JPS58178290A - Reactor container structure - Google Patents

Reactor container structure

Info

Publication number
JPS58178290A
JPS58178290A JP57060360A JP6036082A JPS58178290A JP S58178290 A JPS58178290 A JP S58178290A JP 57060360 A JP57060360 A JP 57060360A JP 6036082 A JP6036082 A JP 6036082A JP S58178290 A JPS58178290 A JP S58178290A
Authority
JP
Japan
Prior art keywords
main
vessel
container
reactor
safety
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
Application number
JP57060360A
Other languages
Japanese (ja)
Inventor
庄司 孝一
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 JP57060360A priority Critical patent/JPS58178290A/en
Publication of JPS58178290A publication Critical patent/JPS58178290A/en
Pending 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

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】 本発明は堕撮機構を備え九原子炉容器構造の改良に係り
特に大暑な地震力に対する吊下げ型原子炉主容器の安全
性を向上させた原子炉容器構造に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement of nine nuclear reactor vessel structures equipped with a photographing mechanism, and particularly to a nuclear reactor vessel structure that improves the safety of a suspended type reactor main vessel against severe earthquake forces.

吊下げ麿の原子炉容器は、一般に、炉心および炉心構造
物を格納してそれらの周囲に冷却材バウンダリを形成す
るタンク型主容器と、この主容器の外側を橿う安全容器
で構成されており、これら内容Sは共通の蓋となるルー
フスラブに吊下げられている。タンク型主容器は、熱応
力の緩和と製作費低減の目的で大口径薄肉構造とされて
いるので、地震時のスロッシングやバルジング等、内蔵
流体と主容器壁との達成振動を考慮する必要があり、q
llK吊下げ構造の場合には、各容器の地震挙動対策と
して主容器外壁へのサポート構造が必要とされてbた。
A suspended nuclear reactor vessel generally consists of a tank-type main vessel that houses the reactor core and core structures and forms a coolant boundary around them, and a safety vessel that extends around the outside of this main vessel. These contents S are suspended from a roof slab serving as a common lid. The tank-type main vessel has a large-diameter, thin-walled structure for the purpose of alleviating thermal stress and reducing manufacturing costs, so it is necessary to take into account possible vibrations between the built-in fluid and the main vessel wall, such as sloshing and bulging during earthquakes. Yes, q
In the case of the llK suspension structure, a support structure for the outer wall of the main container was required as a countermeasure against the seismic behavior of each container.

しかしながら、従来のサポート構造には、種々の問題点
があった。則ち、例えば、主容器を弾性ばねまたはオイ
ル利用のダッシュポットによす安全容器に支持する方法
では、ダンパーに方向性が生じ、どの方向から来るか予
測し得ない地震波に対して支持力が均一にならない。
However, conventional support structures have various problems. For example, in a method where the main container is supported by a safety container using an elastic spring or oil-based dashpot, the damper becomes directional and has no supporting force against seismic waves that cannot be predicted from which direction. It won't be uniform.

壜た、ダンパーの取付けのため、主容器と安全容器の双
方にダンパー順封部とそれらの補強Sを必要とするが、
これらの職封部や補強部を形成すると主容器は不均一板
厚構造となるため、熱応力の問題が生じやすく、しかも
供用期間中検査(I8I)等O障書となる。均一板厚と
するために主容器全体の璽厚を増加させると、贋作コス
トが著しく上昇する上に熱応力の問題が生ずる。
In order to install the damper, the damper sequential sealing part and their reinforcement S are required on both the main container and the safety container.
If these sealing parts and reinforcement parts are formed, the main container will have a non-uniform plate thickness structure, which will easily cause thermal stress problems, and will also lead to failures such as in-service inspections (I8I). Increasing the overall thickness of the main container in order to achieve a uniform plate thickness not only significantly increases the cost of counterfeiting, but also causes thermal stress problems.

さらに、主容器と安全容器聞く流体等の詰め物をした場
合には、主容器溶接部I8Iができなくなる問題がある
Furthermore, if the main container and the safety container are filled with fluid or the like, there is a problem that the main container welding part I8I cannot be formed.

本発11!は、従来装置における上述の如き欠点を除去
すべくなされたもので、主容器溶接部IIIが可能で、
構成が容易で、しかもすぐれた対震性を有する防振機構
を備えた原子炉容器構造′f:提供しようとするもので
ある。
Main issue 11! This was made to eliminate the above-mentioned drawbacks of the conventional device, and it is possible to weld the main container part III.
The present invention aims to provide a nuclear reactor vessel structure 'f that is easy to construct and is equipped with a vibration isolation mechanism that has excellent anti-seismic properties.

