JPS582781A - Reactor container - Google Patents

Reactor container

Info

Publication number
JPS582781A
JPS582781A JP56101620A JP10162081A JPS582781A JP S582781 A JPS582781 A JP S582781A JP 56101620 A JP56101620 A JP 56101620A JP 10162081 A JP10162081 A JP 10162081A JP S582781 A JPS582781 A JP S582781A
Authority
JP
Japan
Prior art keywords
containment vessel
main body
heat shielding
wall
reactor
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
Application number
JP56101620A
Other languages
Japanese (ja)
Other versions
JPS6338111B2 (en
Inventor
豊 村松
佐々木 昌直
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

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パアンメ形の原子炉
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の内面に社ライ
ナー2が張設され、気密性を与えている。そして、との
格納容器本体1内はダイヤフラムフロア3によって上下
に区画され、上部はドライウェル4に、下部はサグレッ
シ曹ンチャンパ6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1が据付ゆられている
。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ms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1
シ、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。この丸め、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1ノは上記支
持部材9・・・の下方に設けなければならなかった。と
ころで、このよう表レール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9上けおよび作業の
丸め、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。し九がっ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が高くなシ、耐震設計上不利であった。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。を九、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
IKgIL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社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。この丸め、格納
容器本体1の上部に大形の取付金具15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を埋め込むとその胸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, a nuclear reactor containment vessel, such as an opaque type reactor containment vessel, has been constructed as shown in FIGS. 1 and 2. That is, 1 is the main body of the containment vessel, which 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. 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 sagress chamber chamber 6 formed in the lower part. A pedestal 6 is erected within the containment vessel body 1, and the reactor pressure vessel 1 is installed and swung on the pedestal 6. A heat shielding wall 8 is provided surrounding the reactor pressure vessel. The upper end of this heat shield ms is supported by the containment vessel main body 1 via support members 9...
The heat shielding wall 8 is configured to support the horizontal load applied to the heat shielding wall 8 in the event of an earthquake or the like. By the way, these support members 9 have conventionally been provided in a horizontal direction between the outer periphery of the upper end of the heat shielding wall 8 and the inner peripheral surface of the containment vessel body 1. The rail 1 for running the hoist crane, which is used for rounding, attaching and removing the main steam isolation valve 10, etc., had to be provided below the support member 9. By the way, a certain distance is required from the front rail 11 to equipment such as the main steam isolation valve 10 for hoisting these equipment, rounding the work, and installing air conditioning ducts. However, if the rails 11 were disposed below the support members 9 as described above, the containment vessel body 1 would be correspondingly higher, which was disadvantageous in terms of earthquake-resistant design. In addition, at the attachment part between the support members 9... and the containment vessel main body 1, a relatively large support fitting 12 is embedded in the containment vessel main body 1 as shown in FIG. It is necessary to disperse and support the large horizontal load acting through the containment vessel main body 1. (9) In such a concrete reactor containment vessel, a flange member 14 for attaching the upper cover 13 must be formed separately, and this must be attached to the containment vessel main body IKgIL. By the way, 14 such flange members are subjected to a large upward load when the internal pressure of the reactor containment vessel increases. For this rounding, it is necessary to embed a large fitting 15 in the upper part of the containment vessel body 1 and attach the flange member 14 to this fitting 15. However, embedding such large fittings 15 and support fittings 12 complicates the reinforcement structure of the chest girth, so it is better to have fewer large fittings embedded in the containment vessel main 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
がって説明する0図中101は格納容器本体であって、
鉄筋コンクリートで強固に形成され、耐圧性および放射
線の纏蔽能力を有している。そして、この格納容器本体
101の内面に社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によって気密性
が与えられている。そして、この格納容器本体101内
はダイヤフラムフロア103によりて上下に区画され、
上部はドライフェル104に% 下部ハサグレクシ冒ン
チャンノ骨1o5に形成されている。また、。この格納
容器本体101内の中央部KFiイデスタル1’0−が
立設されておシ、この−4′yhスタル106上にはj
ll炉圧力容器101が裾付けられている。また、この
(デスタル106上には上記原子炉圧力容器101を囲
んで円筒状の熱遮蔽壁108が立設されている。そして
、この原子炉圧力容器101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、11
oは主蒸気配管であってその途中には主蒸気隔離弁11
1が設けられている。また、この格納容器本体1’0’
lの上部開口には鋼製のフランジ部材112が設けられ
ておシ、このフランジ部材112には上蓋113が着脱
自在に取付けられている。
Hereinafter, the present invention will be explained according to an embodiment shown in FIGS. 3 to 6. In FIG. 0, 101 is a containment vessel main body,
It is made of reinforced concrete and has pressure resistance and radiation shielding ability. A liner 102 made of steel plate or the like 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 sections by a diaphragm floor 103.
The upper part is formed by Dryfell 104% and the lower part is formed by 1o5. Also,. A KFi idetal 1'0- is erected in the central part of the containment vessel main body 101, and on this -4'yh stall 106 is a j
ll furnace pressure vessel 101 is hemmed. Further, a cylindrical heat shielding wall 108 is erected on this (destal 106) surrounding the reactor pressure vessel 101.The reactor pressure vessel 101 and the heat shielding wall 108 are connected to each other by a connecting member 109. It is connected via... Also, 11
o is the main steam pipe, and there is a main steam isolation valve 11 in the middle of the pipe.
1 is provided. In addition, this containment vessel main body 1'0'
A flange member 112 made of steel is provided at the upper opening of 1, and an upper lid 113 is removably attached to this flange member 112.

