JPS59112287A - Water seal plug device of reactor vessel - Google Patents

Water seal plug device of reactor vessel

Info

Publication number
JPS59112287A
JPS59112287A JP57222097A JP22209782A JPS59112287A JP S59112287 A JPS59112287 A JP S59112287A JP 57222097 A JP57222097 A JP 57222097A JP 22209782 A JP22209782 A JP 22209782A JP S59112287 A JPS59112287 A JP S59112287A
Authority
JP
Japan
Prior art keywords
reactor vessel
water
watertight lid
lid
watertight
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
JP57222097A
Other languages
Japanese (ja)
Other versions
JPS6325317B2 (en
Inventor
長野 恒己
孝 西岡
将人 飯田
井島 文雄
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP57222097A priority Critical patent/JPS59112287A/en
Priority to FR8320288A priority patent/FR2538152B1/en
Publication of JPS59112287A publication Critical patent/JPS59112287A/en
Publication of JPS6325317B2 publication Critical patent/JPS6325317B2/ja
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/06Sealing-plugs
    • G21C13/073Closures for reactor-vessels, e.g. rotatable
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Pressure Vessels And Lids Thereof (AREA)
  • 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】 本発明は原子炉容器の水密蓋装置に関するものである。[Detailed description of the invention] The present invention relates to a watertight lid device for a nuclear reactor vessel.

原子カプラントでは、法律で義務づけられている年1回
の定期検査時に、−次冷却水を抜いて、保守、点検を行
なうが、従来行なわれている保守、点検作業を第1図に
より説明すると、(1)がキャビティ、(2)が原子炉
容器蓋、(3)が原子炉容器、(4)が低温側配管、(
5)が−次冷却水循環ポンプ、(6)がクロスオーバレ
グ配管、(力が蒸気発生器、(8)が高温側配管、(9
)が−次冷却水注入ライン、(10)が−次冷却水ドレ
ンライン、(111が上部炉心支持構造物、(+21が
原子炉容器(3)内に残留した一次冷却水、(13)が
ベントラインで、原子カプラントの運転中、原子炉容器
(3)低温側配管(4)−次冷ノJ水循環・Pンプ(5
)クロスオーバレグ配管(6)蒸気発生器(力高温側配
管(8)内には一次冷力J水か充満している。通常上記
要素(4)(506B7)(8)の系統をループと呼び
、この系統の一次冷却水をループ水と呼んでいる。保守
、点検時には、原子カプラントの、11転を停止して、
ループ水を空にする。次いで空気を原子炉容器蓋(2)
の部分から原子炉容器(3)へ送って、ループ水を一次
冷却水ト9レンライン00)から完全にトゝレンする。
At nuclear couplers, during annual periodic inspections required by law, sub-cooling water is drained for maintenance and inspection.The conventional maintenance and inspection work is explained using Figure 1. (1) is the cavity, (2) is the reactor vessel lid, (3) is the reactor vessel, (4) is the low temperature side piping, (
5) is the secondary cooling water circulation pump, (6) is the crossover leg piping, (power is the steam generator, (8) is the high temperature side piping, (9)
) is the secondary cooling water injection line, (10) is the secondary cooling water drain line, (111 is the upper core support structure, (+21 is the primary cooling water remaining in the reactor vessel (3), (13) is At the vent line, during operation of the nuclear coupler, reactor vessel (3) low temperature side piping (4) - next cooling J water circulation/P pump (5)
) Crossover leg piping (6) Steam generator (The high temperature side piping (8) is filled with primary cooling water. Normally, the system of the above elements (4) (506B7) (8) is looped. The primary cooling water of this system is called loop water.During maintenance and inspection, the 11th turn of the nuclear coupler is stopped and
Empty the loop water. Then the air is poured into the reactor vessel lid (2)
The loop water is completely drained from the primary cooling water drain line 00) by sending it to the reactor vessel (3).

このとき、−次冷却水はα2の部分だけに残る。この状
態になったら、ループの保守、点検を行ない、またルー
プの保守、点検が終ったら、キャビティ(1)に遮蔽水
を法り、原子蓋容器蓋(2)を取り外し、上部炉心支持
構造物(111をキャビティ(1)内に取り出して上部
炉心支持構造物fillの保守、点検を行なうようにし
ていた。
At this time, the -order cooling water remains only in the portion α2. In this state, perform maintenance and inspection of the loop. After completing maintenance and inspection of the loop, pour shielding water into the cavity (1), remove the nuclear cap vessel lid (2), and remove the upper core support structure. (111 was taken out into the cavity (1) to perform maintenance and inspection of the upper core support structure fill.

