integrity of the structure can be effectively maintained, and the support member and various structures accompanying it can also be small-sized, thereby reducing the amount of material needed.

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

第1図および第2図は従来例を示し、第1図は
全体の縦断面図、第2図は一部を拡大して示す縦
断面図である。第3図ないし第6図は本発明の一
実施例を示し、第3図は全体の縦断面図、第4図
は一部を拡大して示す縦断面図、第5図は第4図
の―矢視図、第6図は第5図の―矢視図
である。 101…格納容器本体、102…ライナー、1
07…原子炉圧力容器、108…熱遮蔽壁、11
2…フランジ部材、113…上蓋、114…取付
金具、115…支持部材、117…摺動機構。
1 and 2 show a conventional example, with FIG. 1 being a longitudinal sectional view of the whole, and FIG. 2 being a longitudinal sectional view showing a part enlarged. 3 to 6 show one embodiment of the present invention, in which FIG. 3 is an overall vertical sectional view, FIG. 4 is a vertical sectional view showing a partially enlarged view, and FIG. 6 is a view of FIG. 5 in the direction of the arrow. 101... Containment vessel main body, 102... Liner, 1
07...Reactor pressure vessel, 108...Heat shielding wall, 11
2...Flange member, 113...Top lid, 114...Mounting metal fittings, 115...Supporting member, 117 ...Sliding mechanism.

Claims (1)

【特許請求の範囲】[Claims] 1 コンクリート製の格納容器本体と、この格納
容器本体内に収容された原子炉圧力容器を囲んで
設けられた円筒状の熱遮蔽壁と、上記格納容器本
体の上壁部内に埋設され格納容器本体の上蓋を取
付けるフランジ部を支持する環状取付金具と、上
記熱遮蔽壁の上端と上記環状取付金具とを連結し
周方向に連続してトラス状に組まれた支持部材
と、上記環状取付金具及び上記支持部材のいずれ
か一方に形成され半径方向に延長された摺動突部
を備えた摺動子と、上記環状取付金具及び上記支
持部材の他方に形成され上記摺動子の摺動突部に
係合し半径方向に延長された摺動溝を有し摺動子
との間で半径方向への相対的摺動を許容するとと
もに周方向への摺動を規制する受部材とを具備し
たことを特徴とする原子炉格納容器。
1. A containment vessel body made of concrete, a cylindrical heat shielding wall provided surrounding the reactor pressure vessel housed within the containment vessel body, and a containment vessel body buried within the upper wall of the containment vessel body. an annular mounting bracket that supports the flange portion to which the top cover is attached; a support member that connects the upper end of the heat shielding wall and the annular mounting bracket and is continuously assembled in a truss shape in the circumferential direction; A slider having a sliding protrusion formed on one of the supporting members and extending in the radial direction, and a sliding protrusion of the slider formed on the other of the annular mounting bracket and the supporting member. and a receiving member having a sliding groove extending in the radial direction and allowing relative sliding in the radial direction with the slider and restricting sliding in the circumferential direction. A nuclear reactor containment vessel characterized by:
JP56101620A 1981-06-30 1981-06-30 Reactor container Granted JPS582781A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56101620A JPS582781A (en) 1981-06-30 1981-06-30 Reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56101620A JPS582781A (en) 1981-06-30 1981-06-30 Reactor container

Publications (2)

Publication Number Publication Date
JPS582781A JPS582781A (en) 1983-01-08
JPS6338111B2 true JPS6338111B2 (en) 1988-07-28

Family

ID=14305438

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56101620A Granted JPS582781A (en) 1981-06-30 1981-06-30 Reactor container

Country Status (1)

Country Link
JP (1) JPS582781A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02226107A (en) * 1989-02-27 1990-09-07 Fujikura Ltd Loose tube type coated optical fiber

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57125395A (en) * 1981-01-27 1982-08-04 Ishikawajima Harima Heavy Ind Earthquake-proof device for nuclear reactor container

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57125395A (en) * 1981-01-27 1982-08-04 Ishikawajima Harima Heavy Ind Earthquake-proof device for nuclear reactor container

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02226107A (en) * 1989-02-27 1990-09-07 Fujikura Ltd Loose tube type coated optical fiber

Also Published As

Publication number Publication date
JPS582781A (en) 1983-01-08

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