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に取付部られ
、内圧が上昇した場合に上記フランジ部材111に作用
する上向の荷重はこの取付金具77(を介して格納容器
本体101に伝えら糺るように構成されている。
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 the mounting bracket 114, and when the internal pressure increases, the upward load acting on the flange member 111 is transmitted to the containment vessel body 101 via the mounting bracket 77. It is configured as follows.

そして、前記熱遮蔽−108の上端面からは上方に向け
て複数の支持部材115・・・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の土壁
部たとえば上記取付金具114に象付けられている。な
お、116・・・はこれら支持部材115・・・を熱遮
蔽壁1011の上端に取付けるための取付金具であって
、熱遮蔽壁10mの上端部に埋め込まれている。そして
、これら支持部材115・・・は繍5図に示す如く周方
向に連続し九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。したがって、上紀
熱迩蔽壁108に作用する水平方向の荷重紘その荷重の
方向と直交する方向の位置にある支持部材115・・・
によって受けられ、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・・・
の上端部紘摺動機構11F・・・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II・1a・・・と摺動子111b・・・と
から構成されておシ、受部材111a・・・には摺動@
 117 c・・・が形成されている。そして、これら
受部材111a・・・はその摺動子117b・・・かい
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117
m・・・の摺動溝117・・・・内に摺動自在に嵌合し
ており、上記支持部材115・・・O上端部はこれら摺
動子117b・・・Klj付けられている。したがって
これら摺動機構111・・・は支持部材115・・・K
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。し九がって熱遮蔽壁1011の熱変形
はこれら摺動子117b・・・が径方向に摺動すること
によって逃がされるように構成されている。
A plurality of support members 115 are provided upwardly from the upper end surface of the heat shield 108, and the upper ends of these support members 115 are connected to the earth wall of the containment vessel main body 101, for example, as described above. It is embossed on the mounting bracket 114. Incidentally, reference numeral 116 is a mounting metal fitting for attaching these supporting members 115 to the upper end of the heat shielding wall 1011, and is embedded in the upper end of the heat shielding wall 10m. As shown in Fig. 5, these support members 115 are arranged in a nine-truss shape continuous in the circumferential direction, and are configured to withstand loads in the circumferential direction. Therefore, the horizontal load acting on the upper heat shielding wall 108 is the support member 115 located at a position perpendicular to the direction of the load.
It is configured to be received by and transmitted to the containment vessel main body 101. In addition, the support member 115...
It is attached to the mounting bracket 114 via the upper end sliding mechanism 11F... These sliding mechanisms 117...
・ is composed of a receiving member II 1a... and a slider 111b..., and the receiving member 111a...
117c... is formed. These receiving members 111a... are attached so that their sliders 117b... all face in the radial direction. and,
The slider 117b... is the receiving member 117, respectively.
m... are slidably fitted into the sliding grooves 117..., and the upper ends of the supporting members 115...O are attached to these sliders 117b...Klj. Therefore, these sliding mechanisms 111... are supported by supporting members 115...K.
The applied circumferential load is transmitted to the containment vessel body 101, but the radial load is not transmitted to the containment vessel body 101. Accordingly, the structure is such that thermal deformation of the heat shielding wall 1011 is relieved by sliding these sliders 117b in the radial direction.

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
吃ず)はこのレール118に沿って走行するように構成
されている・以上の如く構成された本発明の一実施例は
、地震によって原子炉圧力容器10fl中熱遮蔽壁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・・・によって格納容器本
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
向叶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。よって前記レール118は格納容器本体1
01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10ノの高さを低くてき、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1
15・・・を上7jパに突設したので、これら支持部材
115・・・の上端部は格納容器本体10.1の上端開
口の周囲に位置゛する。よってこれら支持部材115・
・・の荷重を受ける取付金A114はフランジ部材11
2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
が簡単となシ、建築コストを低減することができる。
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. An embodiment of the present invention configured as described above is configured to run along the reactor pressure vessel 10fl during 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. Since the support members 115 are arranged upward from the upper end of the heat shield wall 108, there is no obstruction between the outer peripheral surface of the heat shield wall 108 and the inner surface of the containment vessel body 101. There are no components. Therefore, the rail 118 is connected to the containment vessel main body 1.
01, the height of the containment vessel body 10 can be lowered by that amount, and this 'containment vessel body 1
The earthquake resistance of 01 is improved. Moreover, in this way, the support member 1
15 are provided protruding from the upper part 7j, so that the upper ends of these support members 115 are positioned around the upper opening of the containment vessel main body 10.1. Therefore, these supporting members 115・
The mounting bracket A114 that receives the load of... is the flange member 11
Since only one such mounting fitting 114 is required, the structure of the containment vessel main body 101 is simplified and the construction cost can be reduced.

