JPH08262176A - Method for installing heat insulation layer of reactor pressure vessel - Google Patents

Method for installing heat insulation layer of reactor pressure vessel

Info

Publication number
JPH08262176A
JPH08262176A JP7059231A JP5923195A JPH08262176A JP H08262176 A JPH08262176 A JP H08262176A JP 7059231 A JP7059231 A JP 7059231A JP 5923195 A JP5923195 A JP 5923195A JP H08262176 A JPH08262176 A JP H08262176A
Authority
JP
Japan
Prior art keywords
pressure vessel
heat insulating
insulating layer
reactor pressure
heat insulation
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
JP7059231A
Other languages
Japanese (ja)
Inventor
Hisayuki Yamanaka
久幸 山中
Taeko Saito
多恵子 齋藤
Kumiko Araki
久美子 荒木
Akio Okamoto
旦夫 岡本
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.)
IHI Corp
Original Assignee
IHI Corp
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 IHI Corp filed Critical IHI Corp
Priority to JP7059231A priority Critical patent/JPH08262176A/en
Publication of JPH08262176A publication Critical patent/JPH08262176A/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

PURPOSE: To provide a method for installing a new heat insulation vessel for preventing thermal loss due to air leakage and the damage in the heat insulation vessel when installing the pressure vessel in advance. CONSTITUTION: A nuclear pressure vessel 4 is erected on a pedestal 3 via a skirt part 13 projected around it and at the same time a heat insulation layer 14 for shutting off heat is installed around the nuclear pressure vessel 4. A heat insulation layer is divided into an upper heat insulation layer 14a provided at the upper portion of the skirt part 13 of the nuclear pressure vessel, a bottom heat insulation layer 14b provided at the bottom part of the nuclear pressure vessel 4, and a plurality of heat insulation plates 14c provided between the upper heat insulation layer 14a and the bottom heat insulation layer 14b. The upper heat insulation layer 14a and the bottom heat insulation layer 14b are installed in advance out of them, at the same time the heat insulation plate 14c is mounted to the inner surface of the skirt part 13, and then the nuclear pressure vessel 4 is installed on the pedestal 3 to connect the heat insulation plate 14c and the bottom heat insulation layer 14b.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は原子炉格納容器内に収容
されている原子炉圧力容器の熱を遮断するための保温層
の据付け工法に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a heat insulating layer installation method for shutting off heat from a reactor pressure vessel housed in a reactor containment vessel.

【0002】[0002]

【従来の技術】図5は従来の原子炉格納容器(ABWR
改良型騰水原子炉)の一例を示したものである。図示
するようにこの原子炉格納容器は、建屋1内に建設され
た釣鐘状の鋼板製格納容器2内に、円筒状のペデスタル
3が立設され、このペデスタル3の上端部に略円筒形に
形成された原子炉圧力容器4が支持されて収容されてい
る。また、この鋼板製格納容器2内はペデスタル3の上
端部から水平方向に延びたドーナツ板状のダイヤフラム
フロア5によって上部ドライウェル6と圧力抑制室7
と、下部ドライウェル8とに区画されており、さらにこ
の上部ドライウェル6側に位置している原子炉圧力容器
4の周囲には放射線などを遮蔽するための原子炉遮蔽壁
9が設けられ、また、圧力抑制室7には蒸気を凝縮する
ための冷却水が収容された構造となっている。そして、
この原子炉圧力容器4は図6に示すように、その胴部4
aの外周部に設けられたスカート部13をペデスタル3
の台座3aに着座させることでペデスタル3上に据え付
けられるようになっている。尚、図5中10は上部ドラ
イウェルに漏れだした蒸気を圧力抑制室7側に流すベン
ト管、11は作業員の出入りや機器類の搬出入を行うレ
イズトンネル、12は同じくアクセス用ハッチ、図6
中、4bは冷却水を循環するインタ−ナルポンプであ
る。
2. Description of the Related Art FIG. 5 shows a conventional containment vessel (ABWR).
This is an example of an improved type rising water reactor. As shown in the figure, in this reactor containment vessel, a cylindrical pedestal 3 is erected in a bell-shaped steel plate containment vessel 2 constructed in a building 1, and a substantially cylindrical shape is provided at the upper end of this pedestal 3. The formed reactor pressure vessel 4 is supported and accommodated. Further, the inside of the steel plate storage container 2 is provided with an upper dry well 6 and a pressure suppression chamber 7 by a donut plate-shaped diaphragm floor 5 extending horizontally from the upper end of the pedestal 3.
And a lower dry well 8, and a reactor shielding wall 9 for shielding radiation and the like is provided around the reactor pressure vessel 4 located on the upper dry well 6 side. Further, the pressure suppression chamber 7 has a structure in which cooling water for condensing steam is accommodated. And
As shown in FIG. 6, the reactor pressure vessel 4 has a body portion 4
The skirt portion 13 provided on the outer peripheral portion of a is attached to the pedestal 3
The pedestal 3 can be mounted on the pedestal 3a. In FIG. 5, 10 is a vent pipe through which steam leaking to the upper dry well is made to flow to the pressure suppression chamber 7, 11 is a raise tunnel for carrying in and out of workers and carrying in and out of equipment, 12 is also an access hatch, Figure 6
Inside, 4b is an internal pump for circulating cooling water.