従来は前記のように、ループの保守、点検が終ると上部
炉心支持構造物(1,1+の保守、点検に移るというよ
うに両者の保守、点検な1lil:i次行なっていたの
で、原子カプラントの停止期間を長びかせるという問題
があった。
Conventionally, as mentioned above, once the maintenance and inspection of the loop was completed, the maintenance and inspection of the upper core support structure (1, 1+) was carried out. There was a problem in that the outage period was prolonged.

本発明は前記の問題点に対処するもので、IU子炉容器
の内部をキャビティに源った遮蔽水から一時的に隔離す
る水蜜蓋と、原子炉容器側の部材の上端面に立設した水
密蓋用ガイドピンと、原子炉容器の上部フランジ面の内
11111に形成したシール面と対向するように上記水
蜜蓋に設けた二重の環状蟻溝と、同各環状蟻溝に嵌装し
たシールリングと上記水密蓋に設けた空気抜管と、上記
各シールリング間の封止空間に連通ずるように上記水密
蓋に設けた水位管とを具えていることを特徴とした原子
炉容器の水密蓋装置に係り、その目的とする処は、ルー
プと上部炉心支持構造物との保守、点検を同時に行なう
ことかできて、)9子カプラントの停止期間を短縮でき
る原子炉容器の水密蓋装置を供する点にある。
The present invention addresses the above-mentioned problems, and includes a water cover that temporarily isolates the inside of the IU reactor vessel from the shielding water sourced from the cavity, and a water cover that is installed upright on the upper end surface of the member on the reactor vessel side. A guide pin for the watertight lid, a double annular dovetail groove provided in the watertight lid so as to face the sealing surface formed on the inside 11111 of the upper flange surface of the reactor vessel, and a seal fitted in each of the annular dovetail grooves. A watertight lid for a nuclear reactor vessel, comprising a ring, an air vent pipe provided in the watertight lid, and a water level pipe provided in the watertight lid so as to communicate with the sealed space between each of the seal rings. Regarding the equipment, its purpose is to provide a watertight lid system for the reactor vessel that can shorten the outage period of the nine-child couplant by allowing simultaneous maintenance and inspection of the loop and the upper core support structure. At the point.

次に本発明の原子炉容器の水密蓋装置を第2図乃至第1
0図に示す一実施例により説明すると、(1)(3)〜
fl 0)(121が前記と同一の部分、第2.4.6
.9.10国のC5)かキー)クビテイ(1)に漁った
遮蔽水、第4.6図の(1b)か原子炉容器(3)とキ
ャビティ(遮蔽壁)(I)との間を閉じるシールリング
、第6.4.6.7.8.9図の(1’71か原子炉容
器(3)の上部フランジ面、(1鈎が同フランジ面理J
の内側に形JRしたシール面で、坤子炉容器盈(第1図
の(2)参照)を皿はね状のシール部拐(図示せず)を
介して取付けるようになっている。また第6.4.6図
の(19)がボルトタップ穴、0υ)か同ボルトタップ
穴0」により立設した原子炉容器蓋のガイド8スタツド
、第4゜6図のQl+が下部炉心支持構造物(炉心槽)
、C2l+が同下部炉心支持構造物(2υの上端面に立
設した水密蓋(27)のガイドピン、(231がリフテ
ィング装置本体、(24]がねじ込み棒、(25]が同
ねじ込み棒(241のねじ部、(261がガイド9スク
ツドならい機41:、(0)が原子炉容器(3)の中心
線で、シールリング(161と原子炉容器(3)の上部
フランジ面(17)とシール面08)と下部炉心支持構
造物(2DとVtそれぞれの中心が原子炉容器(3)の
中心線(01上にある。またボルトタップ穴(11も上
記中心線(0)を中心とした円心円上に等リンチで設け
られているが、第6図ではその一部のみを示している。
Next, the watertight lid device for the reactor vessel of the present invention is shown in FIGS. 2 to 1.
To explain with an example shown in Figure 0, (1) (3) ~
fl 0) (121 is the same part as above, Section 2.4.6
.. 9.10 country's C5) or key) Shielding water caught in the cavity (1), closing between (1b) or the reactor vessel (3) and the cavity (shielding wall) (I) in Figure 4.6 Seal ring, Fig. 6.4.6.7.8.9 (1'71) or upper flange surface of reactor vessel (3), (1 hook is the same flange surface J
The inner surface of the container has a JR-shaped sealing surface, and the container canister (see (2) in FIG. 1) is attached through a countersunk-shaped sealing part (not shown). In addition, (19) in Figure 6.4.6 is the bolt tap hole, 0υ) or 0'' is the guide 8 stud of the reactor vessel lid, and Ql+ in Figure 4゜6 is the lower core support. Structure (core tank)
, C2l+ is the guide pin of the watertight lid (27) installed on the upper end surface of the lower core support structure (2υ), (231 is the lifting device main body, (24) is the threaded rod, (25) is the threaded rod (241) (261 is the guide 9 scud profiler 41:, (0) is the center line of the reactor vessel (3), and the seal ring (161) and the upper flange surface (17) of the reactor vessel (3) and the seal The centers of the plane 08) and the lower core support structure (2D and Vt are on the center line (01) of the reactor vessel (3). The bolt tap holes (11 are also located on the circle centered on the center line (0) above). Although they are arranged in a uniform manner on the central circle, only a part of them is shown in Fig. 6.

