JPS6147588A - Leakage countermeasure repair device for housing section of nuclear reactor vessel - Google Patents
Leakage countermeasure repair device for housing section of nuclear reactor vesselInfo
- Publication number
- JPS6147588A JPS6147588A JP59169360A JP16936084A JPS6147588A JP S6147588 A JPS6147588 A JP S6147588A JP 59169360 A JP59169360 A JP 59169360A JP 16936084 A JP16936084 A JP 16936084A JP S6147588 A JPS6147588 A JP S6147588A
- Authority
- JP
- Japan
- Prior art keywords
- housing
- seal ring
- collar
- stub tube
- seal
- 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
- Pipe Accessories (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】
〔発明の利用分野〕
本発明は、原子炉圧力容器（以下、ＲＰＶという。）内
のｉｌｉ！Ｉ御棒駆動機渭し・ウジング（以下、Ｃ几Ｄ
ハウジングという。）の溶接部近傍におけるリーク防止
対策補修装置に関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention provides an ili! I-rod drive mechanism (C-D)
It's called housing. ) related to leak prevention repair equipment near welded parts.
ＲＰＶ内のＣＲＤハウジングおよびスタブチューブは１
１４図に示す組み合せ構造となっている。CRD housing and stub tube in RPV are 1
The combined structure is shown in Figure 14.
即ちインコネル材等によシ肉盛シ溶接ＩＤが施された几
ＰＶＩに貫通孔１人が設けられると共にこのＲＰＶＩの
内面に孔ＩＡと連通ずる円筒型のスタブチューブ２が溶
接部３を介して取シ付けられている。スタブチューブ２
は突端につば２１を有し、このスタブチューブ２に通し
たＣＲ，Ｄノ・ウジング４がスタブチューブ２の突端に
溶接部５を介して取付けられている。国内の従来型沸騰
水型原子炉のＣＲ，Ｄハウジング４は５ＵＳ３０４系の
鋼管を使用してお、９、ＣＲＤハウジング４の溶接部５
近傍の熱影響部においては高残留応力が発生し、結晶粒
界に沿ってクロム欠乏層が生成するので応力腐食割れに
対する感受性が高い部分５Ａが生じる。このため５ＵＳ
３０４系鋼管のＣ几Ｄハウジング４に万一応力腐食割れ
が発生し炉水がリークした場合のことを想定し、リーク
を防止する装置を開発しておく必要がある。That is, a through hole is provided in the PVI, which is made of Inconel material or the like and has been overlaid and welded ID, and a cylindrical stub tube 2 that communicates with the hole IA is provided on the inner surface of this RPVI through the welded part 3. It is installed. stub tube 2
has a collar 21 at its tip, and a CR, D nozzle 4 passed through the stub tube 2 is attached to the tip of the stub tube 2 via a weld 5. The CR and D housings 4 of domestic conventional boiling water reactors use 5US304 series steel pipes.
High residual stress occurs in the nearby heat-affected zone, and a chromium-deficient layer forms along grain boundaries, resulting in a portion 5A highly susceptible to stress corrosion cracking. For this reason, 5US
In the unlikely event that stress corrosion cracking occurs in the C/D housing 4 of the 304 series steel pipe and reactor water leaks, it is necessary to develop a device to prevent leaks.
また、国内の沸騰水星原子炉のスタブチューブ２に耐Ｓ
ＣＣ材であるインコネル６００系の材料が使用されてい
る。In addition, the stub tube 2 of the boiling Mercury nuclear reactor in Japan is S-resistant.
Inconel 600 series material, which is a CC material, is used.