なお、本発明は必らずしも上記の一実施例には限定され
ない。
Note that the present invention is not necessarily limited to the above embodiment.

たとえば支持部材取付用の取付金具とフランジ部材取付
用の取付金具は必らずしも共用しなくてもよい。
For example, the mounting bracket for attaching the support member and the mounting bracket for attaching the flange member do not necessarily have to be used in common.

また、支持部材は必らずしも上記−実施例の如きトラス
構造に組まなくてもよく、他の形状めトラス構造であっ
てもよい。
Further, the support member does not necessarily have to be assembled into a truss structure as in the above-mentioned embodiments, but may have a truss structure in other shapes.

上述の如く本発明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九原子炉圧力容器を囲ん
で設けられ九円筒状の熱遮蔽壁と、この熱遮蔽壁の上部
と上記格納容器本体の土壁部とを連結し局方向に連続し
たトラス状に組まれた支持部材とを臭備したものである
As mentioned above, the present invention includes a containment vessel body made of concrete,
Nine cylindrical heat shielding walls are housed in the containment vessel body and are provided surrounding the nine reactor pressure vessels, and the upper part of this heat shielding wall is connected to the soil wall of the containment vessel body and is continuous in the local direction. It is equipped with a supporting member assembled in a truss shape.

し九がりて地震等によ)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。
The horizontal load acting 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 the horizontal load of the wall.

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関に
は邪魔な部材が存在しない、よってホイストクレーン走
行用のし、−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
、耐震性が向上する等その効果は大である。
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 main body of the containment vessel. The space between this heat shielding wall and the containment vessel body can be used effectively by installing it at the top of the containment vessel, and the height of the containment vessel body can be reduced by that amount, improving earthquake resistance. The effect is great.

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

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6wJ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因は第5
図の■−■矢視図である。 101・・・格納容器本体、102・・・ライナー、1
01・・・原子炉圧力容器、108・・・熱遮蔽壁、1
12・・・フランジ部材、113・・・上蓋、114・
・・取付金具、115・・・支持部材、111・・・摺
動−機構。 出願人代理人  弁理士 鈴 江 武 彦第1図 第2図 第3図 第4図 特許庁長官 島田春樹  殿 1. 事件の表示 特願昭56−101620 号 2・ 発明の名称 原子炉格納容器 3、補正をする者 、 事件との関係 特許出願人 (307>  東京芝浦電気株式会社 4、代理人 5、自発補正
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. Figures 3 to 6 wJ show an embodiment of the present invention;
The figure is a vertical cross-sectional view of the whole, Figure 4 is a vertical cross-sectional view showing a part enlarged, Figure 5 is a view taken along the ■-■ arrow in Figure 4, and the sixth factor is the fifth factor.
It is a view taken along the ■-■ arrow in the figure. 101... Containment vessel main body, 102... Liner, 1
01... Reactor pressure vessel, 108... Heat shield wall, 1
12...Flange member, 113...Top lid, 114...
...Mounting bracket, 115...Supporting member, 111...Sliding mechanism. Applicant's representative Patent attorney Takehiko Suzue Figure 1 Figure 2 Figure 3 Figure 4 Commissioner of the Patent Office Haruki Shimada 1. Indication of the case Patent application No. 56-101620 No. 2 Name of the invention Reactor containment vessel 3, Person making the amendment, Relationship to the case Patent applicant (307> Tokyo Shibaura Electric Co., Ltd. 4, Agent 5, Voluntary amendment

Claims (2)

【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、九原子炉圧力容器を囲んで設けら
れ九円筒状の熱遮蔽壁と、この熱遮蔽壁の上端と上記格
納容器本体の土壁部とを連結し周方向に連続したトラス
状に組まれた支持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 nine cylindrical heat shielding wall housed within the containment vessel body and provided surrounding the nine reactor pressure vessels, and the upper end of this heat shielding wall and the containment vessel. 1. A nuclear reactor containment vessel characterized by comprising a supporting member connected to an earthen wall portion of a main body and constructed in a continuous truss shape in a circumferential direction.
(2)前記支持部材は前記格納容器本体の土壁部に埋設
され上蓋を取付けるフランジ部が取付けられた環状の取
付金具に取付けられていることを特徴とする特許 の原子炉格納容器。
(2) The reactor containment vessel of the patent is characterized in that the support member is attached to an annular mounting bracket that is embedded in the soil wall of the containment vessel body and has a flange portion to which the upper cover is attached.
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 true JPS582781A (en) 1983-01-08
JPS6338111B2 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)

Families Citing this family (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

Also Published As

Publication number Publication date
JPS6338111B2 (en) 1988-07-28

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