またシールリング(1G)は上記のように原子炉容器(
3)とキャビティ(1)との[(11を閉じる1、二め
のもので、水密構造になっている。またシール面(18
1はシールtと適するように樟徐された面で、幅はそう
広くない。
In addition, the seal ring (1G) is attached to the reactor vessel (
3) and the cavity (1) [(11) is closed and has a watertight structure.
1 is a surface that has been polished to match the seal T, and its width is not very wide.

またガイドスタットゝ(2i1!はボルトタップ穴01
υにねじ込んだり、取り外すことかできる。またねじ込
み棒t24)を遮蔽水α9の水面よりも上方位置で回転
し、ねじ部□□□を上部炉心支持構造物(第1図の(l
il +D照)のねじ穴にねじ込んで、リフティング装
置本体(滴を矢印下方向に吊り上げると、下部炉心支持
441造物を原子炉容器(3)内から、取り出すことが
できる、このとき、ガイドスタット9ならい機構(Jt
i+がガイドスタット(訛によりガイドされるので、下
部炉心支持構造物を真直ぐに吊り上げたり、吊り下げる
ことができろ。次に本水密蓋装置の最も特徴とする点を
説明すると、第5.6.7.8,9.10図の07)が
水蜜蓋、(28)がリフティング用ボス、Q!I)が同
ボス□□□を水密蓋(2ηに取付けるポル) 、 C3
0)がガイドピンアクセス部、(311が主ベントライ
ン、C32+が補助ベントライン、C33)がQ IJ
ング間イベントび水位監視ライン、(34)がワッシャ
、(3暖が雌ねじ、(36)かタップねじ穴、Oηがド
レン穴、(38)か外側Oリング、(39)が内側Q 
IJソング(40)が外側0リング溝、(4υが内側O
リング溝、(42)が透明材製ホース、(4jが浮き1
、・(4力が漏洩監視用水で、第5,6図に示す水蜜M
(27)は円板状で、キャビティ(1)に池った遮蔽水
に耐える強度をもっている。なお同水密蓋(27)は半
球状、皿状等であってもよい。また主ベントラインC3
υと補助ベントライン(321とOリング間ベント及び
水位監視ラインc331とは線で描いている管状で、下
端は水密&(2力に水密性をもたせて取付け、上端は遮
蔽水(I5)の水面よりも上方に出ている。またガイド
ピンアクセス部(至)は水密蓋(5)をシール面([8
1上に載置したときガイ)″ビン圏と干渉しない奥行き
をもっている。またリフティング用ボス(2)はポルト
c!(ト)を介して水蜜蓋(27)に固定され、同ボス
(281の雌ねじ051が前記ねじ込み棒(2)のねじ
部(25)と繰合可能である。また上記ポルト(2ωの
直径(D2)と同ボルト翰が馴合するポルト穴の直径(
Dよ)とは、D、>D2で、ボス(281の水密蓋(2
ηに対する取り付は位置を微妙に調整でき7.)。また
ポルト(29)を水密蓋0Dにねじ込んだと雪、締伺力
を安定させるようにワッシャ(34)を通常よりも厚め
にしている。またドレン穴り3徂まねじ部(25)の雌
ねじ09へのねじ込みを容易にするためにボス(’、!
81に、iツけた水抜き穴である。また0リング(38
1C39+は中実のゴム製で、同各OIIソング38)
091は自重だけでもQ IJソング溝40(41)及
びシール面0榎に接触可能である。なお0リングを二重
に設けたのは、シールをより確実にするためである。ま
たOリング溝(4(1(411は蟻ice状で、0リン
グ関0Iの挿入は容易だが、離規は簡単にできないよう
罠なっている。またOリング間ベント及び水位監視ライ
ン(至)及びホース(42)は011ング(38)Cl
I間の封止空間を大気に通じさせるもので、可撓性を有
し、それぞれの下端が水密蓋C71に水密性をもたせて
取り付けられている。水密蓋(2ηをシール面0印上に
載置したのち、ホース(42)の上方からホース(42
)内へスポイト等を挿入し、ホース(421内の水位を
調整して、同水位をキャビティ(1)内に細った遮蔽水
θ5の水位よりも若干低めにし、次いで浮き+43をホ
ース(421内へ挿入する。ホース(421は透明拐製
で、浮き(431をホース(42)外から目視できる。
Also, the guide stud (2i1! is the bolt tap hole 01
It can be screwed into υ or removed. Also, rotate the threaded rod t24) at a position above the water surface of the shielding water α9, and connect the threaded part □□□ to the upper core support structure ((l) in Figure 1.
The lower core support 441 structure can be taken out from the reactor vessel (3) by screwing it into the screw hole of the lifting device main body (droplet in the downward direction of the arrow). Tracing mechanism (Jt
Since the i+ is guided by a guide stat, the lower core support structure can be lifted or hung straight.Next, the most distinctive feature of this watertight lid device is explained in Section 5.6. .7.8, 9.10 Figure 07) is the water bottle lid, (28) is the lifting boss, and Q! I) is the same boss □□□ with a watertight lid (port attached to 2η), C3
0) is the guide pin access part, (311 is the main vent line, C32+ is the auxiliary vent line, C33) is the Q IJ
(34) is the washer, (3) is the female thread, (36) is the tapped screw hole, Oη is the drain hole, (38) is the outer O-ring, (39) is the inner Q
IJ song (40) is the outer O ring groove, (4υ is the inner O ring groove)
Ring groove, (42) is transparent material hose, (4j is float 1
,・(4 forces are water for leakage monitoring, water leakage M shown in Figures 5 and 6)
(27) is disc-shaped and has the strength to withstand the shielding water that has accumulated in the cavity (1). Note that the watertight lid (27) may be hemispherical, dish-shaped, or the like. Also main vent line C3
υ and the auxiliary vent line (321 and the O-ring vent and water level monitoring line c331 are tubular shapes drawn with lines, and the lower end is installed with watertightness in both directions, and the upper end is the shielding water (I5) It protrudes above the water surface.The guide pin access part (to) connects the watertight lid (5) to the sealing surface ([8
The lifting boss (2) has a depth that does not interfere with the area of the bottle when placed on top of the lid (27). The female thread 051 can fit with the threaded portion (25) of the threaded rod (2). Also, the diameter (D2) of the port (2ω) and the diameter (D2) of the port hole into which the bolt holder fits (
D) is D, > D2, and the boss (281 watertight lid (2
7. The mounting position for η can be adjusted slightly. ). Also, when the Porto (29) is screwed into the watertight lid 0D, the washer (34) is made thicker than usual to stabilize the clamping force. In addition, a boss (', !
At 81, there is a drain hole. Also 0 ring (38
1C39+ is made of solid rubber, and each OII song 38)
091 can contact the QIJ song groove 40 (41) and the seal surface 0 even with its own weight alone. The purpose of providing double O-rings is to make the seal more reliable. In addition, the O-ring groove (4 (1 (411) is dovetail-shaped, and it is easy to insert the O-ring 0I, but it is a trap so that it cannot be easily removed. There is also a vent between the O-rings and a water level monitoring line (towards). and the hose (42) is 011 (38) Cl
It allows the sealed space between I to communicate with the atmosphere, and is flexible, and the lower end of each is attached to the watertight lid C71 in a watertight manner. After placing the watertight lid (2η) on the seal surface 0 mark, insert the hose (42) from above the hose (42).
), adjust the water level in the hose (421) to make it slightly lower than the water level of the thin shielding water θ5 in the cavity (1), and then insert the float +43 into the hose (421). The hose (421) is made of transparent material, and the float (431) can be visually seen from outside the hose (42).