ＣＲＤハウジング４およびスタブチューブ２において万
一応力腐食割れが発生し炉水がリークした場合のリーク
防止法には、実開昭５６−８９９９２号公報によって公
知である既設のＣＲＤハウジング４およびスタブチュー
ブ２を新規の耐ＳＣＣ材によるＣＲＤハウジングおよび
スタブチューブに取替える恒久対策補修方法がある。こ
の方法で取替えられた後のＣＲＤハウジング、スタブチ
ューブの構造を第６図に示す。この方法によれば、Ｃ几
Ｄハウジング、スタブチューブは新規の耐ＳＣＣ材に取
替えられるので取替え後のものは信頼性が高いといえる
。一方、実開昭５６−８９９９２号公報に記載の補修方
法は、既設のＣ几Ｄ ／％ウジング４およびスタブチュ
ーブ２を切断しＲ，ＰＶ下鋭ＩＣの内面に新規のスタブ
チューブ６を溶接部７を介して取付ける構造となってい
る。この場合の溶接および既設スタブチューブの切断線
はＲＰＶ下鏡ＩＣの内面に沿った３次元の複雑な形状と
なり溶接および切断には、長時間を要し、補修作業に系
る作業員の放射線被曝の危険性があシ好ましくないと考
えられる。また、本補修作業を行う場合、自動溶接機、
切断加工機等の特殊装置の開発が必要となシ七の開発に
長時間を有すので、至急にリーク防止対策を行う必要が
生じた場合好ましくないと考えらるる。In the event that stress corrosion cracking occurs in the CRD housing 4 and stub tube 2 and reactor water leaks, a method for preventing leakage is to use the existing CRD housing 4 and stub tube 2, which are known from Japanese Utility Model Application Publication No. 56-89992. There is a permanent repair method that involves replacing the CRD housing and stub tube with new SCC-resistant materials. The structure of the CRD housing and stub tube after being replaced by this method is shown in FIG. According to this method, the C housing and the stub tube can be replaced with new SCC-resistant materials, so it can be said that the reliability of the replaced parts is high. On the other hand, the repair method described in Japanese Utility Model Application Publication No. 56-89992 involves cutting off the existing C/D/% housing 4 and stub tube 2, and welding a new stub tube 6 to the inner surface of the R, PV lower IC. The structure is such that it can be attached via 7. In this case, the welding and cutting line of the existing stub tube will be a three-dimensional complex shape that follows the inner surface of the RPV lower mirror IC, and welding and cutting will take a long time, and workers involved in repair work will be exposed to radiation. It is considered that there is a risk of this being undesirable. In addition, when performing main repair work, automatic welding machines,
Since it takes a long time to develop a system that requires the development of special equipment such as a cutting machine, it is considered undesirable if there is an urgent need to take measures to prevent leakage.
また、実開昭５６−８９９９２号公報によって公知であ
るＣ几りノ・ウジングおよびスタブチューブを取替える
恒久対策補修方法を行う場合使用するシール装置（一般
的にはケイソン工法として公知）については、公知であ
る。この公知の水シール装置のａＩ５造を第７図に示す
。第７図に示す様に、公知の水シール装置２２はＣＲＤ
／Ｓウジング４およびスタブチューブ２を補修する場合
作業者の被曝低減の観点よシ炉水有υの状態で補修を行
うことを可能にするための装置であシ補修対象となるＣ
ＲＤハウジングおよびスタブチューブを炉水から隔離す
るのに有効である。しかし、第７図に示す水シール装置
を据付けた状態で原子炉を運転することは出来ず、本水
シール装置により原子炉運転中のＣ几Ｄハウジングおよ
びスタブチューブからの炉水のリークを防止手段とする
ことはできない。Furthermore, the sealing device (generally known as the caisson method) used when carrying out the permanent repair method of replacing the C-hole housing and stub tube, which is known from Japanese Utility Model Application Publication No. 56-89992, is known in the art. It is. FIG. 7 shows an aI5 structure of this known water seal device. As shown in FIG. 7, a known water seal device 22 is a CRD.
/S When repairing the housing 4 and the stub tube 2, from the perspective of reducing radiation exposure for workers, it is a device that allows repairs to be carried out in the presence of reactor water.
