JPS643105Y2 - - Google Patents

Info

Publication number
JPS643105Y2
JPS643105Y2 JP1982152996U JP15299682U JPS643105Y2 JP S643105 Y2 JPS643105 Y2 JP S643105Y2 JP 1982152996 U JP1982152996 U JP 1982152996U JP 15299682 U JP15299682 U JP 15299682U JP S643105 Y2 JPS643105 Y2 JP S643105Y2
Authority
JP
Japan
Prior art keywords
nuclear fuel
nut
gripping
outer cylinder
handle
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
JP1982152996U
Other languages
Japanese (ja)
Other versions
JPS5958395U (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 JP1982152996U priority Critical patent/JPS5958395U/en
Publication of JPS5958395U publication Critical patent/JPS5958395U/en
Application granted granted Critical
Publication of JPS643105Y2 publication Critical patent/JPS643105Y2/ja
Granted legal-status Critical Current

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

  • Load-Engaging Elements For Cranes (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 本考案は原子燃料内挿物構造体を水中にあつ
て、適宜の解体用保持装置に収納保持させてお
き、当該構造体を解体することにより、上記解体
用保持装置に残置された使用済みの原子燃料内挿
物を把持することにより抜き取り、これを所定の
エリアに移送廃棄するのに用いて好適な原子燃料
内挿物構造体の解体用原子燃料内挿物遠隔把持移
送装置に関する。
[Detailed description of the invention] The present invention stores and holds a nuclear fuel insert structure underwater in an appropriate disassembly holding device, and by dismantling the structure, the above-mentioned disassembly holding device A nuclear fuel insert remote for dismantling a nuclear fuel insert structure suitable for use in grasping and extracting a used nuclear fuel insert left behind in a nuclear fuel insert and transporting it to a predetermined area for disposal. This invention relates to a gripping and transferring device.

原子炉における原子燃料内挿物構造体1は、既
知の通り第1図に示す如き構成を有し、上部構造
物2の端板3にクラスタ状にて垂下状態となるよ
う多数の原子燃料内挿物4を取着したものであ
り、上部構造物2はホールドダウンパー5と上記
端板3とを接続したスリーブ6にホールドダウン
スプリング7を被嵌してなり、また上記原子燃料
挿入物4としては、図示の如く原子燃料の反応度
を制御する数mにおよぶ長尺なバーナブルポイズ
ン棒41(可燃性毒物入棒)や、これよりも大径短
尺であり原子燃料集合体内を流過する冷却水の圧
力損失を調整するためのシンブルプラグ42が単
独または組合わせて用いられ、さらにはこれら二
者41,42に中性子源としての原子燃料挿入物を
も組込んだ原子燃料挿入物構造体などが用いられ
ている。
As is known, the nuclear fuel insert structure 1 in a nuclear reactor has a structure as shown in FIG. The upper structure 2 is formed by fitting a hold-down spring 7 into a sleeve 6 that connects the hold-down par 5 and the end plate 3, and the nuclear fuel insert 4 is attached to the upper structure 2. As shown in the figure, there is a burnable poison rod 4 1 (stick containing burnable poison) that is several meters long and that controls the reactivity of nuclear fuel, and a rod with a larger diameter and shorter length that controls the reactivity of nuclear fuel. A thimble plug 4 2 is used alone or in combination to adjust the pressure loss of the cooling water caused by the atomic bomb, and a nuclear fuel insert as a neutron source is also incorporated in these two 4 1 , 4 2 . Fuel insert structures and the like are used.

そしてかゝる原子燃料内挿物構造体1は既知の
如く原子燃料集合体の制御棒案内シングルに挿入
され、ホールドダウンスプリング7を介して上部
炉心板に押圧固定することにより使用されること
になるが、上記したバーナブルポイズン棒41は
原子核反応により発生する余剰の中性子を吸収し
て原子炉の反応度を一定に維持する役割を果すも
のであるから、多量の中性子照射を受けて使用済
みとなつた当該バーナブルポイズン棒41は、強
い放射能を有し、これに接近することが危険とな
るから、従来かゝる場合には原子燃料集合体から
原子燃料内挿物構造体を、そのまゝ遠隔操作によ
り引き抜くと共に、これを移送して原子力発電所
の所定エリア内にて長期にわたり保管する取扱い
をしている。
The nuclear fuel insert structure 1 is inserted into a control rod guide single of a nuclear fuel assembly as is known in the art, and used by being press-fixed to the upper core plate via a hold-down spring 7. However, the burnable poison rod 41 described above has the role of absorbing excess neutrons generated by nuclear reactions and maintaining the reactivity of the reactor at a constant level, so it cannot be used while receiving a large amount of neutron irradiation. Since the burned-out burnable poison rod 41 has strong radioactivity and it is dangerous to approach it, conventionally it has been removed from the nuclear fuel assembly to the nuclear fuel insert structure. The nuclear power plant is removed as is by remote control, transported and stored for a long period of time within a designated area of the nuclear power plant.

