JPH0116075Y2 - - Google Patents

Info

Publication number
JPH0116075Y2
JPH0116075Y2 JP1981038045U JP3804581U JPH0116075Y2 JP H0116075 Y2 JPH0116075 Y2 JP H0116075Y2 JP 1981038045 U JP1981038045 U JP 1981038045U JP 3804581 U JP3804581 U JP 3804581U JP H0116075 Y2 JPH0116075 Y2 JP H0116075Y2
Authority
JP
Japan
Prior art keywords
plug
pressure
seal plug
seal
pressure pipe
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.)
Expired
Application number
JP1981038045U
Other languages
Japanese (ja)
Other versions
JPS57151596U (en
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 filed Critical
Priority to JP1981038045U priority Critical patent/JPH0116075Y2/ja
Publication of JPS57151596U publication Critical patent/JPS57151596U/ja
Application granted granted Critical
Publication of JPH0116075Y2 publication Critical patent/JPH0116075Y2/ja
Expired 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

  • Quick-Acting Or Multi-Walled Pipe Joints (AREA)

Description

【考案の詳細な説明】 この考案は圧力管型原子炉における圧力管の開
口部をシールして1次冷却材の圧力バウンダリを
形成させるシールプラグと、燃料集合体とともに
圧力管内に挿入されるしやへいプラグとの組立構
造の改良に関する。
[Detailed description of the invention] This invention is based on a seal plug that seals the opening of a pressure pipe in a pressure tube reactor to form a pressure boundary for the primary coolant, and a seal plug that is inserted into the pressure pipe together with a fuel assembly. Regarding the improvement of the assembly structure with Yahei plug.

周知のように頭記圧力管型原子炉では、1次冷
却材を封入した圧力管内に上部および下部しやへ
いプラグとともに燃料集合体が挿入されており、
かつ燃料交換のために開放されている圧力管の開
口部には1次冷却材の圧力バウンダリを形成させ
るシールプラグが装着されている。そして燃料交
換に際しては燃料交換機による遠隔操作で燃料集
合体、しやへいプラグおよびシールプラグの取
出、装荷が行われる。
As is well known, in the above-mentioned pressure tube reactor, a fuel assembly is inserted, together with upper and lower shield plugs, into a pressure tube containing a primary coolant.
In addition, a seal plug is attached to the opening of the pressure pipe that is opened for fuel exchange to form a pressure boundary for the primary coolant. During fuel exchange, the fuel assembly, shield plug, and seal plug are removed and loaded by remote control using a fuel exchange machine.

次に従来における圧力管内の組立構造を第1図
に示す。図において1は原子炉炉心にそれぞれ上
下方向の向きに並べて多数設置された圧力管、2
は燃料集合体、3は下部しやへいプラグ、4がシ
ールプラグである。燃料集合体2としやへいプラ
グ3とはコレツト継手などを介して相互一体に連
結され、かつしやへいプラグには連結管5を介し
てボールラツチ機構6が取付けてあり、圧力管内
の挿入位置ではこのボールラツチ機構6を介して
燃料集合体2およびしやへいプラグ3が圧力管1
に支持されている。一方、これとは別個に独立し
た部品として成るシールプラグ4は、そのプラグ
本体7にシールエレメントのシール面を圧力管1
の内壁に圧接して圧力バウンダリを形成させるシ
ール機構8、およびシール機構8の背後に位置し
て、シールプラグ4を圧力管1に支持するための
ボールラツチ機構9を装備して構成されている。
なおボールラツチ機構6,9およびシール機構8
の着脱は燃料交換機のグラブ操作でアクチユエー
タを動作させることにより行われる。
Next, a conventional assembly structure inside a pressure pipe is shown in FIG. In the figure, 1 indicates a large number of pressure pipes installed vertically in the reactor core, 2
3 is a fuel assembly, 3 is a lower seal plug, and 4 is a seal plug. The fuel assembly 2 and the shield plug 3 are integrally connected to each other via a collet joint, etc., and a ball latch mechanism 6 is attached to the shield plug via a connecting pipe 5, and the ball latch mechanism 6 is attached at the insertion position in the pressure pipe. The fuel assembly 2 and the seal plug 3 are connected to the pressure pipe 1 via this ball latch mechanism 6.
is supported by On the other hand, the seal plug 4, which is formed as a separate and independent component, has the sealing surface of the seal element attached to the plug body 7, which is attached to the pressure pipe 1.
The sealing mechanism 8 is in pressure contact with the inner wall of the pressure pipe 1 to form a pressure boundary, and the ball latch mechanism 9 is located behind the sealing mechanism 8 to support the sealing plug 4 on the pressure pipe 1.
Note that the ball latch mechanisms 6 and 9 and the seal mechanism 8
Attachment and detachment is performed by operating the actuator by operating the fuel exchanger's grab.