なお浮き(431は螢ツ0塗料を塗布した発泡スチロー
ル製のものがiR−当である。また第10図の(451
が一次冷却水ドレンライン(101へ延びた仮設水位監
視ラインで透明材製のホースである。
Note that the float (431 is made of styrofoam coated with firewood 0 paint is iR-1).
The primary cooling water drain line (temporary water level monitoring line extending to 101 is a hose made of transparent material).

次に前記原子炉容器の水蜜差装置の作用を説明する。(
I+  原子炉容器蓋(第1図の(2)参照)を取り外
し、上部炉心支持構造物(第1図の(珪参照)も原子炉
容器(3)から取り出して、キャビティ(1)内に遮蔽
水(151を渋る。fIII  大気中でねじ込み棒(
24)のねじ部(25)をボス(ハ)の雌ねじ(2)に
ねじ込んで、リフティング装置本体(23)と水蜜蓋0
′7)とを一体にし、次いでリフティング装置本体(2
(至)を下降させて、水密蓋Qηをシール面081の上
に載置する。C11N  −次冷却水ト8レンライン<
101からループ水をト9レンし、原子炉容器(3)内
が残留−次冷JdJ水(!2)だけ1心なったら、−次
冷却水ドレンライン(1@のバルブを締める。
Next, the operation of the reactor vessel water difference device will be explained. (
I+ The reactor vessel lid (see (2) in Figure 1) is removed, the upper core support structure (see (2) in Figure 1) is also taken out from the reactor vessel (3), and it is shielded in the cavity (1). Water (reluctant to 151. fIII Threaded rod in the atmosphere (
Screw the threaded part (25) of 24) into the female thread (2) of the boss (c) to connect the lifting device body (23) and the water bottle cover 0.
'7) and then the lifting device body (2
(to) is lowered and the watertight lid Qη is placed on the sealing surface 081. C11N - Next cooling water train 8 line <
Drain the loop water from 101, and when the inside of the reactor vessel (3) is filled with only 1 core of residual cold JdJ water (!2), close the valve of the cold water drain line (1@).

