Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPS6238679B2 - - Google Patents
[go: Go Back, main page]

JPS6238679B2 - - Google Patents

Info

Publication number
JPS6238679B2
JPS6238679B2 JP55069661A JP6966180A JPS6238679B2 JP S6238679 B2 JPS6238679 B2 JP S6238679B2 JP 55069661 A JP55069661 A JP 55069661A JP 6966180 A JP6966180 A JP 6966180A JP S6238679 B2 JPS6238679 B2 JP S6238679B2
Authority
JP
Japan
Prior art keywords
container
cooling water
valve
opening
nuclear fuel
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
JP55069661A
Other languages
Japanese (ja)
Other versions
JPS5712397A (en
Inventor
Tadashi Tsuji
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP6966180A priority Critical patent/JPS5712397A/en
Publication of JPS5712397A publication Critical patent/JPS5712397A/en
Publication of JPS6238679B2 publication Critical patent/JPS6238679B2/ja
Granted 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 この発明は、貯留水槽内のコンテナ中に核燃料
集合体を収納し、その核燃料集合体の異常を検出
するために、それを浸す冷却水試料を採取する方
法とその装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention provides a method and apparatus for storing a nuclear fuel assembly in a container in a storage water tank and collecting a cooling water sample to immerse the nuclear fuel assembly in order to detect abnormalities in the nuclear fuel assembly. Regarding.

原子炉の炉心に装着された核燃料集合体は長期
の使用又は何等かの突発原因により破損する虞れ
があり、従来から定期的に原子炉を停止して、核
燃料集合体を炉心外の貯留水槽内のコンテナ中に
移し、コンテナ内の冷却水を採り出して試料と
し、それにより、核燃料集合体の異常の有無を検
出している。
Nuclear fuel assemblies installed in the core of a nuclear reactor are at risk of being damaged due to long-term use or due to some unexpected cause. The cooling water inside the container is extracted and used as a sample to detect whether there is an abnormality in the nuclear fuel assembly.

従来の核燃料集合体異常検出用冷却水試料を採
取する方法とその装置を第1図について述べる。
A conventional method and apparatus for collecting a cooling water sample for nuclear fuel assembly abnormality detection will be described with reference to FIG.

異常の有無を検査される核燃料集合体1が差し
入れられる中空コンテナ2は、その下端台座部を
貯留水槽3の槽底に接して、冷却水4中その水面
5下に垂直に静置されている。コンテナ2の上端
上面開放円筒形部6には、それに水平に固定され
た一対のピン軸7に、ほぼコの字形をなすアーム
8が、その下端両脚部において回動自在に軸支さ
れている。アーム8の上辺にはアイボルト9がね
じはめされている。アーム8は、その下端突起部
10が円筒形部6に固定された位置決めピン11
に係合するときは垂直に、アーム8の脚部自体
が、円筒形部6に固定された他の位置決めピン1
2に係合するときはほぼ水平になる。開閉蓋13
は、ヒンジ14により円筒形部6に開閉自在に連
結され、開閉蓋13を閉じ、垂直に立つたアイボ
ルト9を回すことにより、その下端面は円筒形部
6の上端面に水密に密着しコンテナ2を密封す
る。コンテナ2内には、貯留水槽3内の冷却水4
が満たされている。コンテナ2の下端には管路1
5が、開閉蓋13の上端には、それへの接続部附
近がたわむことができる管路16が接続され、管
路16は、電動ポンプ17、開閉弁18を経て管
路15に接続されている。電動ポンプ17と開閉
弁18間の管路は分枝してその分枝管は開閉弁1
9に接続され、開閉弁19の出口側は冷却水試料
採取管路22に接続されている。
The hollow container 2 into which the nuclear fuel assembly 1 to be inspected for abnormalities is inserted is placed vertically in the cooling water 4 below the water surface 5 with its lower end pedestal in contact with the tank bottom of the storage tank 3. . A substantially U-shaped arm 8 is rotatably supported by a pair of pin shafts 7 horizontally fixed to the upper open cylindrical portion 6 of the container 2 at both legs of the lower end thereof. . An eye bolt 9 is screwed onto the upper side of the arm 8. The arm 8 has a positioning pin 11 whose lower end protrusion 10 is fixed to the cylindrical part 6.
vertically when engaged with the other locating pin 1 fixed to the cylindrical part 6.
When engaged with 2, it becomes almost horizontal. Opening/closing lid 13
is connected to the cylindrical part 6 by a hinge 14 so as to be openable and closable, and by closing the opening/closing lid 13 and turning the vertical eye bolt 9, the lower end surface of the container is brought into close contact with the upper end surface of the cylindrical part 6 in a watertight manner. Seal 2. Inside the container 2, there is cooling water 4 in a storage water tank 3.
is fulfilled. Conduit 1 is located at the bottom of container 2.
5 is connected to the upper end of the opening/closing lid 13, and is connected to a conduit 16 which can be bent near the connecting part thereof, and the conduit 16 is connected to the conduit 15 via an electric pump 17 and an on-off valve 18. There is. The pipe line between the electric pump 17 and the on-off valve 18 is branched, and the branch pipe is connected to the on-off valve 1.
9, and the outlet side of the on-off valve 19 is connected to a cooling water sample collection conduit 22.