Effective in isolating the RD housing and stub tube from reactor water. However, it is not possible to operate the reactor with the water seal device shown in Figure 7 installed, and this water seal device prevents leakage of reactor water from the C/D housing and stub tube during reactor operation. It cannot be used as a means.
以上のことよ、り、ＣＲＤハウジング、スタブチューブ
の補修作業に係る作業員の放射線被曝の観点より補修作
業が短時間に終了し、また、至急対策を行う必要が生じ
た場合のＣ几Ｄハウジング。Based on the above, from the viewpoint of radiation exposure of workers involved in repair work of CRD housing and stub tube, repair work can be completed in a short time, and if urgent measures need to be taken, CRD housing .
スタブチューブのリーダ対策補修用装置を開発しておく
必要がある。It is necessary to develop a stub tube leader repair device.
本発明の目的は、几ＰＶのＣＨＤハウジングのリーク防
止対策が至急にて短時間に行え、しかもリーク防止対策
を施したまま運転できるＣＲＤハウジングのリーク対策
補修装置を提供することにある。An object of the present invention is to provide a leak prevention repair device for a CRD housing that can quickly and quickly take measures to prevent leaks in a CHD housing of a PV and can be operated with the measures taken to prevent leaks.
本発明は、九Ｐｖの内側に固設されたスタブチューブ内
に前記ＲＰＶの壁を貫通して挿入され、前記スタブチュ
ーブと溶接されたＣ几りノ・ウジングにおいて、前記ス
タブチューブと前記ＣＲＤ／−ウジングの溶接部近傍で
前記Ｃ几りノ・ウジン、グに万が一応力腐食割れによシ
リークが発生した場合の防止法として前記Ｃ几Ｄハウジ
ングの外表面およびスタブチューブのツバ部上面の２箇
所でシールするような、支持構造物、前記支持構造物で
支′持された送り込み装置、および前記送り込み装置内
面、下面に設置されたシールリング体よシ構成されるメ
カニカルシール装置を取シ付け、リークを防止するよう
にしたものである。The present invention provides a C-hole housing that is inserted through the wall of the RPV into a stub tube fixedly installed inside the nine Pv and welded to the stub tube, in which the stub tube and the CRD/ - In the event that leakage occurs due to stress corrosion cracking in the C-hole D housing near the welded part of the housing, there are two locations on the outer surface of the C-hole D housing and the upper surface of the collar of the stub tube. a mechanical seal device consisting of a support structure, a feeding device supported by the support structure, and a seal ring body installed on the inner and lower surfaces of the feeding device; This is to prevent leaks.
以下、本発明の実施例を第１図〜第５図を参照して説明
する。Embodiments of the present invention will be described below with reference to FIGS. 1 to 5.
第５図は沸腸水型原子炉の几ｐｖｔ−示し、ＲＰＶｌは
ＲＰＶ胴体ＩＢ、ＲＰＶ下鏡ＩＣおよびＲＰＶ上蓋（図
示せず）から構成されている。Ｒ，Ｐ’ＶＩはスカート
８によって原子炉格納容器のペデスタル（図示せず）上
に固設されている。また、スタブチューブ２は前記Ｒ，
ＰＶ下鏡ＩＣに溶接部３よシ固設されている。一方、Ｃ
几Ｄハウジング４は溶接部５を介し、前記スタブチュー
ブ２に固設されている。FIG. 5 shows the structure of a boiling water reactor, and the RPV1 is composed of an RPV body IB, an RPV lower mirror IC, and an RPV upper cover (not shown). R and P'VI are fixedly installed on the pedestal (not shown) of the reactor containment vessel by a skirt 8. In addition, the stub tube 2 has the above-mentioned R,
It is fixed to the PV lower mirror IC at the welding part 3. On the other hand, C
The box D housing 4 is fixed to the stub tube 2 via a welded portion 5.