以下図示の実施例につき、本発明の詳細な説明する。The present invention will be described in detail below with reference to the illustrated embodiments.

第1図において、原子炉容器1ii1icは、上端をル
ーフスラブ2に固定した水密構造の安全容器4が据付け
られている。この安全容器内圧はそれよ妙も直径および
長さがや中小さめ主容器5が配置され、その上4Fiル
ーフスフブ2に固定されて吊下げ構造とされて−る。ル
ーフスラグ2はその周縁部分を支持部6上に直播支承さ
れて嬉屋床面上に据付けられている。主容器5内iCは
原子炉心7と炉内構造!It!l18が収納され、また
、それらの周囲VCfま冷却材である液体ナトリウ、ム
9が充填されている。主1!a5外面溶接部には、溶接
部をおおうカバー3が、密閉構造を保つように主容器5
にと9つけられてbる。
In FIG. 1, a reactor vessel 1ii1ic has a watertight safety vessel 4 whose upper end is fixed to a roof slab 2. The internal pressure of this safety container is strangely that a main container 5 with a medium to small diameter and length is arranged, and is fixed to a 4Fi roof frame 2 to form a hanging structure. The roof slag 2 is installed on the roof surface with its peripheral portion directly supported on the support part 6. The iC inside the main vessel 5 is the reactor core 7 and the reactor internal structure! It! 118 is housed, and the surrounding area VCf is filled with liquid sodium, M9, which is a coolant. Lord 1! A cover 3 covering the welded part is attached to the main container 5 to maintain an airtight structure.
Nito 9 is attached b.

また、主客45と安全容器4との間には流動性のあるダ
ンパー媒体として液体ナトリウム10が充填されている
Further, liquid sodium 10 is filled between the main container 45 and the safety container 4 as a fluid damper medium.

上述のように構成され九本発明の防4M4wにおいて、
運転開始に際してヒートアップされると主客器5は王と
して軸方向に熱膨張するが、その外周には液体ナトリウ
ム10を充填しであるので、主客器5の熱膨張はこの液
体ナトリウムの移動によって吸収され、従って安全@′
a4との間には大自な拘束力は作用しない。
In the defense 4M4w of the present invention configured as described above,
When the main passenger unit 5 is heated up at the start of operation, it thermally expands in the axial direction, but since its outer periphery is filled with liquid sodium 10, the thermal expansion of the main passenger unit 5 is absorbed by the movement of this liquid sodium. and therefore safe @′
There is no natural restraining force between it and a4.

ま之、地震が発生し、地震波が4+1屋床から原子炉容
器m1llおよびルー7スラブ2を伝わって主客器5に
作用し九場合、主客i5は加速度金受けて撮動しようと
するが、その際にd安全容器4との間に充填された液体
す) IJウム10が主客45の加速度を抑える方向に
力を及す了すので、主容器5の受ける力は緩和され、従
って大きな地震力が作用しても破損するようなことはな
−。
However, when an earthquake occurs and the seismic waves propagate from the 4+1 roof through the reactor vessel m1ll and the roof slab 2 and act on the main passenger unit 5, the main passenger i5 receives the acceleration and tries to take a picture. At this time, the IJum 10 exerts a force in the direction of suppressing the acceleration of the main passenger 45 (liquid filled between it and the safety container 4), so the force received by the main container 5 is alleviated, and therefore the large seismic force is Even if it acts, it will not be damaged.

を九、主客器5と安全容器4の間に充填しt液体ナトリ
ウム10け上述のようにダンパー媒体として機能するだ
けでなく、万一、炉心が融解するような事故が発生し念
場合にけ、冷却材として利用で舞るので、安全容器4け
コアキャッチャの機能を持つことになる。
9. Fill 10 tons of liquid sodium between the main passenger unit 5 and the safety vessel 4 to not only function as a damper medium as described above, but also to be used in case an accident such as melting of the reactor core occurs. Since it is used as a coolant, the safety container functions as a 4-piece core catcher.