核燃料集合体1をコンテナ2内に差し入れるに
は、先ず、開閉蓋13を開ける。そのためには、
先端に引掛け部を有する図示しない操作棒を、冷
却水4内のアイボルト9に目視により引つ掛けて
アイボルト9を回し、開閉蓋13の締付けを解
き、アイボルト9をアーム8と共に水平に倒す。
続いて、開閉蓋13を同一操作棒によつて開け
る。その状態で、核燃料集合体1をコンテナ2中
に適宜の手段で差し入れる。核燃料集合体1は、
その下部端栓20が、コンテナ2の下部の円すい
座21に、上部外周が図示しない位置決め部材に
より位置決めされ、その外周をコンテナ2の内壁
から離して、コンテナ2中に垂直に保持される。
その状態で、前記同様にして操作棒により、開閉
蓋13を閉じ、アーム8と共に直立に戻したアイ
ボルト9をねじ込みコンテナ2を密封する。続い
て、開閉弁19を閉じ開閉弁18を開いて、電動
ポンプ17を運転すれば、コンテナ2中の冷却水
は循環する。この状態を一定時間継続後、電動ポ
ンプ17を停止し、開閉弁18を閉じ、開閉弁1
9を開けば、冷却水試料採取管路22を経て冷却
水試料を採取することができる。冷却水試料が所
要量採取されれば、開閉弁19を閉じる。
To insert the nuclear fuel assembly 1 into the container 2, first open the lid 13. for that purpose,
An operating rod (not shown) having a hook at the tip is visually hooked onto the eye bolt 9 in the cooling water 4, the eye bolt 9 is turned, the opening/closing lid 13 is untightened, and the eye bolt 9 is folded horizontally together with the arm 8.
Subsequently, the opening/closing lid 13 is opened using the same operating rod. In this state, the nuclear fuel assembly 1 is inserted into the container 2 by appropriate means. The nuclear fuel assembly 1 is
The lower end stopper 20 is positioned vertically in the container 2 with its upper outer periphery positioned on a conical seat 21 at the lower part of the container 2 by a positioning member (not shown) and with its outer periphery separated from the inner wall of the container 2.
In this state, the opening/closing lid 13 is closed using the operating rod in the same manner as described above, and the eye bolt 9, which has been returned to the upright position along with the arm 8, is screwed in to seal the container 2. Subsequently, when the on-off valve 19 is closed and the on-off valve 18 is opened and the electric pump 17 is operated, the cooling water in the container 2 is circulated. After this state continues for a certain period of time, the electric pump 17 is stopped, the on-off valve 18 is closed, and the on-off valve 1 is closed.
9, a cooling water sample can be collected via the cooling water sampling conduit 22. Once the required amount of cooling water sample has been collected, the on-off valve 19 is closed.