このため上記従来の取扱いによるときは、機械
的破損等のない限り再使用の可能である上部構造
物2やシンブルプラグ42が、バーナブルポイズ
ン棒41と共に廃棄されることゝなり、大きな損
失を伴うものとなつている。
For this reason, when using the conventional handling described above, the upper structure 2 and the thimble plug 42 , which can be reused unless there is mechanical damage, are discarded together with the burnable poison rod 41 , resulting in a large loss. It has become accompanied by

本発明はかゝる現況に着目し、使用済みとなつ
た原子燃料内挿物構造体1をそのまゝ移送保管す
るのではなく、当該構造体1を水中で解体するこ
とにより、バーナブルポイズン棒41だけを取り
出して、これを放射性廃棄物として所定エリア内
に移し、かつ新規なバーナブルポイズン棒を当該
構造体1の上部構造物2に取着し、同構造物2、
シンブルプラグ42等の再使用を意図するもので、
本考案では特に上記の使用済み原子燃料内挿物構
造体1を原子燃料集合体から引き出し、これを解
体用保持装置に収納静置した後、当該構造体1の
解体を行ない、次に原子燃料内挿物たるバーナブ
ルポイズン棒等を水中より取り出して別途設けら
れた放射性廃棄物収納箇所に移送することができ
ると共に、新規なバーナブルポイズン棒等を上記
解体用保持装置に搬入し得るようにし、しかも
かゝる移送を遠隔操作により安全性を確保しなが
ら、簡易な操作により迅速にして確実な把持と移
送を行ない得るようにするのが、その目的であ
る。
The present invention focuses on the current situation, and instead of transporting and storing the spent nuclear fuel insert structure 1 as it is, the present invention dismantles the structure 1 underwater to remove burnable poison. Only the rod 4 1 is taken out and moved to a designated area as radioactive waste, and a new burnable poison rod is attached to the upper structure 2 of the structure 1, and the same structure 2,
It is intended for reuse of thimble plug 4 2 etc.
In particular, in the present invention, the above-mentioned spent nuclear fuel insert structure 1 is pulled out from the nuclear fuel assembly, stored in a holding device for disassembly, and then left undisturbed, the structure 1 is dismantled, and then the nuclear fuel Burnable poison rods, etc., which are inserts, can be taken out of the water and transferred to a separately provided radioactive waste storage area, and new burnable poison rods, etc., can be carried into the holding device for dismantling. Moreover, the purpose is to ensure the safety of such transfer by remote control, and to enable quick and reliable gripping and transfer with simple operations.

本考案を図示の実施例によつて詳記すれば、第
4図に示す通り、ブリツジクレーン等により吊持
可能とした吊持部8と、これに垂設固定した把持
杆9と、同杆9に昇降自在なるよう被嵌した外筒
10と、当該外筒10を手動操作によつて昇降動
させる把持用操作部11とを主要構成部とするも
のである。
To describe the present invention in detail with reference to the illustrated embodiment, as shown in FIG. The main components are an outer cylinder 10 that is fitted onto the rod 9 so as to be able to move up and down, and a gripping operation section 11 that moves the outer cylinder 10 up and down by manual operation.

先ず吊持部8として図示されたものは、基板1
2にUボルト13の両端部をナツト14締めによ
り上向きに突出固定したものであり、把持杆9は
パイプにより形成されパイプの上端に嵌着した接
続棒9′を、上記基板12に貫設してナツト15
止めすることにより、把持杆9を基板12から垂
設してある。
First, what is illustrated as the hanging portion 8 is the substrate 1
2, both ends of a U-bolt 13 are fixed to protrude upward by tightening nuts 14, and the gripping rod 9 is formed of a pipe, and a connecting rod 9' fitted to the upper end of the pipe is inserted through the base plate 12. Te Natsu 15
By stopping, the gripping rod 9 is suspended from the base plate 12.