【0003】また、この原子炉圧力容器4は運転を開始
すると高温に達することから、図8に示すように、その
周囲には複数枚のアルミ薄板15…を枠板16内に積層
してなる保温層14が所定の間隔を隔ててこれを囲繞す
るように設けられており、保温層14内の空気の対流を
抑制することで原子炉圧力容器4側の熱を遮断して熱損
失を防止するようになっている。また、上述したよう
に、この原子炉圧力容器4はスカート部13をペデスタ
ル3の台座3aに着座させることでペデスタル3上に据
え付けられるようになっているため、この周囲に設けら
れる保温層14もスカート部13を境にして上下に二分
割されており、スカート部13より上方に設けられる上
部保温層14aと、スカート部13より底部に設けられ
る底部保温層14bとから構成されている。そして、先
ず、これら上部保温層14aを原子炉圧力容器4側に、
底部保温層14bをその上端部が突出するようにペデス
タル3側にそれぞれ据え付けた後、図7に示すように、
原子炉圧力容器4を垂直に降下させてそのスカート部1
3をペデスタル3に着座させることによって、スカート
部13の内面に沿って屈曲した底部保温層14bの頂部
を内面に密着し、このスカート部13を挟んで上部保温
層14aと底部保温層14bとが合体し、連続した保温
層14が形成されて良好な断熱効果を発揮するようにな
っている。
Further, since the reactor pressure vessel 4 reaches a high temperature when the operation is started, as shown in FIG. 8, a plurality of aluminum thin plates 15 ... The heat insulating layer 14 is provided so as to surround the heat insulating layer 14 with a predetermined space therebetween, and by suppressing the convection of the air in the heat insulating layer 14, the heat on the reactor pressure vessel 4 side is blocked and the heat loss is prevented. It is supposed to do. Further, as described above, since the reactor pressure vessel 4 is designed to be installed on the pedestal 3 by seating the skirt portion 13 on the pedestal 3a of the pedestal 3, the heat insulating layer 14 provided around the pedestal 3 as well. It is vertically divided into two parts with the skirt portion 13 as a boundary, and is composed of an upper heat insulating layer 14a provided above the skirt portion 13 and a bottom heat insulating layer 14b provided at the bottom of the skirt portion 13. Then, first, these upper heat retaining layers 14a are provided on the reactor pressure vessel 4 side,
After installing the bottom heat insulating layer 14b on the pedestal 3 side so that the upper end thereof projects, as shown in FIG.
The reactor pressure vessel 4 is lowered vertically and its skirt 1
By seating 3 on the pedestal 3, the top portion of the bottom heat insulating layer 14b bent along the inner surface of the skirt portion 13 is brought into close contact with the inner surface, and the upper heat insulating layer 14a and the bottom heat insulating layer 14b are sandwiched with the skirt portion 13 interposed therebetween. They are united to form a continuous heat retaining layer 14 to exert a good heat insulating effect.

【0004】[0004]

【発明が解決しようとする課題】ところで、このような
従来の据付け工法では、支持スカート部13の加工精度
のばらつきによって図9に示すように、スカート部13
の内面と底部保温層14bとの間に隙間が生じて原子炉
圧力容器4側の高温空気が漏れてしまい、熱損失を招い
てしまったり、また、据付け時の圧力容器4の傾きやク
レーンの振れ等によって、スカート部13が底部保温層
14bに接触してこれが破損してしまう等の不都合があ
った。
By the way, in such a conventional installation method, as shown in FIG.
There is a gap between the inner surface of the reactor and the bottom heat retaining layer 14b, and the high temperature air on the side of the reactor pressure vessel 4 leaks out, resulting in heat loss. Also, the inclination of the pressure vessel 4 during installation and the crane There is a problem that the skirt portion 13 comes into contact with the bottom heat insulating layer 14b and is damaged due to shake or the like.