前記従来の方法及び装置においては、冷却水4
中の部分の操作は、すべて、それらの部分を、作
業員が、貯留水槽3の側壁上床面に位置して、目
視観察しながら、手作業で行うため、作業に多く
の時間を要し、核燃料集合体1よりの放射線に被
曝する危険があり、又、冷却水面5に波立や光反
射がある場合には目視観察も困難になるなどの欠
点があつた。
In the conventional method and apparatus, cooling water 4
The operations on the internal parts are all carried out manually by a worker who is positioned on the floor above the side wall of the storage water tank 3 and visually observes them, which requires a lot of time. There is a risk of being exposed to radiation from the nuclear fuel assembly 1, and there are also drawbacks such as difficulty in visual observation if there are ripples or light reflections on the cooling water surface 5.

この発明は、前記従来の方法と装置の欠点を除
去するためになされたもので、核燃料集合体をコ
ンテナ中に差し入れた後は、すべての操作を遠隔
制御により自動化した冷却水試料を採取する方法
とその装置を提供することを目的とする。
This invention was made to eliminate the drawbacks of the conventional methods and devices, and is a method for collecting cooling water samples in which all operations are automated by remote control after a nuclear fuel assembly is inserted into a container. and its equipment.

この発明の一実施例を第2図ないし第4図につ
いて説明する。ここにおいて、第1図におけると
同一符号を付した部分は第1図におけるものと全
く同一のものであるから重ねて説明しない。
An embodiment of the present invention will be described with reference to FIGS. 2 to 4. Here, parts given the same reference numerals as in FIG. 1 are completely the same as those in FIG. 1, and therefore will not be described again.