第５図は、Ｃ几Ｄ ／％ウジング４が溶接部５を介しス
タブチューブ２に、スタブチューブ２が溶接部３を介し
てＲＰＶ下鏡ＩＣに固設された状態を示す断面図であ’
ｔ 、ＲＰ Ｖ下鏡ＩＣの内面にはインコネルの肉盛Ｉ
Ｄが施されている。５人は、溶接５によって前記Ｃ几り
ノ翫つジング４に形成された敏鋭化領域である。FIG. 5 is a sectional view showing a state in which the housing 4 is fixed to the stub tube 2 via the welding part 5, and the stub tube 2 is fixed to the RPV lower mirror IC via the welding part 3.
t, RP V Inconel overlay I on the inner surface of the lower mirror IC
D is applied. 5 is a sensitized area formed in the C-shaped fitting 4 by welding 5.
第１図は本発明の一実施例によるＣ几Ｄ ／％ウジング
補修用メカニカルシール装置の断面図である。FIG. 1 is a cross-sectional view of a mechanical seal device for repairing a C/D/% housing according to an embodiment of the present invention.
メカニカルシール装置は、その下部が前記スタブチュー
ブ２０つば２１部と引っ掛かって取り合う様な内面カギ
形構造で、内面上部にはテーパねじ２４を切シ、さらに
外面には外周廻りに溝２３を設けた半割９円筒形状の支
持構造物９、外面上部に前記支持構造物９とかみ合う様
なテーパねじ２５を切９、内周面および下面にはシール
リング１１．１２を固設するための溝２６を設けた円筒
形状シールリング支持体１０、送り込み装置となる各テ
ーパねじ２４，２５、前記、半割シ円筒形状の各支持構
造物９をしめ付ける固定用バンド１３゜１４、および、
前記シールリング支持体１０に固設されたシールリング
ｌ １ 、４２とから成る。スタブチューブ２のつば２
１部上面およびＣ几りノ１ウジング４の外表面の２カ所
でシール部を形成し溶接部５近傍のＣ几Ｄ ）ｓウジフ
グ４の敏鋭化領域５人よυリークが発生した場合これら
のシール部によシ炉水のリークを防止する。炉水のリー
ク防止は、前記シールリング支持体１０を前記支持構造
物９にテーパねし２４．２５を噛み合せてねじ込むこと
により前記シールリング支持体１０に固設されたシール
リング１１．１２がテーパねじ２４．２５による傾斜方
向ねじ送り作用でスタブチューブ２のつば２１部上面お
よびＣＲＤハウジング４の外表面に圧着され、このこと
によシシールが行なわれる。The mechanical seal device has an inner hook-shaped structure in which the lower part thereof is caught and engaged with the stub tube 20 and the collar 21, and a tapered screw 24 is cut on the inner upper part, and a groove 23 is provided on the outer surface around the outer periphery. A half-split cylindrical support structure 9, a tapered screw 25 cut 9 on the upper outer surface to engage with the support structure 9, and grooves 26 on the inner peripheral surface and the lower surface for fixing seal rings 11 and 12. A cylindrical seal ring support 10 provided with a cylindrical seal ring support 10, each tapered screw 24, 25 serving as a feeding device, a fixing band 13° 14 for tightening each half-cylindrical support structure 9, and
The seal ring l 1 and 42 are fixedly attached to the seal ring support 10 . Stub tube 2 collar 2
A seal is formed at two places on the top surface of the first part and the outer surface of the C-ring 1 housing 4, and the C-ring near the welded part 5 is sensitized. The seal part prevents leakage of reactor water. To prevent leakage of reactor water, the seal ring support 10 is screwed into the support structure 9 by engaging the taper screws 24 and 25, so that the seal rings 11 and 12 fixed to the seal ring support 10 are tapered. The stub tube 2 is pressed against the upper surface of the collar 21 and the outer surface of the CRD housing 4 by the screw feeding action in the inclined direction by the screws 24 and 25, thereby performing a seal.