OM  ループの保守、点検と上部炉心支持構造物の保
守、点検とを1i・1時に行なり。Mこのと勾、遮蔽水
09の水深は13 I11程度あり、しかもシール面0
8)は幅が非常に狭く、ここに当て傷を生じさせたりす
ると、漏水する惧れあ4)。そのためには水密蓋(靭を
シール面(18iK精度よく載置させなけれはならない
。この作業は8nL程度の水深を通して行なうので、特
別の配慮かJy?萼になろ。また水密蓋(2γ)にはベ
ントラインも必要にな4)。さらに安全性の面から、水
密蓋0ηとシール面θ〜との接合部に漏水のないことを
確認しなければならない。本発明では上記の点にも対処
している。(四Il!+4ち、上述のように水密蓋(2
′0をシール面(181の上に載置するとき、水密蓋I
2ηをシール面(181の上にiil#度よく載置しな
いと互の間から漏水したり、シール面(ilGを損傷し
たりする倶れがあるが、リフティング装置本体(ハ)と
水密1(27+との結合体の下降なガイドスタッドイド
8スタツト9ならい機構(イ)とでガイrしており、水
密蓋(27)をシール面(18)に精度よく載置できる
。またこのとき、水密蓋(2つのねじ込み棒(241に
対する取り付は位置が悪くて,水密蓋(2ηかフランジ
面(17)に乗り上げろようなことがあれば、水密性を
確保できないが、ボス(28)の水密蓋(21に対する
取り付は位置を微調整することか可能で、この事態も防
止できる。(〜41)  ループ水を抜き取るとき、原
子炉容器(3)内の空気をベントしなければならないが
、これは主ベントライン(3j)メ補助ベントラインC
’i2+を使用[2て行なうことができろ。また主ベン
トライン(31Jを燕蔽水(]5)の中に浸漬すると、
辺!;蔽水(I5)が主ベントライン6Bを経て原子炉
容器(3)内へ入り、原子炉容器(3)内の空気が補助
ベントラインG2を経て大気中へ出るので、原子炉容器
(3)内の水深りを容易に行なえる。なおこのような原
子炉容器(3)内を水深り状態にするのは、水蜜蓋Q7
)を吊り上げるとき遮蔽水(15)の水頭を水密蓋(2
7)にかげないようにして水密蓋(9)の吊り上げを容
易にするためである。
Maintenance and inspection of the OM loop and the upper core support structure were performed at 1i/1:00. The depth of the shielding water 09 is about 13 I11, and the sealing surface is 0.
8) is very narrow, and if a scratch is caused here, there is a risk of water leakage 4). In order to do this, the watertight lid (2γ) must be placed on the sealing surface (18iK) with high accuracy.This work is done through a water depth of about 8nL, so special consideration must be given to the calyx.Also, the watertight lid (2γ) A vent line is also required4).Furthermore, from the standpoint of safety, it must be confirmed that there is no water leakage at the joint between the watertight lid 0η and the sealing surface θ~.The present invention also addresses the above points. (4Il!+4chi, as mentioned above, the watertight lid (2
'0 on the sealing surface (181), the watertight lid I
If the 2η is not placed well on the sealing surface (181), water may leak from between them or damage the sealing surface (ilG), but the lifting device body (c) and the watertight 1 ( 27+ is connected to the descending guide stud id 8 stud 9 profiling mechanism (a), so that the watertight lid (27) can be placed on the sealing surface (18) with high precision. If the two threaded rods (241) are installed in the wrong position, and the watertight lid (2η) rides on the flange surface (17), watertightness cannot be ensured, but the watertightness of the boss (28) It is possible to attach the lid (21) by slightly adjusting its position, and this situation can also be prevented. (~41) When removing the loop water, the air inside the reactor vessel (3) must be vented, but This is the main vent line (3j) and the auxiliary vent line C.
'Use i2+ [2 can be done. Also, when the main vent line (31J) is immersed in Yanbai water (]5),
Side! ; The water (I5) enters the reactor vessel (3) through the main vent line 6B, and the air inside the reactor vessel (3) exits to the atmosphere through the auxiliary vent line G2. ) can be easily accessed. It should be noted that the water inside the reactor vessel (3) is brought into a water-deep state by using the water cover Q7.
) when lifting the watertight lid (2), the water head of the shielding water (15)
7) This is to make it easier to lift the watertight lid (9) so as not to overshadow it.