中空のコンテナ2aは、その下端台座部を貯留
水槽3の槽底に接して、冷却水4中にその水面5
下に垂直に定置されている。コンテナ2aの上部
周壁は外方に張り出した上面開放円筒形部6aを
なし、円筒形部6aの底面には、中心穴中に核燃
料集合体1を位置決めすることができる位置決め
板25が一体に取り付けられている。円筒形部6
aの外壁には、突出アーム26が一体に形成さ
れ、突出アーム26の上外端にはヒンジピン27
が水平にはめ込まれている。円筒形部6aの環状
上端面にはOリング28が納められている。コン
テナ2aの下端部にはその中心に円すい座21が
形成され、コンテナ2中に差し入れられた核燃料
集合体1は、円すい座21と位置決め板25とに
より、コンテナ2のほぼ中心に、その外側面とコ
ンテナ2の内側壁との間に冷却水4で満たされた
空間を存在させて直立に保持される。外側壁が円
筒形部6aの外側壁と同形の、上面が閉鎖した開
閉蓋13aは、その突出アーム29の外下端にお
いて、ヒンジピン27に回動自在に軸支され、そ
の下端面はOリング28を介し円筒形部6aの上
端面に密着できるようになつている。さらに、開
閉蓋13aの上端面には、水平のピン軸30を上
端部に有する突出台31が一体に形成されてい
る。ピン軸30には、レバー32がその中央部に
おいて回動自在に軸支され、レバー32の左端
は、空圧シリンダ33のピストン棒34の上端に
回動自在に軸支され、レバー32の右端には、下
端にパツトを有する蓋押え35がその上端におい
て回動自在に軸支されている。空圧シリンダ33
のシリンダ部下端は、コンテナ2aの外壁から一
体に突出した突出アーム36の先端に回動自在に
軸支されている。空圧シリンダ33のシリンダ部
の上下両端は、それぞれ、管路を介し4路電磁切
換弁37に接続され、電磁切換弁37の他の2路
は、それぞれ、開放管路38、圧縮空気供給管路
39に接続され、管路39には圧力計40、減圧
弁41が接続されている。コンテナ2aの底部に
は管路15aが、その最低部にドレン弁42を備
えて、開閉蓋13aの上端には管路16aが、そ
れぞれ接続され、管路16aの開閉蓋13aに接
続する箇所に近い部分はたわますことができるよ
うになつている。管路16aには直列に、タイマ
43に連係して制御することができる電動ポンプ
17a、流量調整弁44、電磁開閉弁18aが接
続され、電磁開閉弁18aの出口は管路15aに
接続されている。流量調整弁44と電磁開閉弁1
8aを結ぶ管路は分枝し、この分枝管路はタイマ
45によつて制御される電磁開閉弁19aに接続
され、電磁開閉弁19aの出口は冷却水試料採取
管路22に接続されている。電磁切換弁37、圧
力計40、減圧弁41、電動ポンプ17a、タイ
マ43,45、流量調整弁44、電磁開閉弁18
a,19aはいずれも貯留液槽3から離れた位置
に設置され、圧力計40、減圧弁41、流量調整
弁44を除いて、いずれも、図示しない別置公知
構成の集中電磁制御盤を通じて個別に及びシーケ
ンス遠隔制御できるようになつている。
The hollow container 2a has its lower end pedestal in contact with the tank bottom of the storage water tank 3, and its water surface 5 is in contact with the cooling water 4.
It is placed vertically at the bottom. The upper peripheral wall of the container 2a has a cylindrical part 6a with an open top extending outward, and a positioning plate 25 that can position the nuclear fuel assembly 1 in the center hole is integrally attached to the bottom of the cylindrical part 6a. It is being Cylindrical part 6
A protruding arm 26 is integrally formed on the outer wall of a, and a hinge pin 27 is provided at the upper outer end of the protruding arm 26.
is fitted horizontally. An O-ring 28 is housed in the annular upper end surface of the cylindrical portion 6a. A conical seat 21 is formed at the center of the lower end of the container 2a, and the nuclear fuel assembly 1 inserted into the container 2 is placed approximately at the center of the container 2 on its outer surface by the conical seat 21 and the positioning plate 25. A space filled with cooling water 4 exists between the container 2 and the inner wall of the container 2, and the container 2 is held upright. The opening/closing lid 13a, whose outer wall is the same as the outer wall of the cylindrical portion 6a and whose upper surface is closed, is rotatably supported on a hinge pin 27 at the outer lower end of its protruding arm 29, and its lower end surface is supported by an O-ring 28. It can be brought into close contact with the upper end surface of the cylindrical portion 6a via the cylindrical portion 6a. Furthermore, a protruding base 31 having a horizontal pin shaft 30 at its upper end is integrally formed on the upper end surface of the opening/closing lid 13a. A lever 32 is rotatably supported on the pin shaft 30 at its center, the left end of the lever 32 is rotatably supported on the upper end of a piston rod 34 of a pneumatic cylinder 33, and the right end of the lever 32 is rotatably supported on the pin shaft 30. A lid holder 35 having a pad at its lower end is rotatably supported at its upper end. Pneumatic cylinder 33
The lower end of the cylinder is rotatably supported by the tip of a protruding arm 36 that protrudes integrally from the outer wall of the container 2a. Both upper and lower ends of the cylinder portion of the pneumatic cylinder 33 are connected to a four-way electromagnetic switching valve 37 via pipes, and the other two roads of the electromagnetic switching valve 37 are connected to an open pipe 38 and a compressed air supply pipe, respectively. A pressure gauge 40 and a pressure reducing valve 41 are connected to the pipe line 39 . A conduit 15a is connected to the bottom of the container 2a, a drain valve 42 is provided at the lowest part thereof, and a conduit 16a is connected to the upper end of the opening/closing lid 13a. The near part can be bent. Connected in series to the conduit 16a are an electric pump 17a that can be controlled in conjunction with a timer 43, a flow rate adjustment valve 44, and an electromagnetic on-off valve 18a, and the outlet of the electromagnetic on-off valve 18a is connected to the conduit 15a. There is. Flow rate adjustment valve 44 and electromagnetic opening/closing valve 1
The pipe connecting 8a branches, and this branch pipe is connected to an electromagnetic on-off valve 19a controlled by a timer 45, and the outlet of the electromagnetic on-off valve 19a is connected to a cooling water sample collection pipe 22. There is. Electromagnetic switching valve 37, pressure gauge 40, pressure reducing valve 41, electric pump 17a, timers 43, 45, flow rate adjustment valve 44, electromagnetic on-off valve 18
19a and 19a are both installed at a position away from the storage liquid tank 3, and except for the pressure gauge 40, the pressure reducing valve 41, and the flow rate adjustment valve 44, all of them are controlled individually through a separate centralized electromagnetic control panel (not shown) with a known configuration. It is now possible to remotely control the sequence.