そして上記把持杆9に間隙空所16を介して被
嵌した外筒10の上端部が、上記接続棒9′に被
嵌されて、外筒10が当該接続棒9′を案内とし
て昇降動自在であり、図中Mが当該昇降動が許容
される摺動域を示している。
The upper end of the outer cylinder 10 fitted into the gripping rod 9 through the gap 16 is fitted onto the connecting rod 9', and the outer cylinder 10 can freely move up and down using the connecting rod 9' as a guide. In the figure, M indicates a sliding area in which the vertical movement is allowed.

次に前記の把持用操作部11は、上記基板12
の下面に固設したナツト受筒台17と、同受筒台
17の凹陥底部17′に落込み状態で載受された
把手付ナツト18を具備し、当該ナツト18は前
記外筒10に被着した螺筒19に螺合しており、
把手付ナツト18の把手18′はナツト受筒台1
7の周壁に穿設された横向長孔20から外側へ延
出しており、従つて把手18′を例えば180゜だけ
回動できるようにしてある。
Next, the gripping operation section 11 is connected to the substrate 12.
It is equipped with a nut receiving cylinder stand 17 fixedly installed on the lower surface, and a nut with a handle 18 resting in a recessed bottom part 17' of the receiving cylinder stand 17 in a depressed state, and the nut 18 is covered with the outer cylinder 10. It is screwed into the attached screw tube 19,
The handle 18' of the nut with handle 18 is attached to the nut receiver base 1.
The handle 18' extends outwardly from a horizontal elongated hole 20 formed in the peripheral wall of the handle 7, thereby allowing the handle 18' to rotate, for example, by 180 degrees.

さらに把持用操作部11には外筒10の回り止
め機構21が付設されており、図示例ではこのた
め外筒10に支持腕22を横向固設し、この支持
腕22から植立した昇降案内ピン23を、ナツト
受筒台17から突設したガイド環24に装通させ
るようにしており、かくて把手18′を前記のよ
うに180゜回動操作することにより、外筒10は把
手付ナツト18と螺筒19との螺合と、上記の回
り止め機構21とによつて、回転することなく前
記摺動域Mの範囲内において昇降動することゝな
る。
Further, the grasping operation part 11 is provided with a mechanism 21 for preventing rotation of the outer cylinder 10, and in the illustrated example, a support arm 22 is horizontally fixed to the outer cylinder 10, and an elevating guide is installed from the support arm 22. The pin 23 is inserted through a guide ring 24 protruding from the nut receiver base 17, and by rotating the handle 18' by 180 degrees as described above, the outer cylinder 10 is attached to the handle. Due to the screw engagement between the nut 18 and the screw tube 19 and the above-mentioned rotation prevention mechanism 21, it is possible to move up and down within the sliding area M without rotating.

さらに本考案では上記した把持杆9の先端にあ
つて複数個に分割された挾持爪25,25…が設
けられており、これらの挾持爪25,25…によ
り囲成された把持端口26を下端に開口すること
によりコレツトチヤツク27が形成されている。
Furthermore, in the present invention, a plurality of clamping claws 25, 25... are provided at the tip of the above-mentioned gripping rod 9, and the gripping end opening 26 surrounded by these clamping claws 25, 25... is connected to the lower end. A collector chuck 27 is formed by opening at the opening.

コレツトチヤツク27の挾持端口26には、前
記原子燃料内挿物4の上部端栓4aが挿入し得る
よう平時は当該端口26が拡開状態を保持してお
り、図示例では当該拡開状態が縮径されることが
ないようにするため、把持杆9の先端に螺着した
棒心材28が、コレツトチヤツク27の軸心上位
に内嵌してある。
In normal times, the clamping end opening 26 of the collector chuck 27 is held in an expanded state so that the upper end plug 4a of the nuclear fuel insert 4 can be inserted therein, and in the illustrated example, the expanded state is contracted. In order to prevent the gripping rod 9 from becoming loose, a rod core 28 screwed onto the tip of the gripping rod 9 is fitted inside the collection chuck 27 above its axis.

また図示の挾持爪25,25…にあつては、挾
持端口26を形成している内面に螺子部29が刻
設されており、当該螺子部29のピツチを、原子
燃料内挿物4の上部端栓4aに形成されている螺
杆部30のピツチと整合させているが、螺杆部3
0を有しない原子燃料内挿物4を対象とするので
あれば、かゝる螺子部29の刻設はなくともよ
く、対象如何によつては螺子部にかえて図示しな
い凹凸を形成するようにしてもよい。
Further, in the case of the illustrated clamping claws 25, 25..., a threaded part 29 is carved on the inner surface forming the clamping end opening 26, and the pitch of the threaded part 29 is inserted into the upper part of the nuclear fuel insert 4. The pitch of the threaded threaded portion 30 formed on the end plug 4a is aligned with the pitch of the threaded threaded portion 30.
If the target is a nuclear fuel insert 4 that does not have zero, it is not necessary to provide such a threaded portion 29. Depending on the target, unevenness (not shown) may be formed instead of the threaded portion. You can also do this.