【0005】そこで、本発明は上記課題を解決するため
に案出されたものであり、その目的は空気漏れによる熱
損失や、圧力容器据え付け時の保温層の破損などを未然
に防止することができる新規な原子炉圧力容器の保温層
据付け工法を提供することにある。
Therefore, the present invention has been devised to solve the above problems, and its purpose is to prevent heat loss due to air leakage and damage to the heat retaining layer when the pressure vessel is installed. A new reactor pressure vessel heat insulation layer installation method that can be performed is provided.

【0006】[0006]

【課題を解決するための手段】上記目的を達成するため
に、第一の発明は原子炉圧力容器を、その周囲に張り出
したスカート部を介してペデスタル上に立設すると共
に、この原子炉圧力容器の周囲に熱を遮断するための保
温層を据付ける工法において、上記保温層を上記原子炉
圧力容器のスカート部より上方に設けられる上部保温層
と、上記原子炉圧力容器の底部に設けられる底部保温層
と、これら上部保温層と底部保温層との間に設けられる
複数の保温板とに分割し、このうち上記上部保温層と底
部保温層を予め設置すると共に、上記保温板を上記スカ
ート部の内面に取り付けた後、この原子炉圧力容器をペ
デスタル上に据え付けて上記保温板と底部保温層とを接
続させるようにしたものであり、第二の発明は、上記保
温層を上記原子炉圧力容器のスカート部より上方に設け
られる上部保温層と、上記原子炉圧力容器の底部に設け
られる底部保温層と、これら上部保温層と底部保温層と
の間に設けられる複数の保温板とに分割し、このうち上
記上部底部保温層を予め設置してから上記原子炉圧力容
器をペデスタル上に据え付け、その後、上記スカート部
内面とペデスタルに設けられたサポートによって上記保
温板を上部保温層と底部保温層間に据え付けるようにし
たものであり、さらに第三の発明は、上記保温層を上記
原子炉圧力容器のスカート部より上方に設けられる上部
保温層と、このスカート部の内面より底部に設けられる
底部保温層とに分割し、これら上部保温層と底部保温層
を予め設置すると共に、この底部保温層の上記スカート
部内面に接する位置に耐熱性のシール部材を設け、その
後、上記原子炉圧力容器をペデスタル上に据え付けるよ
うにしたものである。
In order to achieve the above object, the first aspect of the invention is to install a reactor pressure vessel on a pedestal through a skirt portion projecting around the reactor pressure vessel, and In a method of installing a heat insulating layer for cutting off heat around a vessel, the heat insulating layer is provided on an upper heat insulating layer provided above a skirt portion of the reactor pressure vessel and on a bottom portion of the reactor pressure vessel. It is divided into a bottom heat insulating layer and a plurality of heat insulating plates provided between the upper heat insulating layer and the bottom heat insulating layer, of which the upper heat insulating layer and the bottom heat insulating layer are installed in advance and the heat insulating plate is attached to the skirt. After attaching to the inner surface of the section, the reactor pressure vessel is installed on a pedestal so as to connect the heat insulating plate and the bottom heat insulating layer, and the second invention is to install the heat insulating layer in the reactor. Pressure Divided into an upper heat insulating layer provided above the skirt of the vessel, a bottom heat insulating layer provided at the bottom of the reactor pressure vessel, and a plurality of heat insulating plates provided between the upper heat insulating layer and the bottom heat insulating layer. Among them, after installing the upper bottom heat insulating layer in advance, install the reactor pressure vessel on the pedestal, and then support the heat insulating plate with the upper heat insulating layer and the bottom heat insulating layer by the support provided on the inner surface of the skirt and the pedestal. The third aspect of the present invention is to install the heat insulating layer above the heat insulating layer above the skirt portion of the reactor pressure vessel, and the bottom portion below the inner surface of the skirt portion. It is divided into a heat insulating layer, and these upper heat insulating layer and bottom heat insulating layer are installed in advance, and a heat-resistant seal is placed at a position of the bottom heat insulating layer in contact with the inner surface of the skirt. The timber is provided, then, is obtained by the so install the reactor pressure vessel on the pedestal.

【0007】[0007]