前記のように構成されたこの発明の装置の作用
を次に述べる。
The operation of the apparatus of the present invention constructed as described above will be described below.

圧力計40の指示を見て、減圧弁41により、
供給圧縮空気の圧力を所望の大きさに調整する。
電磁切換弁37を一方の側に付勢すれば、圧縮空
気は空圧シリンダ33のシリンダ部上端に送入さ
れ、そのピストン棒34は下降し、それにより、
レバー32を介して、蓋押え35は開閉蓋13a
の圧下を解き、続いて、空圧シリンダ33は、突
出アーム36の先端に備わるピン軸を中心にして
反時計方向に回動させられるため、開閉蓋13a
はヒンジピン27を中心として反時計方向に回動
して開き、コンテナ2aの上面は開口される。そ
の状態で、核燃料集合体1をコンテナ2a内に従
来公知の手段でつり降ろせば、核燃料集合体1
は、コンテナ2aの下部円すい座21にその下部
端栓20を、位置決め板25の内穴にその上部外
周を位置決めされて、コンテナ2a中、冷却水4
の中に直立に静置される。続いて、電磁切換弁3
7を逆方向に付勢すれば、圧縮空気は空圧シリン
ダ33の下部に送り込まれて、ピストン棒34は
上昇し、ピストン棒34が下降した前記の場合と
逆の方向経路をたどつて、開閉蓋13aは閉じ、
蓋押え35は、Oリング28を介して開閉蓋13
aをコンテナ2aの開口上面に水密に押えつけ
る。
Checking the indication on the pressure gauge 40, the pressure reducing valve 41
Adjust the pressure of the compressed air supply to the desired level.
When the electromagnetic switching valve 37 is biased to one side, compressed air is sent to the upper end of the cylinder portion of the pneumatic cylinder 33, and its piston rod 34 is lowered, thereby,
Through the lever 32, the lid holder 35 opens and closes the lid 13a.
is released, and then the pneumatic cylinder 33 is rotated counterclockwise around the pin shaft provided at the tip of the protruding arm 36, so that the opening/closing lid 13a is rotated counterclockwise.
is rotated counterclockwise around the hinge pin 27 to open, and the top surface of the container 2a is opened. In this state, if the nuclear fuel assembly 1 is lowered into the container 2a by conventionally known means, the nuclear fuel assembly 1
The lower end plug 20 is positioned in the lower conical seat 21 of the container 2a, and the upper outer periphery is positioned in the inner hole of the positioning plate 25.
It is placed upright inside. Next, solenoid switching valve 3
7 is energized in the opposite direction, compressed air is sent to the lower part of the pneumatic cylinder 33, the piston rod 34 rises, and the piston rod 34 follows the opposite direction path to the previous case in which it descended. The opening/closing lid 13a is closed,
The lid holder 35 connects the opening/closing lid 13 via the O-ring 28.
A is pressed against the top of the opening of the container 2a in a watertight manner.