ｖＸ２図及び第３図に本発明の応用例によるＯＲ，Ｄハ
ウジング補修用メカニカルクール装置の断面図を示す。FIG.
第２図によるメカニカルシール装置は、一方を前記スタ
ブチューブ２のつば２１部下面に引っ掛け、他方を第１
シールリング支持体１０人下方に設けたつば１００部に
支持する万力機構の支持構造物１５、前記万力機構の支
持構造物１５に垂直に螺合したボルト１６、前記ボルト
１６を支持するつば１００部を設は下面にはシールリン
グ１１を固設するための溝２６を設は内面上部にはテー
パねじ２７を切った円筒形状の第１シールリング支持体
１０Ａ１外面上部に前記第１シールリング支持体１０Ａ
とかみ合う様なテーパねじ２８を切シ内面にはシールリ
ング１２を固設するための溝２６を設は上面にはボルト
用のネジ穴が設けられた円筒形状の第２シールリング支
持体１０Ｂ１前記第１．第２両シールリング支持体１０
Ａ、ＩＯＢ上面に設置されたシールリング１８．１９、
前記シールリング体１８．１９圧着用のリング状プレー
ト２０およびプレート２０を下方へ締め付ける埋め込み
ボルト１７によυ、スタブチューブ２のつば２１部上面
、Ｃ几Ｄハウジング４の外周面および第１．第２シール
リング支持体１０Ａ、ｌＯＢの上面の４カ所でシール部
を形成し溶接部５近傍のＣＲＤハウジング４の敏鋭化領
域５Ａよリリーフが発生した場合これらのシール部にょ
シ炉水のリークを防止する。炉水のリーク防止は、下記
の様にして行われる。The mechanical seal device shown in FIG.
A support structure 15 of the vise mechanism supported by the collar 100 provided below the seal ring support body, a bolt 16 screwed vertically to the support structure 15 of the vise mechanism, and a collar that supports the bolt 16. A cylindrical first seal ring support 10A1 has a groove 26 on the lower surface for fixing the seal ring 11 and a tapered thread 27 on the upper inner surface. Support body 10A
A groove 26 for fixing the seal ring 12 is cut on the inner surface of the second seal ring support 10B1, which has a cylindrical shape and has a threaded hole for a bolt on the upper surface. 1st. Second double seal ring support 10
A, Seal ring 18.19 installed on the top surface of IOB,
The ring-shaped plate 20 for crimping the seal ring body 18 and 19 and the embedded bolt 17 that tightens the plate 20 downward are attached to the upper surface of the collar 21 of the stub tube 2, the outer peripheral surface of the C-D housing 4, and the first. Seal parts are formed at four locations on the upper surface of the second seal ring support 10A and IOB, and if relief occurs from the sensitized area 5A of the CRD housing 4 near the welding part 5, leakage of reactor water will occur at these seal parts. prevent. Preventing reactor water leaks is carried out as follows.
前記ボルト１６を下方へねじ送りすることにより前記シ
ールリング１１が前記スタブチューブ２のつば２１部上
面に圧着され、前記第２シールリング支持体１０Ｂを前
記第２シールリング支持体１０ＡＫテーパねじ２７ｊ２
８を噛み合せてねじ込むことによシ第２シールリング支
持体１０Ｂを斜めに送ると、シールリング１２がＣＲＤ
ハウジング４に圧着され、さらに、埋め込みボルト１７
を締め付けることによジアールリング１８．１９が第１
．第２の各シールリング支持体１０Ａ。By threading the bolt 16 downward, the seal ring 11 is pressed onto the upper surface of the collar 21 of the stub tube 2, and the second seal ring support 10B is screwed into the second seal ring support 10AK with the taper screw 27j2.
When the second seal ring support body 10B is sent diagonally by engaging and screwing the seal ring 12 into the CRD
Crimp-bonded to the housing 4, and an embedded bolt 17
By tightening the ring 18.19, the first
．． Each second seal ring support 10A.