(vlII)0リング(2)(3鋳からの漏水の有無を
次の要領で監視する。もしOリング(至)のシール性が
害なわれ−(いると、Oリング間ベント及び水位監視ラ
イン(至)の漏洩監視用水(A4)の水位が遮蔽水(+
51の水位と同じになる。浮き(431は漏洩監視用水
(44)の水位を示すから、浮き(431を見れば、0
リング(2)のシール性が害なわれているか否かが判る
。またO ljソング39)のシール性が害なわれてい
ると、漏洩監視用水(44)の水位が下がる。このとき
にも浮き(43を見れば0リング(3ωのシール性が害
なわれているか否かが判る。通常、0リングC38)(
3→のシール性が同時に害なわれることはなく、どちら
かの洩れを検知すれば漏水防止の対策を構じることにな
る。また漏水状況は仮設水位監視ライン(4暖によって
も監視できる。
(vlII) Monitor the presence or absence of water leakage from the O-rings (2) (3) as follows. If the sealing performance of the O-rings (to) is impaired, use the vent between the O-rings and the water level monitoring line. (To) The water level of the leak monitoring water (A4) is the shielding water (+
It will be the same as the water level of 51. The float (431) indicates the water level of the leak monitoring water (44), so if you look at the float (431), it will be 0.
It can be determined whether the sealing performance of the ring (2) is impaired. Furthermore, if the sealing performance of the oil song 39) is impaired, the water level of the leakage monitoring water (44) will drop. At this time, you can tell whether the sealing performance of the 0 ring (3ω is impaired or not by looking at the float (43). Usually, the 0 ring C38) (
The sealing performance of 3→ will not be impaired at the same time, and if leakage from either is detected, measures will be taken to prevent water leakage. Water leakage conditions can also be monitored using a temporary water level monitoring line (4-tan).

(IX)  Oリング(へ)備は蟻溝状のOリング溝(
41Jl(41)に嵌装されているので、水蜜蓋C!η
を吊り下げる途中の段階でも抜は出ることがない。また
水密蓋G2ηを吊り上げようとするとき、Oリング間ベ
ント及び水位監視ラインC畑及びホース(4カがなけれ
ば、0リング(至)091間の封止空間は、吸盤のよう
に一時的に負圧になって、0リング(至)(至)がOリ
ング溝(4[)(41)かも離脱し易くなり、もし離脱
すれば遮蔽水(151の上方から別の工具でOリング0
2◇儲を拾わなければならなくて、作業時1シlを長く
するか、Oリング間バンド及び水位監視ライン(ハ)及
びホース(42は大気に通じており、さらにその内部に
は漏洩監視用水(44)が入っているので、水密蓋(2
ηを吊り上げようとするとき、Q IJングク燭09間
の封止空間が一時的に負圧にならなくて、0リング(3
咄■のOリング溝(40(41jからの離脱を防止でき
る。
(IX) The O-ring has a dovetail-shaped O-ring groove (
Since it is fitted to 41Jl (41), the water bottle lid C! η
Even in the middle of hanging it, it never comes out. Also, when trying to lift the watertight lid G2η, if there is no vent between the O-rings, the water level monitoring line C field, and the hose (4), the sealed space between the O-rings (to) 091 will temporarily close like a suction cup. When the pressure becomes negative, the O-ring (To) (To) and the O-ring groove (4[) (41) will also come off easily. If it comes off, remove the O-ring from above the shielding water (151) using another tool.
2◇If you have to make a profit, you should either lengthen the band by 1 sill during work, or use the band between the O-rings, the water level monitoring line (c), and the hose (42 is connected to the atmosphere, and inside it there is a leak monitoring line. Since it contains water (44), close the watertight lid (2).
When trying to lift η, the sealed space between Q IJ ring candle 09 temporarily did not become negative pressure
O-ring groove (40 (41j) can be prevented from coming off.

本発明の原子炉容器の水密蓋装置は前記作用のTII乃
至(IV)項で説明したように原子炉容器蓋を取り外し
、上部炉心支持構造物も原子炉容器から取り出して、キ
ャビティ内に甥蔽水を法り、次いで水密蓋をリフティン
グ装置により下降させて、下部炉心支持構造物の上端の
シール面上に載置し、次いで原子炉容器内を残留−次冷
却水だけにすることかできるので、ループと上部炉心構
造物との保守、点検を同時に行なうことができて、原子
カプラントの停止期間を短縮できる。また前記作用の(
V)乃至(IX)項で説明したように水密蓋のシール面
への載置、シールリングにヨルシール、シールリングの
保持などを確実に行なうことができるので、ループの保
守、点検を安全に、円滑に実施できる効果がある。
In the reactor vessel watertight lid device of the present invention, as explained in sections TII to (IV) of the above operation, the reactor vessel lid is removed, the upper core support structure is also taken out from the reactor vessel, and the upper core support structure is installed in the cavity. After draining the water, the watertight lid is lowered using a lifting device and placed on the sealing surface at the upper end of the lower core support structure, leaving only residual secondary cooling water in the reactor vessel. , maintenance and inspection of the loop and the upper core structure can be performed simultaneously, and the shutdown period of the nuclear couplant can be shortened. Also, the above action (
As explained in sections V) to (IX), it is possible to securely place the watertight lid on the sealing surface, place a seal on the seal ring, and hold the seal ring, so maintenance and inspection of the loop can be done safely. This has the effect of facilitating smooth implementation.