上記従来構成での燃料交換作業は次の順序で行
われる。まず圧力管1の下部開口端10に図示さ
れてない燃料交換機を接続し、そのグラブ操作で
シールプラグ4をつかみシール機構8およびボー
ルラツチ機構9を外して圧力管1より引き出す。
次に燃料交換機のグラブを再び操作し、圧力管1
の内方に挿入してしやへいプラグ3をつかみ、そ
のボールラツチ機構6を外してしやへいプラグ3
および燃料集合体2を一緒に引き出す。その後に
前記とは逆の手順で新燃料としやへいプラグを一
緒に結合したまま圧力管内に装荷し、最後にシー
ルプラグを挿入する。
The fuel exchange operation in the conventional configuration described above is performed in the following order. First, a fuel exchanger (not shown) is connected to the lower open end 10 of the pressure pipe 1, and the seal plug 4 is grasped by a grab operation, the seal mechanism 8 and the ball latch mechanism 9 are removed, and the fuel exchanger is pulled out from the pressure pipe 1.
Next, operate the grab of the fuel exchanger again and pressure pipe 1.
Insert the flexible plug 3 into the housing, grasp the flexible plug 3, remove the ball latch mechanism 6, and remove the flexible plug
and pull out the fuel assembly 2 together. Thereafter, in the reverse procedure to the above, new fuel and the seal plug are loaded into the pressure pipe while still being connected together, and finally the seal plug is inserted.

このように従来の構造ではシールプラグ4は単
独で、燃料集合体2としやへいプラグ3は一体に
結合された状態で燃料交換機のグラブによつて取
扱われ、かつそれぞれがボールラツチ機構9,6
を介して圧力管1に支持されている。かかる構成
では、シールプラグ4のボールラツチ機構9はシ
ール機構8よりも下方に位置しているのに対し、
しやへいプラグ3のボールラツチ機構6は当然の
ことながらシールプラグ4の上方に位置すること
になる。つまり1次冷却材の圧力バウンダリを境
にしてボールラツチ機構の一方9は1次冷却機の
外側に、他方6は内側に位置することになる。
In this way, in the conventional structure, the seal plug 4 is handled alone, the fuel assembly 2 and the seal plug 3 are handled as an integral unit by the grab of the fuel exchanger, and the ball latch mechanisms 9 and 6 are used, respectively.
It is supported by the pressure pipe 1 via. In such a configuration, the ball latch mechanism 9 of the seal plug 4 is located below the seal mechanism 8;
The ball latch mechanism 6 of the sealing plug 3 will naturally be located above the sealing plug 4. That is, one side 9 of the ball latch mechanism is located outside the primary cooler, and the other 6 is located inside the primary coolant pressure boundary.

一方、圧力管型原子炉では、最近になり炉の長
期運転経過に伴つてクラツドと呼ばれるさびなど
の放射性を帯びた微細な不溶性異物(以下「クラ
ツド」と呼称する)が炉心構成物より1次冷却材
中に溶出し、これが圧力管内を沈降して底部に沈
澱推積する現象のあることが明かになつた。この
ために上記従来の構造では1次冷却材中にさらさ
れているしやへいプラグ3のボールラツチ機構6
の可動部へ前記のクラツドが侵入推積し、その結
果燃料交換に際してボールラツチ機構6が動作不
能を引起す恐れがある。しかも万一燃料交換に際
してしやへいプラグ3の取出しが不能になると、
原子炉の運転スケジユールに重大な支障を来たす
ことになるので、この点は是非避けなければなら
ない。
On the other hand, in pressure tube reactors, over the course of long-term reactor operation, radioactive fine insoluble foreign matter (hereinafter referred to as "crud"), such as rust, has recently become more important than the core components. It has become clear that there is a phenomenon in which this elutes into the coolant, settles inside the pressure pipe, and accumulates at the bottom. For this reason, in the conventional structure described above, the ball latch mechanism 6 of the insulation plug 3 is exposed to the primary coolant.
The crud may intrude into the movable parts of the ball latch mechanism 6, causing the ball latch mechanism 6 to become inoperable during fuel exchange. Moreover, in the unlikely event that it becomes impossible to remove the plug 3 when changing the fuel,
This must be avoided at all costs, as it will seriously disrupt the reactor's operating schedule.