ｌＯＢ上面とプレート２０下面とに圧着されテーバねじ
２７．２８部からのリークをも防止している。テーバね
じ２７，２８からのリークがない場合はシールリング１
８．１９は不用である。It is crimped to the upper surface of the lOB and the lower surface of the plate 20, and also prevents leakage from the Taper screw 27 and 28 portions. If there is no leak from Taper screws 27 and 28, seal ring 1
8.19 is unnecessary.
第３図によるメカニカルシール装置は、一方を前記スタ
ブチューブ２のつば２１部下面に引っ掛け、他方を第１
．第２の各シールリング支持体１０Ａ、ＩＯＢ上で支持
する万力機構の支持構造物１５、前記万力機構の支持構
造物１５を締め付けるために支持構造物１５に垂直に螺
合したボルト１６、下部にシールリングを固設するため
の溝２６を設は内面上部には送り込み手段としてテーバ
ねじ２７が切った円筒形状の第１シールリング支持体１
０人、外面上部に前記第１シールリング支持体１０Ａと
かみ合う様なテーバねじ２８を送り込み手段として切シ
内面にはシールリングを固設するための９２６が設けら
れた円筒形状の第２シールリング支持体１０Ｂ、前記第
１．第２の各シールリング支持体１０Ａ、ＩＯＢに固設
されたシールリング４１，１２、前記第１．第２の各シ
ールリング支持体１０Ａ、ＩＯＢ上面に設置されたシー
ルリング１８，１９、前記シールリング体圧着用のリン
グ状プレート２０によシ、スタブチューブ２のつば２１
部上面、Ｃ几Ｄ ／Ｓウジング４の外周面および第１．
第２の各シールリング支持体１０Ａ、ＩＯＢ上面の４ケ
所でシール部を形成し溶接部５近傍のＣ几Ｄハウジング
の敏鋭化領域５Ａでリークが発生した場合これらのシー
ル部で炉水のリークを防止する。炉水のリーク防止は以
下の様にして行われる。前記第２シールリング支持体１
０Ｂを前記８ｇ１シ一ルリング支持体１０Ａに送り込み
装置としての両テーバねじ２７，２８を噛ませてねじ込
むことによジアールリング１２がＣＲＤハウジング４の
外周面に圧着され、さらに前記ボルト１６を締めること
によジアールリング１１はスタブチューブ２のつば２１
部上面に圧着されると同時にシールリング１８．１９が
送り込み装置１０Ａ、ＩＯＢ上面に圧着されリーク発
。The mechanical seal device shown in FIG.
．． a second seal ring support 10A, a support structure 15 of the vise mechanism supported on the IOB, a bolt 16 threaded vertically into the support structure 15 for tightening the support structure 15 of the vise mechanism; A cylindrical first seal ring support 1 is provided with a groove 26 for fixing the seal ring in its lower part, and has a taper screw 27 cut in its upper inner surface as a feeding means.
A cylindrical second seal ring having a tapered screw 28 on the upper outer surface thereof which engages with the first seal ring support 10A as feeding means, and a cylindrical second seal ring provided on the inner surface of the cutting edge with a hole 926 for fixing the seal ring. Support body 10B, the first. The second seal ring supports 10A, the seal rings 41 and 12 fixedly attached to the IOB, the first seal rings 41 and 12, and the first seal rings 41 and 12 fixedly attached to the IOB. The second seal ring support 10A, the seal rings 18 and 19 installed on the upper surface of the IOB, the ring-shaped plate 20 for pressing the seal ring body, and the collar 21 of the stub tube 2
upper surface, the outer circumferential surface of the C/S housing 4, and the first.