電磁切換弁37の前記逆方向付勢に伴い、電磁
制御盤から電気信号(以下単に信号と称する)S
1が電磁開閉弁18aに送られ電磁開閉弁18a
は開く。このとき、電磁開閉弁19aは閉じたま
まである。電磁開閉弁18aの開動作に伴い、信
号S2が発出され、それを受けて電動ポンプ17
aが起動する。電動ポンプ17aが運転すれば、
コンテナ2a中の冷却水は、予め流量調整弁44
で設定された流量をもつて、管路16a、電動ポ
ンプ17a、流量調整弁44、電磁開閉弁18
a,管路15aを経て循環する。タイマ43に予
め設定した時間が経過すれば、その信号S3によ
り電動ポンプ17aは停止し、その発出信号S4
を受けて電磁開閉弁18aは閉じ、電磁開閉弁1
9aは開いて、管路22中を冷却水は流下し、そ
の下方管端で冷却水試料を採取することができ
る。タイマ45に予め設定した時間が電磁開閉弁
19aが開いてから経過すればタイマ45は信号
S5を発出し、電磁開閉弁19aは信号S5を受
けて閉じ、冷却水試料の採取は終ると共に、電磁
切換弁37は、信号S5と同時にタイマ45から
発出された信号S6を受けて、空圧シリンダ33
のシリンダ上部に圧縮空気を送入するように切り
換わつて、開閉蓋13aは前記したと同様にして
開き、核燃料集合体1をコンテナ2aから取り出
し、次の被検査核燃料集合体をコンテナ2a中に
差し入れる準備が整う。
As the electromagnetic switching valve 37 is biased in the reverse direction, an electric signal (hereinafter simply referred to as a signal) S is sent from the electromagnetic control panel.
1 is sent to the electromagnetic on-off valve 18a, and the electromagnetic on-off valve 18a
opens. At this time, the electromagnetic on-off valve 19a remains closed. With the opening operation of the electromagnetic on-off valve 18a, a signal S2 is issued, and in response to this, the electric pump 17
a starts. If the electric pump 17a operates,
The cooling water in the container 2a is supplied to the flow rate regulating valve 44 in advance.
With the flow rate set in
a, circulates through the pipe 15a. When the time preset in the timer 43 has elapsed, the electric pump 17a is stopped by the signal S3, and the emitted signal S4 is stopped.
In response, the electromagnetic on-off valve 18a closes, and the electromagnetic on-off valve 1
9a is open so that cooling water flows down through the conduit 22 and a cooling water sample can be taken at its lower tube end. When the time preset in the timer 45 has elapsed since the electromagnetic on-off valve 19a opened, the timer 45 emits a signal S5, and the electromagnetic on-off valve 19a closes upon receiving the signal S5. The switching valve 37 receives the signal S6 issued from the timer 45 at the same time as the signal S5, and the pneumatic cylinder 33
Switching to supply compressed air to the upper part of the cylinder, the opening/closing lid 13a is opened in the same manner as described above, the nuclear fuel assembly 1 is taken out from the container 2a, and the next nuclear fuel assembly to be inspected is placed in the container 2a. It's ready to be inserted into.

この発明の装置は、前記実施例について詳述し
たように、貯留水槽内冷却水中に定置され上面が
開口し、核燃料集合体を直立に差し入れることが
できるコンテナと、このコンテナの開口上面を密
閉することができる開閉自在の開閉蓋と、この開
閉蓋を遠隔制御によつて開閉し、貯留水槽内の冷
却水中において開閉蓋の密着密閉動作と開閉動作
とを同時に行なう空圧シリンダと、コンテナの上
端部、下端部に一端がそれぞれ接続されたコンテ
ナ内冷却水の循環管路と、この循環管路中に設け
られ、タイマにより設定された一定時間、循環管
路、コンテナ内にコンテナ内冷却水を循環させる
遠隔制御の循環装置と、循環管路から分枝し、遠
隔制御により開閉自在の開閉弁により連通し、循
環装置によりコンテナ内より循環された冷却水が
流下する分枝管と、前記のそれぞれの制御をシー
ケンス制御することができる制御装置とを備える
ことにより、この発明の装置を用い又この発明の
方法によるときは、被検査核燃料集合体をコンテ
ナ内に差し入れた後は、冷却水試料を採取するま
で、すべての操作を遠隔制御で自動的に行うこと
ができ、従つて貯留水槽側壁上面床上に位置して
作業員が目視観察しながら手作業を行う従来の場
合に較べて、作業時間が著しく短縮され、操作は
遠隔制御により行われるので放射線被曝の度合も
著しく減少し安全確実な作業ができる効果があ
る。
As described in detail in the above embodiments, the device of the present invention includes a container that is placed in cooling water in a storage water tank and has an open top surface into which a nuclear fuel assembly can be inserted upright, and a container that has the open top surface of the container sealed. A pneumatic cylinder that opens and closes the lid by remote control and simultaneously performs the sealing operation and opening/closing operation of the lid in the cooling water in the storage water tank; A circulation pipe for cooling water inside the container, one end of which is connected to the upper end and one end of the lower end. a remote-controlled circulation device that circulates the water; a branch pipe that branches from the circulation pipe and communicates with an on-off valve that can be opened and closed by remote control, through which cooling water circulated from inside the container by the circulation device flows; When using the apparatus of the present invention and the method of the present invention, after inserting the nuclear fuel assembly to be inspected into the container, cooling water is All operations can be performed automatically by remote control until the sample is collected, compared to the conventional case where the operator is located on the upper floor of the side wall of the storage tank and manually performs the work while visually observing the sample. The work time is significantly shortened, and since the operation is performed by remote control, the degree of radiation exposure is also significantly reduced and the work can be carried out safely and reliably.