以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものではなく、本発
明の精神を逸脱しない範囲内で種々の設計の改変を施し
うるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .

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

第1図は従来の原子カプラントを示す説明図、第2図は
本発明に係る原子力容器の水蜜蓋装置の一実施例の概略
を示す縦断側面図、第6図はその要部を拡大して示す平
面図、第4図は第2図矢印■部分を拡大して示す縦断側
面図、第5図は水蜜蓋の拡大平面図、第6図はその縦断
側面図、第7図は水密蓋のリフティング用ボス部分の拡
大平面図、第8図は第7図矢視till−■線に沿う縦
断側面図、第9図は空気抜管部分の縦断側面図、第1゜
図は全体の系統図である、 (1)・・・キャビティ、(3)・・・原子炉容器、a
η・・・フランジ面、(!帽・・シール面、(2I)・
・・原子炉容器(3)側の部材、@・・・ガイド9ビン
、(21・・・水密蓋、C311C!:、D・・・空気
抜管、(3:31(42)・・・水位管、(:灼Oト・
シールリング、(40)(41)・・・環状蟻溝。 後代理人弁理士 岡 本 重 文 外2名 第2図 第3図 第5図 第7図 第8図 第9図 手続補正書 昭和58年1 月24日 特許庁長官  若 杉 和 夫  殿 1、事件の表示 昭和57年特 許 願第222097号2、発明の名称
 原子炉容器の水密蓋装置3、補正をする者 事例との関係  特     許出願人名 称(620
)三菱重工業株式会社 4、復代理人 5、補正命令のl]付  昭和(1年″” ’J−] 
  [1手続補正書 11i’(和58年12月8 日 特許庁長官  若 杉 和 夫  殿 1、事件の表示 昭和57年特 許 願第222097号2、発明の名称
 原子炉容器の水密蓋装置3、補正をする者 事件との関係  1.1      許出願人名 称(
620)三菱重工業株式会社 4、復代理人 5、補正命令の1=1伺  昭和(1年4力  日(発
送1」)6、補正の対象 明細書 7、補正の内容 明細書中 第12頁第16行乃至第17行の「下部炉心支持構造物
」を「原子炉容器に」に補正します。 手続補正書 昭和58年】2月12 日 特許庁長官  若 杉 和 夫  殿 1、事件の表示 昭和57年特 許 願第222097号2、発明の名称
 原子炉容器の水密蓋装置3、補正をする者 事f1との関係  特     、許出願人名 称(6
20)三菱重工業株式会社 4、復代理人 5、補正命令の日付  昭和(百年1力   日(発送
日)6、補正の対象 明細″:!1 7、補正の内容 明細書中 第12頁第16行乃至第17行の「下部炉心支持構造物
」を「原子炉容器」に補正します。
Fig. 1 is an explanatory diagram showing a conventional atomic couplant, Fig. 2 is a longitudinal side view schematically showing an embodiment of a water cap device for a nuclear vessel according to the present invention, and Fig. 6 is an enlarged view of the main parts. Fig. 4 is an enlarged longitudinal sectional side view of the arrow ■ part in Fig. 2, Fig. 5 is an enlarged plan view of the watertight lid, Fig. 6 is a longitudinal sectional side view thereof, and Fig. 7 is a longitudinal sectional side view of the watertight lid. Fig. 8 is an enlarged plan view of the lifting boss portion, Fig. 8 is a vertical cross-sectional side view taken along the arrow till-■ line in Fig. 7, Fig. 9 is a longitudinal cross-sectional side view of the air vent pipe portion, and Fig. 1 is an overall system diagram. Yes, (1)...cavity, (3)...reactor vessel, a
η...Flange surface, (!Cap...Seal surface, (2I)...
...Reactor vessel (3) side parts, @...Guide 9 bottle, (21...Watertight lid, C311C!:, D...Air vent pipe, (3:31 (42)...Water level Tube, (: Burnt Oto・
Seal ring, (40) (41)... annular dovetail groove. Sub-representative Patent Attorney Shige Okamoto 2 persons Figure 2 Figure 3 Figure 5 Figure 7 Figure 8 Figure 9 Procedural Amendment January 24, 1981 Commissioner of the Patent Office Kazuo Wakasugi 1, Indication of the case 1982 Patent Application No. 222097 2, Title of the invention Reactor vessel watertight lid device 3, Relationship with the case of the person making the amendment Patent applicant name (620
) Mitsubishi Heavy Industries, Ltd. 4, Sub-Agent 5, Amendment Order l] Attached to Showa (1st year""'J-]
[1 Procedural Amendment 11i' (December 8, 1958 Kazuo Wakasugi, Commissioner of the Japan Patent Office 1, Indication of the case, Patent Application No. 222097 of 1982, 2, Title of the invention: Watertight lid device for nuclear reactor vessel 3 , Relationship with the case of the person making the amendment 1.1 Name of applicant (
620) Mitsubishi Heavy Industries, Ltd. 4, sub-agent 5, amendment order 1 = 1 request Showa (1 year 4 days (dispatch 1)) 6, subject of amendment Specification 7, contents of amendment Page 12 of the specification "Lower core support structure" in lines 16 and 17 is amended to "to the reactor vessel." Procedural amendment 1981] February 12, Kazuo Wakasugi, Commissioner of the Patent Office, 1, of the case Indication: 1982 Patent Application No. 222097 2, Title of the invention: Reactor vessel watertight lid device 3, Relationship with amendment f1: Patent, Patent applicant name (6)
20) Mitsubishi Heavy Industries, Ltd. 4, Sub-Agent 5, Date of amendment order Showa (100 years 1st day (shipment date) 6, Subject of amendment Details'':! 1 7, Contents of amendment Page 12 of the specification, No. 16 Correct "lower core support structure" in lines to lines 17 to "reactor vessel".