【作用】第一の発明は上述したように、原子炉圧力容器
をペデスタル上に据え付ける前に、予め保温板をスカー
ト部の内面に取り付けるようにしたため、スカート部の
加工精度にばらつきがあっても、このスカート部と、そ
の内面に設けられる保温板との間に隙間が生じなくな
り、この隙間からの空気の漏れを未然に防止することが
できる。また、据え付け時に原子炉圧力容器が多少揺れ
たり、傾いたりしても、この保温板の底部は解放された
状態となっているため、保温板がペデスタルに接触して
破損するような不都合も未然に防止できる。また、第二
の発明は、圧力容器をペデスタル上に据え付けた後に、
そのスカート部の内面とペデスタルに設けられたサポー
ト間に保温板を嵌め込んで上部保温層と底部保温層間を
接続するようにしたため、第一の発明と同様に空気漏れ
や据え付け時の断熱層の破損などの不都合を未然に防止
することができる。また、第三の発明によれば、底部保
温層のスカート部内面に接する位置に耐熱性のシール部
材を設けることにより、底部保温層とスカート部内面間
に隙間が生じた場合であっても上記発明と同様に、この
隙間からの空気漏れを防止することができる。また、シ
ール部材の幅の分だけ、底部保温層とスカート部との間
隔をあけることができるため、据え付け時に圧力容器が
多少振れたり、傾いたりしても底部保温層に接触して、
これを破損してしまう確率が大幅に減少する。
As described above, according to the first aspect of the invention, since the heat insulating plate is attached to the inner surface of the skirt in advance before the reactor pressure vessel is installed on the pedestal, even if the machining accuracy of the skirt varies. A gap is not formed between the skirt portion and the heat insulating plate provided on the inner surface of the skirt portion, and air can be prevented from leaking from the gap. In addition, even if the reactor pressure vessel sways or tilts during installation, the bottom of this heat retaining plate is still open, so there is the inconvenience that the heat retaining plate will contact the pedestal and break. Can be prevented. In addition, the second invention, after installing the pressure vessel on the pedestal,
Since the heat insulating plate was fitted between the inner surface of the skirt portion and the support provided on the pedestal to connect the upper heat insulating layer and the bottom heat insulating layer, air leakage and insulation layer at the time of installation like the first invention Inconvenience such as breakage can be prevented in advance. Further, according to the third invention, by providing a heat-resistant seal member at a position in contact with the inner surface of the skirt portion of the bottom heat insulating layer, even if a gap is generated between the bottom heat insulating layer and the inner surface of the skirt portion, As with the invention, it is possible to prevent air leakage from this gap. Further, since the space between the bottom heat insulating layer and the skirt can be opened by the width of the sealing member, even if the pressure vessel is slightly shaken or tilted during installation, the bottom heat insulating layer contacts the bottom heat insulating layer.
The probability of damaging it is greatly reduced.

【0008】[0008]

【実施例】以下、本発明の一実施例を添付図面に基づい
て詳述する。
An embodiment of the present invention will be described in detail below with reference to the accompanying drawings.

【0009】図1は第一の発明に係る断熱層据付け工法
の一実施例を示したものであり、図中13は上述した原
子炉圧力容器4のスカート部、3aはこのスカート部1
3を着座させて据え付ける台座、14bは上述したよう
に原子炉圧力容器4を断熱するためにこの台座3aに支
持された底部保温層である。図示するように、本実施例
は、この底部保温層14bの上端部、すなわち、台座3
aより上方に突出してスカート部13の内面に位置する
部分を分割し、この分割された部分を上述したような底
部保温層14bと同様な構成をした保温板14cで構成
し、この保温板14cの上端部をスカート部13の内面
に設けられたフック等の係合手段18に係合させて密着
させてから、原子炉圧力容器4を台座3aに着座させて
据え付けるようにしたものである。従って、図示するよ
うに、原子炉圧力容器4を台座3aに着座させた際に、
この保温板14cの下端部が予め据え付けられている底
部保温層14bと連続するように接続されるようにな
り、保温板14cとスカート部13の内面との間は勿
論、保温板14cの下端部と底部保温層14bの上端部
との間も接続されて空気漏れなどによる断熱効果の低下
を未然に防止することができる。また、この保温板14
cの下端部と底部保温層14bの上端部との間に案内溝
19を設けることにより、圧力容器4を降下させるだけ
で保温板14cと底部保温層14bとの接続が容易に行
われると同時に保温板14cの落下も未然に防止するこ
とができる。尚、この保温板14cをスカート部13の
内面に係合させる係合手段18としては、図2(A)に
示すように、止め金具20とリベット21を用いて図示
するような構成にしたり、同図(B)に示すように、ボ
ルト22を用いたものでも良い。また、同図に示すよう
に、この保温板14cをその高さ方向に細かく分割し、
これらをリベット21等で接続することで、形状に適度
な自由性を持たせるように構成しても良い。
FIG. 1 shows an embodiment of the heat insulating layer installation method according to the first invention, in which 13 is a skirt portion of the reactor pressure vessel 4 and 3a is this skirt portion 1.
The pedestal 3 on which 3 is seated and installed, and 14b is the bottom heat insulating layer supported by this pedestal 3a for insulating the reactor pressure vessel 4 as described above. As shown in the figure, in this embodiment, the upper end portion of the bottom heat insulating layer 14b, that is, the pedestal 3
A portion projecting upward from a and located on the inner surface of the skirt portion 13 is divided, and the divided portion is constituted by a heat insulating plate 14c having the same structure as the bottom heat insulating layer 14b as described above. The upper end of the reactor is engaged with the engaging means 18 such as a hook provided on the inner surface of the skirt portion 13 to be in close contact therewith, and then the reactor pressure vessel 4 is seated on the pedestal 3a and installed. Therefore, as shown in the figure, when the reactor pressure vessel 4 is seated on the pedestal 3a,
The lower end of the heat insulating plate 14c is connected so as to be continuous with the bottom heat insulating layer 14b installed in advance, and the lower end of the heat insulating plate 14c is not only between the heat insulating plate 14c and the inner surface of the skirt portion 13. The upper part of the bottom heat insulating layer 14b is also connected to prevent a decrease in the heat insulating effect due to air leakage or the like. Also, this heat insulation plate 14
By providing the guide groove 19 between the lower end of c and the upper end of the bottom heat insulating layer 14b, the heat insulating plate 14c and the bottom heat insulating layer 14b can be easily connected at the same time by simply lowering the pressure vessel 4. It is possible to prevent the heat insulating plate 14c from dropping. As the engaging means 18 for engaging the heat retaining plate 14c with the inner surface of the skirt portion 13, as shown in FIG. 2 (A), a stopper 20 and a rivet 21 are used, or the structure shown in FIG. A bolt 22 may be used as shown in FIG. Further, as shown in the figure, the heat insulating plate 14c is finely divided in the height direction,
By connecting these with a rivet 21 or the like, the shape may be appropriately controlled.