またさらにシリンダの駆動源に空気を用いた空
気シリンダを貯留水槽内の冷却水中における開閉
蓋の開閉動作および閉じられた蓋の密着密閉動作
の原動力として用いる構成としたので、冷却水中
における開閉操作等の作業中に圧縮空気の供給管
路(ホース)に空気漏れが生じてもこの空気漏れ
は水中で気泡となつて水面上の作業者が容易に観
察することができる。したがつて、装置の不具合
を早期に、しかも確実にかつコストをかけること
なく知ることができる。
Furthermore, an air cylinder using air as the driving source of the cylinder is used as the driving force for the opening/closing operation of the opening/closing lid in the cooling water in the storage water tank and the tight sealing operation of the closed lid, so that the opening/closing operation in the cooling water, etc. Even if an air leak occurs in the compressed air supply pipe (hose) during the work, this air leak forms bubbles in the water and can be easily observed by the worker on the surface of the water. Therefore, malfunctions in the device can be detected early, reliably, and without incurring any cost.

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

第1図は従来の核燃料集合体異常検出用冷却水
試料の採取装置の構成図、第2図はこの発明の装
置の構成図、第3図はこの発明の装置の要部平面
図、第4図はこの発明の装置の作動順序を示すブ
ロツク図である。 1……核燃料集合体、2a……コンテナ、3…
…貯留水槽、4……冷却水、13a……開閉蓋、
15a,16a……管路、17a……電動ポン
プ、18a,19a……電磁開閉弁、22……冷
却水試料採取管路、33……空圧シリンダ。
FIG. 1 is a block diagram of a conventional cooling water sample collection device for detecting abnormalities in nuclear fuel assemblies, FIG. 2 is a block diagram of the device of the present invention, FIG. 3 is a plan view of essential parts of the device of the present invention, and FIG. The figure is a block diagram showing the operating sequence of the apparatus of the present invention. 1...Nuclear fuel assembly, 2a...Container, 3...
...Storage tank, 4...Cooling water, 13a...Opening/closing lid,
15a, 16a...pipe line, 17a...electric pump, 18a, 19a...electromagnetic on-off valve, 22...cooling water sample collection pipe line, 33...pneumatic cylinder.

Claims (1)