さらに、主客器5[1部ではカバー3を設け、ダンパー
媒体によりシールしているので、この部分よりガスサン
プリングしエアゾルサンプリングmNa漏洩検出器へ導
くことで、溶P4部I8Iが可能となる・ なお、以上の説明では主客器5と安全容a4の間に液体
す) IJウム10を充填した例につき述べたが、本発
明はこれに限定されるものではなく、例えば嘱2図に示
す如く、チック(Nak )、砂、ボール等のダンパー
媒体11を使用することもできる。また、同図に示すよ
うに主f1.55の外面に制動用のひれ12t−突出さ
せておけば、主客器5が加速力を受けた際の制動力が増
加するので耐震性は一段と向上する。
Furthermore, since the cover 3 is installed in the main container 5 [1 part and sealed with a damper medium, by sampling gas from this part and guiding it to the aerosol sampling mNa leak detector, it becomes possible to perform the molten P4 part I8I. In the above explanation, an example was described in which IJum 10 was filled between the main container 5 and the safety container A4, but the present invention is not limited to this, and for example, as shown in Figure 2, Damper media 11 such as ticks, sand, balls, etc. can also be used. Additionally, as shown in the figure, if 12t of braking fins are protruded from the outer surface of the main f1.55, the braking force will increase when the main passenger unit 5 receives acceleration force, thereby further improving earthquake resistance. .

さらに、王容尋5溶接部I81の方法は、カバー3を設
けておけば、接触型Na漏洩検出器を設置してもよく、
カバー内にレールを設置してUT等による検査横6を駆
動させることでも可能となる。
Furthermore, in the method of Wang Yongjin 5 welding part I81, as long as the cover 3 is provided, a contact type Na leak detector may be installed;
This can also be done by installing a rail inside the cover and driving the inspection side 6 using a UT or the like.

このように、本発明によれば、従来の弾性ばねヤダッシ
ュボノト等のダンパーの取付けによって生じていた局部
反力を避けることができ、また、サポートをとるための
主容器の補強は不要となり、薄肉構造で熱的問題のない
主容器を使用することができる。また、本発明における
ダンパーには方向性がないので、いずれの方向からの地
1[に対して一十分に対処することができる。
As described above, according to the present invention, it is possible to avoid the local reaction force that occurs due to the attachment of a damper such as a conventional elastic spring Yadashbonoto, and there is no need to reinforce the main container to provide support. A main vessel without thermal problems can be used. Further, since the damper according to the present invention has no directionality, it can sufficiently deal with the ground 1 from any direction.

さらに、主容器と安全容器間に結め物をした場合でも主
容器溶接部のISIを可能とすることができる。
Furthermore, even when a tie is made between the main container and the safety container, ISI of the welded portion of the main container can be performed.

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

@1図と第2図は夫々本発明の一実施例における原子炉
容器構造の縦断面図である。 2 ルーフスラブ   3 カバー 4 安全容器     5 主容器 10  液体ナトリウム  11  ダンパー媒体12
  ひれ (7317)  代理人 弁理士 則 近 憲 佑 (
ほか1名)第1図
1 and 2 are longitudinal sectional views of the reactor vessel structure in one embodiment of the present invention, respectively. 2 Roof slab 3 Cover 4 Safety container 5 Main container 10 Liquid sodium 11 Damper medium 12
Fin (7317) Agent Patent Attorney Noriyuki Chika (
1 other person) Figure 1

Claims (1)

【特許請求の範囲】 1、原子炉主容器とこれを覆う安全容器とを同一のルー
フスラ/に吊下げると共に、前記主容器と安全容器との
関に流動性のダンパー媒体を充填し、主容器溶接部外m
に溶接部をおおうカッ(一部材を設置してなることを特
徴とする原子炉vI#器構造0 2、前記主容器は外壁に制動用のひれを有していること
を特徴とする特許請求の範囲第1項記載の原子炉容器構
造。 3、流動性のダンパー媒体は液体す) +1ウムの如き
液体から成ることを特徴とする特1f’F請求の範囲第
1項または第2項記載の原子炉容器構造。
[Claims] 1. Suspend the reactor main vessel and the safety vessel that covers it from the same roof slab, fill the gap between the main vessel and the safety vessel with a fluid damper medium, and Outside welding area m
Nuclear reactor structure 02, characterized in that the main vessel has a braking fin on its outer wall. 3. The reactor vessel structure according to claim 1, characterized in that the fluid damper medium is made of a liquid such as +1 um. reactor vessel structure.
JP57060360A 1982-04-13 1982-04-13 Reactor container structure Pending JPS58178290A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57060360A JPS58178290A (en) 1982-04-13 1982-04-13 Reactor container structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57060360A JPS58178290A (en) 1982-04-13 1982-04-13 Reactor container structure

Publications (1)

Publication Number Publication Date
JPS58178290A true JPS58178290A (en) 1983-10-19

Family

ID=13139895

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57060360A Pending JPS58178290A (en) 1982-04-13 1982-04-13 Reactor container structure

Country Status (1)

Country Link
JP (1) JPS58178290A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6089799A (en) * 1983-10-24 1985-05-20 財団法人電力中央研究所 Nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6089799A (en) * 1983-10-24 1985-05-20 財団法人電力中央研究所 Nuclear reactor

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