Sealing portions are formed at four locations on the second seal ring support 10A and the top surface of the IOB, and if a leak occurs in the sensitized area 5A of the C/D housing near the welding portion 5, these seal portions will allow the reactor water to leak. Prevent leaks. Preventing leakage of reactor water is done as follows. Said second seal ring support 1
0B is fed into the 8g1 seal ring support 10A, and by engaging and screwing both tapered screws 27 and 28 as devices, the ring ring 12 is crimped onto the outer peripheral surface of the CRD housing 4, and the bolt 16 is further tightened. In particular, the dial ring 11 is attached to the collar 21 of the stub tube 2.
At the same time, the seal rings 18 and 19 are crimped onto the top surface of the feeding device 10A and the IOB, causing leakage.
.
生を防止する。テーバねじ２７，２８の噛み合いによυ
リークが両テーパねじ２７．２８間を通して生じない場
合には、シールリング１８．１９は不用である。Prevent life. Due to the engagement of the Taper screws 27 and 28, υ
If no leakage occurs between the two tapered screws 27, 28, the sealing ring 18, 19 is not required.
以上の如く、本発明によれば、ＣＲＤノ・ウジングの全
体取替を要することなくリーク防止できるので至急のリ
ーク防止対策補修に有効である上に、全体を囲う従来の
水シール装置にくらべて小型で局部的なシールにてリー
クを防止するのでリーク防止した状態で運転することも
可能であシ又小型で取扱い容易であるのでリーク防止作
業も容易となる効果が得られる。As described above, according to the present invention, leakage can be prevented without requiring the entire CRD housing to be replaced, so it is effective for urgent leakage prevention measures and repairs, and is more effective than conventional water sealing devices that enclose the entire CRD housing. Since leakage is prevented by a small and localized seal, it is possible to operate the device in a leak-prevented state, and since it is small and easy to handle, leak prevention work is also facilitated.
第１図は本発明の実施例を示すメカニカルシール装置の
縦断面図、第２図、第３図は本発明の各応用例に基づく
メカニカルシール装置の縦断面図、第４図はＲＰｖ内の
Ｃ，ＲＤ ノ・ウジング近傍の縦断面図、第５図はＲＰ
Ｖ下鏡構造を示す縦断面図１、 第６図は、従来のＣＲ
Ｄ ノ・ウジフグ補修後の構造を示すＣＲＤハウジング
部の縦’１ｆｆｒ回図、第７図は、従来のシール装置で
ある水ミール装量を据付けたＲＰＶの縦断面図である。FIG. 1 is a vertical sectional view of a mechanical seal device showing an embodiment of the present invention, FIGS. 2 and 3 are vertical sectional views of a mechanical seal device based on each application example of the present invention, and FIG. 4 is a vertical sectional view of a mechanical seal device according to an embodiment of the present invention. C, RD Longitudinal cross-sectional view near No-Using, Figure 5 is RP
Vertical cross-sectional views 1 and 6 showing the structure of the V lower mirror are the conventional CR
FIG. 7 is a vertical cross-sectional view of the CRD housing section showing the structure after repair, and FIG. 7 is a vertical sectional view of the RPV in which a water meal charger, which is a conventional sealing device, is installed.