【0010】次に、図3は第二の発明に係る断熱層据付
け工法の一実施例を示したものであり、本実施例は第一
の発明で用いた保温板14cを、原子炉圧力容器4のス
カート部13を台座3aに着座させた後に、据え付ける
ようにしたものである。そして、そのためには、図3
(A)に示すように、スカート部13を台座3aに着座
させる前に、台座3a側に、保温板14cの下端部を支
持する円環状の下部サポート23を設けると共に、スカ
ート部13の内面側に、保温板14cの下端部を支持す
る鈎状の上部サポート24を設け、この下部サポート2
3、上部サポート24間に保温板14cを嵌め込み、こ
の保温板14cを図3(B)に示すように、スカート部
13の周方向に沿って順次並べることで、保温板14c
と底部保温層14bとが一体的に接続される。従って、
スカート部13と保温板14の間は勿論、保温板14c
と底部保温層14bとも容易に接続され、効果的な断熱
が達成できる。また、スカート部13を着座させた後
に、この保温板14を据え付けるようにしたため、圧力
容器4の据え付け時の断熱層の破損も同時に防止するこ
とができる。
Next, FIG. 3 shows an embodiment of a heat insulation layer installation method according to the second invention. This embodiment is the same as the heat insulation plate 14c used in the first invention except that the reactor pressure vessel is used. After the skirt portion 13 of No. 4 is seated on the pedestal 3a, it is installed. And for that purpose, FIG.
As shown in (A), before the skirt portion 13 is seated on the pedestal 3a, an annular lower support 23 for supporting the lower end of the heat insulating plate 14c is provided on the pedestal 3a side, and the inner surface side of the skirt portion 13 is provided. Is provided with a hook-shaped upper support 24 that supports the lower end of the heat insulating plate 14c.
3 and the heat insulating plate 14c is fitted between the upper supports 24, and the heat insulating plate 14c is sequentially arranged along the circumferential direction of the skirt portion 13 as shown in FIG.
And the bottom heat insulating layer 14b are integrally connected. Therefore,
Not only between the skirt portion 13 and the heat insulating plate 14, but also the heat insulating plate 14c
And the bottom heat insulating layer 14b are easily connected, and effective heat insulation can be achieved. Further, since the heat insulating plate 14 is installed after the skirt portion 13 is seated, it is possible to prevent the heat insulating layer from being damaged when the pressure vessel 4 is installed.

【0011】次に、図4は、第三の発明の一実施例を示
したものである。図示するように、本実施例は、台座3
aより上方に突出した従来の底部保温層14bの頂部外
縁側、すなわち、スカート部13との当接面にシール部
材25を備えたものであり、これにより、スカート部1
3と底部保温層14b間に隙間が生じていても、原子炉
圧力容器4側の高温空気の漏れ出すのを防止することが
できる。
Next, FIG. 4 shows an embodiment of the third invention. As shown in the figure, this embodiment has a base 3
A seal member 25 is provided on the top outer edge side of the conventional bottom heat retaining layer 14b protruding above a, that is, on the contact surface with the skirt portion 13, whereby the skirt portion 1 is formed.
It is possible to prevent the high temperature air from leaking out from the side of the reactor pressure vessel 4 even if there is a gap between the No. 3 and the bottom heat insulating layer 14b.