【特許請求の範囲】[Claims] 1 貯留水槽内冷却水中に定置されて、上面が開
口し、核燃料集合体を直立に差し入れることがで
きるコンテナと、このコンテナの前記開口上面を
密閉することができる開閉自在の開閉蓋と、この
開閉蓋を遠隔制御によつて開閉し、貯留水槽内冷
却水中において前記開閉蓋の密閉と蓋の開閉を同
時に行なう空圧シリンダと、前記コンテナの上端
部と下端部に一端がそれぞれ接続されたコンテナ
内冷却水の循環管路と、この循環管路中に設けら
れ、タイマにより設定された一定時間の間、前記
環管路および前記コンテナ内に前記コンテナ内冷
却水を循環させる遠隔制御の循環装置と、前記循
環管路から分枝し遠隔制御により開閉自在の開閉
弁により連通されて、前記循環装置により先に前
記コンテナ内より循環された冷却水が流下する分
枝管と、前記それぞれの制御をシーケンス制御す
ることができるシーケンス制御装置とを備えた核
燃料集合体異常検出用冷却水試料の採取装置。
1. A container that is placed in cooling water in a storage tank and has an open top surface into which a nuclear fuel assembly can be inserted upright; a lid that can be opened and closed to seal the top surface of the opening; a pneumatic cylinder that opens and closes the opening/closing lid by remote control and simultaneously seals the opening/closing lid and opens and closes the lid in cooling water in a storage water tank; and a container having one end connected to the upper end and the lower end of the container, respectively. an internal cooling water circulation pipe; and a remote-controlled circulation device provided in the circulation pipe, which circulates the container cooling water within the ring pipe and the container for a certain period of time set by a timer. and a branch pipe branching from the circulation pipe and communicating with an on-off valve that can be opened and closed by remote control, through which cooling water previously circulated from within the container by the circulation device flows, and each of the above-mentioned controls. A cooling water sample collection device for nuclear fuel assembly abnormality detection, comprising a sequence control device capable of sequence control.
JP6966180A 1980-05-27 1980-05-27 Method and device for sampling coolant for abnormality detection of nuclear fuel assembly Granted JPS5712397A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6966180A JPS5712397A (en) 1980-05-27 1980-05-27 Method and device for sampling coolant for abnormality detection of nuclear fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6966180A JPS5712397A (en) 1980-05-27 1980-05-27 Method and device for sampling coolant for abnormality detection of nuclear fuel assembly

Publications (2)

Publication Number Publication Date
JPS5712397A JPS5712397A (en) 1982-01-22
JPS6238679B2 true JPS6238679B2 (en) 1987-08-19

Family

ID=13409230

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6966180A Granted JPS5712397A (en) 1980-05-27 1980-05-27 Method and device for sampling coolant for abnormality detection of nuclear fuel assembly

Country Status (1)

Country Link
JP (1) JPS5712397A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58153199A (en) * 1982-03-09 1983-09-12 原子燃料工業株式会社 Opening and closing device for cap in shipping device
JP2006029930A (en) * 2004-07-15 2006-02-02 Hitachi Ltd Nuclear fuel out-of-core shipping apparatus and out-of-core shipping method
FR3120981B1 (en) * 2021-03-19 2023-02-10 Framatome Sa Device for raising or lowering a nuclear fuel assembly in a pool of a nuclear installation
FR3131061B1 (en) * 2021-12-16 2023-11-24 Framatome Sa Device for raising or lowering a nuclear fuel assembly in a pool of a nuclear installation

Also Published As

Publication number Publication date
JPS5712397A (en) 1982-01-22

Similar Documents

Publication Publication Date Title
JP2013517481A (en) Hydrostatic pressure test system and method
JPS6238679B2 (en)
CN109236802A (en) A kind of solenoid directional control valve sampling automatic test equipment and its working method
US3650147A (en) Cooling system pressure tester
CN112461613B (en) A transformer gas automatic collection detection box and its use method
CN217403897U (en) Gas-liquid mixture sampling bottle of looking for leaks
US2821851A (en) System for hydrostatically testing containers
JP2942586B2 (en) Internal inspection method of hydraulic machine
US4161197A (en) Apparatus for measuring and dispensing chemical
US4144744A (en) Vein preparation and testing device
US20050016261A1 (en) Pressure checking apparatus for a swimming pool and method of use
KR890001137B1 (en) Leakage test instrument of gas can
CN107638650A (en) A kind of transportable fire extinguisher barrel pressure alternation and explosion bulge test device
CN222993906U (en) A valve leak detection device
JPH0526498Y2 (en)
CN216386716U (en) Pneumatic water tester
JPH0220662Y2 (en)
CN221055999U (en) Intelligent testing mechanism of valve
JP3018960U (en) Floor heating inspection equipment
JPS58153200A (en) Failed fuel detecting device
JPS6346834Y2 (en)
JPS6026974B2 (en) Automatic Penetration Detection Development Tool
WO2001094903A1 (en) Method and apparatus for pressure testing sealed packages
CA1066914A (en) Vein preparation and testing device
US2096497A (en) Demonstrating apparatus