この考案は上記の点にかんがみなされたもので
あり、その目的は圧力管内の下方に沈澱するクラ
ツドによつて燃料交換の作業が阻害される恐れが
なく、加えて燃料交換の作業時間の短縮も図れる
ようにした圧力管のしやへいおよびシールプラグ
組立体を提供することにある。
This idea was developed in consideration of the above points, and its purpose was to eliminate the possibility that the fuel exchange work would be obstructed by crud deposited in the lower part of the pressure pipe, and also to shorten the fuel exchange work time. It is an object of the present invention to provide a pressure pipe shield and seal plug assembly that can be used in a pressure pipe.

かかる目的はこの考案により、従来におけるし
やへいプラグのボールラツチ機構を削除し、シー
ルプラグの先端にしやへいプラグを一体的に連結
させた組立構造と成し、圧力管内挿入位置では燃
料集合体、しやへいプラグおよびシールプラグの
全重量をシールプラグの例えばボールラツチ機構
である係止支持機構を介して圧力管に支持させる
とともに、燃料交換時には燃料集合体、しやへい
体およびシールプラグを一体として圧力管への装
荷、取出が行えるようにしたことにより達成され
る。
This purpose is achieved by eliminating the conventional ball latch mechanism of the seal plug and creating an assembly structure in which the seal plug is integrally connected to the tip of the seal plug, and the fuel assembly, The entire weight of the shield plug and seal plug is supported by the pressure pipe through the seal plug's locking support mechanism, such as a ball latch mechanism, and the fuel assembly, shield body, and seal plug are integrated as one body during fuel exchange. This is achieved by making it possible to load and unload the pressure pipe.

以下この考案を図示実施例に基づき説明する。 This invention will be explained below based on illustrated embodiments.

まず第2図において、シールプラグ4はそのプ
ラグ本体7に第1図と同じく係止支持機構である
ボールラツチ機構9と、該ボールラツチ機構より
も前方に位置したシール機構8を装備している。
かかるシールプラグ4に対してその先端側には連
結管5を介して下部しやへいプラグ3が連結ボル
ト11により一体的に連結結合されており、燃料
集合体2、しやへいプラグ3およびシールプラグ
4の全重量がすべてボールラツチ機構9を介して
圧力管1に支持されるように構成されている。
First, in FIG. 2, the seal plug 4 is equipped with a ball latch mechanism 9, which is a locking support mechanism, on its plug body 7, as in FIG. 1, and a seal mechanism 8 located in front of the ball latch mechanism.
A lower shield plug 3 is integrally connected to the distal end side of the seal plug 4 via a connecting pipe 5 with a connecting bolt 11, and the fuel assembly 2, the shield plug 3, and the seal are connected to each other by a connecting bolt 11. The entire weight of the plug 4 is supported by the pressure tube 1 via the ball latch mechanism 9.

また第3図に示す応用実施例では、第2図の構
造に加えて、シールプラグ4としやへいプラグ3
との間の切離しを可能とするように、コレツト継
手12を介してしやへいプラグ3がシールプラグ
4に連結されている。これにより炉外へ取出した
後に、シールプラグ4を単独に外して保守点検す
ることが可能になる。
Furthermore, in the applied example shown in FIG. 3, in addition to the structure shown in FIG.
The seal plug 3 is connected to the seal plug 4 via a collet joint 12 so as to enable disconnection between the seal plug 3 and the seal plug 4. This makes it possible to individually remove the seal plug 4 for maintenance and inspection after taking it out of the furnace.

さて上記第2図および第3図の実施例によれ
ば、圧力管内1次冷却材の圧力バウンダリを形成
するシール機構8を境にしてその管内側には係止
支持機構はなく、1次冷却材中のクラツドに対す
る配慮はまつたく不要である。しかも唯一の係止
支持機構であるボールラツチ機構9はシール機構
8の背後に位置しているのでその可動部へのクラ
ツドの侵入の恐れもなく、常に正常な動作が保証
される。加えて燃料交換に際しては1回のグラブ
操作で燃料集合体2、しやへいプラグ3およびシ
ールプラグ4の取出、装荷を行うことができ、従
来と較ベて作業時間の大巾な短縮も可能である等
の実益が得られる。
Now, according to the embodiments shown in FIGS. 2 and 3, there is no locking support mechanism on the inside of the pipe with the seal mechanism 8 forming the pressure boundary of the primary coolant in the pressure pipe as a boundary, and the primary cooling There is no need to consider crud in the material. Moreover, since the ball latch mechanism 9, which is the only locking support mechanism, is located behind the seal mechanism 8, there is no fear of the crud entering the movable part, and normal operation is always guaranteed. In addition, when changing fuel, the fuel assembly 2, seal plug 3, and seal plug 4 can be removed and loaded with a single grab operation, making it possible to significantly shorten the work time compared to conventional methods. You can obtain practical benefits such as:

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

第1図および第2図はそれぞれ従来およびこの
考案の一実施例に基づく圧力管組立構造の構成断
面図、第3図はこの考案の他の実施例の要部を示
す構成図である。 1:圧力管、2:燃料集合体、3:しやへいプ
ラグ、4:シールプラグ、8:シール機構、9:
係止支持機構としてのボールラツチ機構、11:
連結ボルト、12:コレツト継手。
FIGS. 1 and 2 are sectional views of pressure pipe assembly structures based on the conventional and one embodiment of this invention, respectively, and FIG. 3 is a structural diagram showing the main parts of another embodiment of this invention. 1: Pressure pipe, 2: Fuel assembly, 3: Shiyahei plug, 4: Seal plug, 8: Seal mechanism, 9:
Ball latch mechanism as a locking support mechanism, 11:
Connection bolt, 12: Collet joint.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 燃料集合体とともに圧力管内に挿入されるしや
へいプラグと、シール面を圧力管の内壁へ圧接し
て1次冷却材の圧力バウンダリを形成させるシー
ル機構および該シール機構の背後に配置された圧
力管への支持のための係止支持機構が装備されて
いるシールプラグとを一体的に連結して組立構成
したことを特徴とする圧力管型原子炉における圧
力管のしやへいおよびシールプラグ組立体。
A flexible plug inserted into the pressure pipe together with the fuel assembly, a sealing mechanism that presses the sealing surface against the inner wall of the pressure pipe to form a pressure boundary for the primary coolant, and a pressure disposed behind the sealing mechanism. A pressure pipe shield and seal plug assembly in a pressure tube type nuclear reactor, characterized in that the seal plug is integrally connected with a seal plug equipped with a locking support mechanism for supporting the pipe. Three-dimensional.
JP1981038045U 1981-03-18 1981-03-18 Expired JPH0116075Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1981038045U JPH0116075Y2 (en) 1981-03-18 1981-03-18

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1981038045U JPH0116075Y2 (en) 1981-03-18 1981-03-18

Publications (2)

Publication Number Publication Date
JPS57151596U JPS57151596U (en) 1982-09-22
JPH0116075Y2 true JPH0116075Y2 (en) 1989-05-12

Family

ID=29835217

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1981038045U Expired JPH0116075Y2 (en) 1981-03-18 1981-03-18

Country Status (1)

Country Link
JP (1) JPH0116075Y2 (en)

Also Published As

Publication number Publication date
JPS57151596U (en) 1982-09-22

Similar Documents

Publication Publication Date Title
JPH0116075Y2 (en)
JPH0252991A (en) Flow passage control mechanism for heat exchanger
CN212794694U (en) Automatic stove cover bottom plate stamping workpiece of location
CN211999865U (en) Vacuum feeding device for magnesium purification equipment
JPH0645920Y2 (en) Ball latch mechanism clad removing device
JPS6214088A (en) Upper structure of nuclear reactor
JPH035916Y2 (en)
JPS6039994U (en) Pressure tube lower sealing device for pressure tube reactor
JPH052279B2 (en)
JPS59108984A (en) Handling system for seal plug used for repairing pressure tube of pressure tube type reactor
JPS6045838B2 (en) Reactor fuel inlet/outlet guide tube hole plug support device
JPS6219677B2 (en)
JPS6051676B2 (en) Blade guide for nuclear reactor
JPS5934994B2 (en) Emergency core cooling system for high temperature gas reactor
JPH0112237Y2 (en)
JPS6331035Y2 (en)
JPS63105899U (en)
JPH01136095A (en) Core support construction
JPS60188897A (en) Decontaminating device for surrounding of thermal sleeve
JPS58223782A (en) Control rod drive mechanism
JPH0274896A (en) Structure of nuclear reactor
JPH02136789A (en) Outflow preventive wall for reactor core melt
JPS63295990A (en) Fuel assembly
JPH0136916B2 (en)
JPH0569399B2 (en)