【0012】このシール部材25は、原子炉圧力容器4
の周囲の高温に達することから、これ以上の耐熱性を備
えたものが使用され、例えば、ステンレスクロス等の金
属繊維からなるものが適している。さらに、このスカー
ト部13と底部保温層14bとの隙間が不均一であるこ
とから、このシール部材25に適度な厚さを持たせるた
めに、帯状のステンレスクロス25aをその長さ方向に
折り、その間に耐熱性のウェブ、例えば、ステンレス製
のウェブ25bを入れた後、このステンレスクロス25
aの合わせ面をリベットなどのクロス止め金具25cで
保温層14側に固定し、さらに、その下部にクロス押え
金具25dを設けて、ウェブ25bに弾力性を持たせる
と共に、これが広がって潰れるのを防止するようにした
ものである。
This seal member 25 is used for the reactor pressure vessel 4
Since it reaches a high temperature in the surroundings, a material having heat resistance higher than that is used, and for example, a material made of metal fiber such as stainless cloth is suitable. Further, since the gap between the skirt portion 13 and the bottom heat insulating layer 14b is non-uniform, in order to give the seal member 25 an appropriate thickness, the band-shaped stainless cloth 25a is folded in its length direction, After inserting a heat resistant web, for example, a stainless web 25b, in between, the stainless cloth 25
The mating surface of a is fixed to the heat retaining layer 14 side by a cross stopper metal fitting 25c such as a rivet, and further, a cross pressing metal fitting 25d is provided under the metal fitting so as to give the web 25b elasticity and prevent it from expanding and crushing. This is to prevent it.

【0013】これにより、上述したように、加工精度の
ばらつきによるスカート部13と保温層14間からの空
気漏れを防止できることは勿論、スカート部13と保温
層14間に隙間が生じることを前提として底部保温層1
4bの径を多少小さくすることができるため、スカート
部13を台座3aに着座させる時に、このスカート部が
底部保温層14bに接触する確率が低くなり、保温層1
4の破損等の不都合を未然に防止することができる。
尚、本発明は上記実施例のような構成でも充分な効果を
発揮することができるが、上記第一の発明及び第二の発
明の保温板14cと組み合わせることも可能であり、こ
の場合にはより大きな断熱効果が得られる。
As a result, as described above, it is possible to prevent air leakage between the skirt portion 13 and the heat retaining layer 14 due to variations in processing accuracy, and of course, on the premise that a gap is formed between the skirt portion 13 and the heat retaining layer 14. Bottom heat insulation layer 1
Since the diameter of 4b can be made slightly smaller, the probability that the skirt portion will come into contact with the bottom heat insulating layer 14b when the skirt portion 13 is seated on the pedestal 3a is low, and the heat insulating layer 1
Inconvenience such as breakage of No. 4 can be prevented in advance.
Although the present invention can exert sufficient effects even with the configuration of the above embodiment, it can be combined with the heat insulating plate 14c of the first invention and the second invention, and in this case, Greater heat insulation effect is obtained.

【0014】[0014]

【発明の効果】以上要するに本発明によれば、スカート
部の加工精度によるばらつきがあっても、このスカート
部と保温層との間に隙間が生じなくなるため、圧力容器
側の高温の空気が断熱層外へ漏れなくなり、断熱効果の
低下を未然に防止することができ、しかも、据え付け時
に原子炉圧力容器が多少揺れたり、傾いたりしても、保
温層の破損や潰れ等の不都合も未然に防止できる等とい
った優れた効果を発揮する。
In summary, according to the present invention, since there is no gap between the skirt portion and the heat retaining layer even if there are variations due to the processing accuracy of the skirt portion, the high temperature air on the pressure vessel side is insulated. It is possible to prevent leakage to the outside of the layer and prevent deterioration of the heat insulation effect.Moreover, even if the reactor pressure vessel sways or tilts during installation, the insufficiency such as damage or crushing of the heat retaining layer will occur. It has excellent effects such as prevention.

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

【図1】第一の発明の一実施例を示す説明図である。FIG. 1 is an explanatory diagram showing an embodiment of the first invention.

【図2】(A)は第一の発明の第一変形実施例を示す側
面図である。(B)は第一の発明の第二変形実施例を示
す側面図である。
FIG. 2A is a side view showing a first modified embodiment of the first invention. (B) is a side view showing a second modification of the first invention.

【図3】(A)は第二の発明の一実施例を示す側面図で
ある。(B)は(A)の正面図である。
FIG. 3A is a side view showing an embodiment of the second invention. (B) is a front view of (A).