Claims (1)

【特許請求の範囲】[Claims] 原子炉容器の内部をキャビティに渋った遮蔽水から一時
的に隔離する水密蓋と、原子炉容器側の部材の上端面に
立設した水密蓋用ガイド″ビンと、原子炉容器の上部7
ランジ面の内側に形成したシール面と対向するように上
記水密蓋に設けた二重の環状蟻溝と、同各環状蟻溝に嵌
装したシールリングと、上記水蜜蓋に設けた空気抜管と
、上記各シールリング間の封止空(用に連jFnするよ
うに上記水密蓋に設けた水位管とを具えていることを特
徴とした原子炉容器の水密蓋装置。
A watertight lid that temporarily isolates the inside of the reactor vessel from the shielding water that has collected in the cavity, a guide bottle for the watertight lid installed upright on the upper end of the reactor vessel side member, and an upper part 7 of the reactor vessel.
A double annular dovetail groove provided on the watertight lid so as to face a sealing surface formed inside the flange surface, a seal ring fitted in each of the annular dovetail grooves, and an air vent pipe provided on the watertight lid. A watertight lid device for a nuclear reactor vessel, comprising: a water level pipe provided in the watertight lid so as to connect a sealing space between each of the seal rings.
JP57222097A 1982-12-20 1982-12-20 Water seal plug device of reactor vessel Granted JPS59112287A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP57222097A JPS59112287A (en) 1982-12-20 1982-12-20 Water seal plug device of reactor vessel
FR8320288A FR2538152B1 (en) 1982-12-20 1983-12-19 WATERPROOF COVER FOR NUCLEAR REACTOR ENCLOSURES

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57222097A JPS59112287A (en) 1982-12-20 1982-12-20 Water seal plug device of reactor vessel

Publications (2)

Publication Number Publication Date
JPS59112287A true JPS59112287A (en) 1984-06-28
JPS6325317B2 JPS6325317B2 (en) 1988-05-25

Family

ID=16777085

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57222097A Granted JPS59112287A (en) 1982-12-20 1982-12-20 Water seal plug device of reactor vessel

Country Status (2)

Country Link
JP (1) JPS59112287A (en)
FR (1) FR2538152B1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015533425A (en) * 2012-11-07 2015-11-24 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Repair method for reactor-mounted instrumentation nozzle

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2327911A1 (en) * 1973-06-01 1974-12-19 Licentia Gmbh STATIONARY FLOOD COMPENSATOR FOR NUCLEAR REACTORS
US3926722A (en) * 1973-06-29 1975-12-16 Combustion Eng Reactor vessel head support arrangement
DE2615175C2 (en) * 1976-04-08 1984-10-04 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Gas- and radiation-tight closure
US4330368A (en) * 1979-02-21 1982-05-18 Electric Power Research Institute, Inc. Cable handling system for use in a nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015533425A (en) * 2012-11-07 2015-11-24 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Repair method for reactor-mounted instrumentation nozzle

Also Published As

Publication number Publication date
FR2538152A1 (en) 1984-06-22
FR2538152B1 (en) 1986-08-01
JPS6325317B2 (en) 1988-05-25

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