Claims (1)
を有するスタブチューブと、前記スタブチューブ内に通
されており前記突端部に溶着されたハウジングとを備え
た構造物において、前記つば下面に引っ掛けて設けた支
持構造物と、前記ハウジング廻りに配置して前記つば上
面上方に設置したシールリング支持体と、前記つば上面
と前記つば上面と対向する前記シールリング支持体部位
との間に前記ハウジング廻りに配置して設けた第１のシ
ールリングと、前記ハウジング廻りに配置されて前記ハ
ウジングと前記ハウジングの外周に対向する前記シール
リング支持体部位との間に設けた第２のシールリングと
、前記支持構造物と前記シールリング支持体との間を螺
合するテーパねじとから成る原子炉容器のハウジング部
リーク対策補修装置。 ２、原子炉圧力容器に取り付けられており突端部につば
を有するスタブチューブと、前記スタブチューブ内に通
されており前記突端部に溶着されたハウジングとを備え
た構造物において、前記つば下面に引っ掛けて設けた支
持構造物と、前記ハウジング廻りに配置して前記つば上
面上方に設置した第１シールリング支持体及び第２シー
ルリング支持体と、前記つば上面と前記つば上面と対向
する前記シールリング支持体部位との間に前記ハウジン
グ廻りに配置して設けた第１のシールリングと、前記ハ
ウジング廻りに配置されて前記ハウジングと前記ハウジ
ングの外周に対向する前記第２シールリング支持体部位
との間に設けた第２のシールリングと、前記支持構造物
と、前記第１と第２の両シールリング支持体とのすくな
くとも一方との間に送り方向を上下方向に向けて設けた
ねじと、前記第１と第２の両シールリング支持体間を螺
合するテーパねじとから成る原子炉容器のハウジング部
リーク対策補修装置。[Claims] 1. A structure that includes a stub tube that is attached to a reactor pressure vessel and has a flange on its tip end, and a housing that is passed through the stub tube and welded to the tip end. A support structure hooked onto the lower surface of the collar, a seal ring support disposed around the housing and above the upper surface of the collar, and the seal ring support facing the upper surface of the collar and the upper surface of the collar. a first seal ring disposed around the housing between the housing and the seal ring support body disposed around the housing and facing the housing and an outer periphery of the housing; A leak prevention repair device for a housing portion of a nuclear reactor vessel, comprising a second seal ring and a tapered screw threadedly engaged between the support structure and the seal ring support. 2. In a structure including a stub tube that is attached to a reactor pressure vessel and has a flange at its tip end, and a housing that is passed through the stub tube and welded to the tip end, the lower surface of the flange is a support structure provided by hooking; a first seal ring support and a second seal ring support disposed around the housing and above the upper surface of the collar; and the upper surface of the collar and the seal facing the upper surface of the collar. a first seal ring disposed around the housing between the ring support part; and a second seal ring support part disposed around the housing and facing the housing and an outer periphery of the housing. a second seal ring provided between the support structure and at least one of the first and second seal ring supports, a screw provided with the feed direction facing in the vertical direction; and a tapered screw threadedly engaged between the first and second seal ring supports.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59169360A JPS6147588A (en) | 1984-08-15 | 1984-08-15 | Leakage countermeasure repair device for housing section of nuclear reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59169360A JPS6147588A (en) | 1984-08-15 | 1984-08-15 | Leakage countermeasure repair device for housing section of nuclear reactor vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6147588A true JPS6147588A (en) | 1986-03-08 |
Family
ID=15885133
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59169360A Pending JPS6147588A (en) | 1984-08-15 | 1984-08-15 | Leakage countermeasure repair device for housing section of nuclear reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6147588A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0693753A1 (en) * | 1994-07-19 | 1996-01-24 | Jeumont Industrie | Method for implementing a leakproof connection means between a control rod drive mechanism and an adapter of a nuclear reactor, and corresponding connection means |
| JPWO2013150750A1 (en) * | 2012-04-03 | 2015-12-17 | 株式会社東芝 | Reactor pressure vessel penetration protection structure and reactor |
-
1984
- 1984-08-15 JP JP59169360A patent/JPS6147588A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0693753A1 (en) * | 1994-07-19 | 1996-01-24 | Jeumont Industrie | Method for implementing a leakproof connection means between a control rod drive mechanism and an adapter of a nuclear reactor, and corresponding connection means |
| FR2722908A1 (en) * | 1994-07-19 | 1996-01-26 | Jeumont Industrie | METHOD FOR PRODUCING A SEAL BETWEEN A CONTROL CLUSTER MECHANISM AND A NUCLEAR REACTOR ADAPTER, AND CORRESPONDING SEAL |
| JPWO2013150750A1 (en) * | 2012-04-03 | 2015-12-17 | 株式会社東芝 | Reactor pressure vessel penetration protection structure and reactor |
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