【図4】第三の発明の一実施例を示す拡大側面図であ
る。
FIG. 4 is an enlarged side view showing an embodiment of the third invention.

【図5】従来の原子炉格納容器の構成を示す全体図であ
る。
FIG. 5 is an overall view showing a configuration of a conventional reactor containment vessel.

【図6】従来の原子炉格納容器の据付け構造及び保温層
の据付け位置を示す側面図である。
FIG. 6 is a side view showing an installation structure of a conventional reactor containment vessel and an installation position of a heat retaining layer.

【図7】従来の原子炉圧力容器をペデスタルの台座上に
着座させる状態を示す説明図である。
FIG. 7 is an explanatory view showing a state in which a conventional reactor pressure vessel is seated on a pedestal of a pedestal.

【図8】従来の保温層の構造を示す分解斜視図である。FIG. 8 is an exploded perspective view showing a structure of a conventional heat retaining layer.

【図9】圧力容器のスカート部と保温層との間に隙間が
生じている状態を示す説明図である。
FIG. 9 is an explanatory diagram showing a state in which a gap is formed between the skirt portion of the pressure container and the heat retaining layer.

【符号の説明】[Explanation of symbols]

3 ペデスタル 4 原子炉圧力容器 13 スカート部 14 保温層 14a 上部保温層 14b 底部保温層 14c 保温板 23,24 サポート 25 シール部材 3 Pedestal 4 Reactor Pressure Vessel 13 Skirt 14 Thermal insulation layer 14a Upper thermal insulation layer 14b Bottom thermal insulation layer 14c Thermal insulation plate 23, 24 Support 25 Seal member

───────────────────────────────────────────────────── フロントページの続き (72)発明者 荒木 久美子 神奈川県横浜市磯子区新中原町1番地 石 川島播磨重工業株式会社横浜エンジニアリ ングセンター内 (72)発明者 岡本 旦夫 神奈川県横浜市磯子区新中原町1番地 石 川島播磨重工業株式会社横浜エンジニアリ ングセンター内 ─────────────────────────────────────────────────── ─── Continuation of front page (72) Inventor Kumiko Araki 1 Shin-Nakahara-cho, Isogo-ku, Yokohama-shi, Kanagawa Ishi Kawashima Harima Heavy Industries, Ltd. Yokohama Engineering Center (72) Inventor, Otomo Okamoto Isogo, Yokohama-shi, Kanagawa Shin-Nakahara-cho, Tokyo-shi Ishikawajima Harima Heavy Industries Ltd. Yokohama Engineering Center

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】 原子炉圧力容器を、その周囲に張り出し
たスカート部を介してペデスタル上に立設すると共に、
この原子炉圧力容器の周囲に熱を遮断するための保温層
を据付ける工法において、上記保温層を上記原子炉圧力
容器のスカート部より上方に設けられる上部保温層と、
上記原子炉圧力容器の底部に設けられる底部保温層と、
これら上部保温層と底部保温層との間に設けられる複数
の保温板とに分割し、このうち上記上部保温層と底部保
温層を予め設置すると共に、上記保温板を上記スカート
部の内面に取り付けた後、この原子炉圧力容器をペデス
タル上に据え付けて上記保温板と底部保温層とを接続さ
せることを特徴とする原子炉圧力容器の保温層据付け工
法。
1. A reactor pressure vessel is erected on a pedestal through a skirt portion that extends around the reactor pressure vessel, and
In a method of installing a heat insulating layer for shutting off heat around the reactor pressure vessel, the heat insulating layer is an upper heat insulating layer provided above the skirt portion of the reactor pressure vessel,
A bottom heat insulating layer provided at the bottom of the reactor pressure vessel,
It is divided into a plurality of heat retaining plates provided between the upper heat retaining layer and the bottom heat retaining layer, of which the upper heat retaining layer and the bottom heat retaining layer are preliminarily installed, and the heat retaining plate is attached to the inner surface of the skirt portion. After that, this reactor pressure vessel is installed on a pedestal, and the above-mentioned heat insulation plate and the bottom heat insulation layer are connected to each other.
【請求項2】 原子炉圧力容器を、その周囲に張り出し
たスカート部を介してペデスタル上に立設すると共に、
この原子炉圧力容器の周囲に熱を遮断するための保温層
を据付ける工法において、上記保温層を上記原子炉圧力
容器のスカート部より上方に設けられる上部保温層と、
上記原子炉圧力容器の底部に設けられる底部保温層と、
これら上部保温層と底部保温層との間に設けられる複数
の保温板とに分割し、このうち上記底部保温層を予め設
置してから上記原子炉圧力容器をペデスタル上に据え付
け、その後、上記スカート部内面とペデスタルに設けら
れたサポートによって上記保温板を上部保温層と底部保
温層間に据え付けることを特徴とする原子炉圧力容器の
保温層据付け工法。
2. A reactor pressure vessel is erected on a pedestal through a skirt portion that projects around the reactor pressure vessel, and
In a method of installing a heat insulating layer for shutting off heat around the reactor pressure vessel, the heat insulating layer is an upper heat insulating layer provided above the skirt portion of the reactor pressure vessel,
A bottom heat insulating layer provided at the bottom of the reactor pressure vessel,
Divide into a plurality of heat insulating plates provided between the upper heat insulating layer and the bottom heat insulating layer, of which the bottom heat insulating layer is installed in advance and then the reactor pressure vessel is installed on the pedestal, and then the skirt A heat insulation layer installation method for a reactor pressure vessel, characterized in that the heat insulation plate is installed between the top heat insulation layer and the bottom heat insulation layer by means of supports provided on the inner surface of the section and the pedestal.
【請求項3】 原子炉圧力容器を、その周囲に張り出し
たスカート部を介してペデスタル上に立設すると共に、
この原子炉圧力容器の周囲に熱を遮断するための保温層
を据付ける工法において、上記保温層を上記原子炉圧力
容器のスカート部より上方に設けられる上部保温層と、
このスカート部の内面より底部に設けられる底部保温層
とに分割し、これら上部保温層と底部保温層を予め設置
すると共に、この底部保温層の上記スカート部内面に接
する位置に耐熱性のシール部材を設け、その後、上記原
子炉圧力容器をペデスタル上に据え付けることを特徴と
する原子炉圧力容器の保温層据付け工法。
3. A reactor pressure vessel is erected on a pedestal through a skirt portion that extends around the reactor pressure vessel, and
In a method of installing a heat insulating layer for shutting off heat around the reactor pressure vessel, the heat insulating layer is an upper heat insulating layer provided above the skirt portion of the reactor pressure vessel,
The skirt is divided into an inner surface and a bottom heat insulating layer provided at the bottom, and the upper heat insulating layer and the bottom heat insulating layer are preliminarily installed, and a heat-resistant seal member is provided at a position of the bottom heat insulating layer in contact with the inner surface of the skirt. And then installing the reactor pressure vessel on the pedestal, the method for installing a heat insulation layer of the reactor pressure vessel.
JP7059231A 1995-03-17 1995-03-17 Method for installing heat insulation layer of reactor pressure vessel Pending JPH08262176A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7059231A JPH08262176A (en) 1995-03-17 1995-03-17 Method for installing heat insulation layer of reactor pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7059231A JPH08262176A (en) 1995-03-17 1995-03-17 Method for installing heat insulation layer of reactor pressure vessel

Publications (1)

Publication Number Publication Date
JPH08262176A true JPH08262176A (en) 1996-10-11

Family

ID=13107410

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7059231A Pending JPH08262176A (en) 1995-03-17 1995-03-17 Method for installing heat insulation layer of reactor pressure vessel

Country Status (1)

Country Link
JP (1) JPH08262176A (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2016122105A1 (en) * 2015-01-29 2016-08-04 문인득 Method for replacing steam generator of two-loop type pressurized light water reactor
WO2016122104A1 (en) * 2015-01-29 2016-08-04 문인득 Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor
KR101675077B1 (en) * 2015-12-07 2016-11-10 문인득 Construction method and displacement system for constructing the reactor coolant piping and steam generator of pressurized water reactor of 2 loop type
CN109243626A (en) * 2018-08-17 2019-01-18 中国核工业二三建设有限公司 ACP1000 nuclear pressure container cylinder insulating layer installation method

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2016122105A1 (en) * 2015-01-29 2016-08-04 문인득 Method for replacing steam generator of two-loop type pressurized light water reactor
WO2016122104A1 (en) * 2015-01-29 2016-08-04 문인득 Heat insulating material mounting structure of steam generator of two-loop type pressurized light water reactor
KR101675077B1 (en) * 2015-12-07 2016-11-10 문인득 Construction method and displacement system for constructing the reactor coolant piping and steam generator of pressurized water reactor of 2 loop type
WO2017099457A1 (en) * 2015-12-07 2017-06-15 문인득 Construction method for steam generator of two-loop type pressurized light water reactor and reverse displacement system therefor for construction of reactor pipe
CN109243626A (en) * 2018-08-17 2019-01-18 中国核工业二三建设有限公司 ACP1000 nuclear pressure container cylinder insulating layer installation method
CN109243626B (en) * 2018-08-17 2020-10-23 中国核工业二三建设有限公司 ACP1000 nuclear power pressure vessel cylinder heat-insulating layer installation method

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