一方前記外筒10の先端部にはスリーブ10′
が固設され、同スリーブ10′の先端内周面に押
圧テーパ面31が形成されており、把持操作部1
1の前記回動操作により外筒10を下動させるこ
とにより、上記押圧テーパ面31が、挾持爪2
5,25…の先端外周面に形成した受圧テーパ面
32に摺接し、当該挾持爪25,25…を、その
挾持端口26が縮径する方向へ押動するよう構成
されている。
On the other hand, a sleeve 10' is provided at the tip of the outer cylinder 10.
is fixedly installed, and a pressing tapered surface 31 is formed on the inner circumferential surface of the tip end of the sleeve 10', and the gripping operation section 1
By moving the outer cylinder 10 downward by the rotational operation in step 1, the pressing tapered surface 31 is moved against the clamping claw 2.
The clamping claws 25, 25, .

そこで上記装置を使用するには、先ず原子燃料
集合体から使用済みの原子燃料内挿構造体1を、
ブリツジクレーン等を用いて引き揚げ、別途水中
に設置された解体用保持装置33に第3図に示す
如く収納立置させる。
Therefore, in order to use the above device, first, the spent nuclear fuel insertion structure 1 is removed from the nuclear fuel assembly.
It is lifted up using a bridge crane or the like and stored and placed upright in a dismantling holding device 33 installed separately underwater as shown in FIG.

こゝで上記解体用保持装置33しては複数本の
縦枠材34,34…に横向天板35、横向中板3
6、横向底板37を架設したものが用いられ、図
示例ではバーナブルポイズン棒41が横向天板3
5、横向中板36に天々穿設した上位通孔38、
中位通孔39を貫通して、その下位端栓41aが横
向底板37に支承されると共に、大径短尺のシン
ブルプラグ42は上位通孔38に貫通して、その
下部端栓42aが横向中板36の中位通孔39に係
合支承されるようにしてある。
Here, the holding device 33 for disassembly is a horizontal top plate 35, a horizontal middle plate 3, and a plurality of vertical frame members 34, 34...
6. A horizontal bottom plate 37 is used, and in the illustrated example, the burnable poison rod 41 is installed on the horizontal top plate 3.
5. An upper hole 38 bored in the horizontal middle plate 36,
The lower end plug 4 1a passes through the middle through hole 39 and is supported by the horizontal bottom plate 37, and the large diameter and short thimble plug 4 2 passes through the upper through hole 38 and is supported by the lower end plug 4 2a. is adapted to be engaged and supported by the middle through hole 39 of the lateral middle plate 36.

このようにして原子燃料内挿物構造体1が水中
にて安定的に静置されたならば、既知のように原
子燃料内挿物4の上部端栓4aを、第2図に明示
する如く上部構造物2の端板3に取着しているナ
ツト40の取外しを行なうのであり、この際端板
3の角孔41に上部端栓4aの段縁42から突設
せる嵌合胴部43が嵌合しており、端板3から上
向きに突設している当該端栓4aの螺杆部30に
は筒部44付きのナツト40が螺着され、筒部4
4は螺杆部30の切欠45にあつてかしめられて
いるので、当該ナツト40に所定のトルクをかけ
て螺回させれば、切欠45にかしめられている回
り止めの筒部44は被壊され、原子燃料内挿物4
は嵌合胴部43の角孔41への嵌合により回り止
めとなつているから、上記ナツト40を取り外す
ことができる。
Once the nuclear fuel insert structure 1 has been stably placed in water in this way, the upper end plug 4a of the nuclear fuel insert 4 can be opened as shown in FIG. The nut 40 attached to the end plate 3 of the upper structure 2 is removed, and at this time, the fitting body 43 protruding from the step edge 42 of the upper end plug 4a is inserted into the square hole 41 of the end plate 3. A nut 40 with a cylindrical portion 44 is screwed onto the threaded rod portion 30 of the end plug 4a that is fitted and protrudes upward from the end plate 3.
4 is placed in the notch 45 of the threaded rod portion 30 and is caulked, so if a predetermined torque is applied to the nut 40 and the nut 40 is screwed, the anti-rotation cylindrical portion 44 that is caulked in the notch 45 will not be damaged. , nuclear fuel interpolant 4
Since the nut 40 is prevented from rotating by fitting into the square hole 41 of the fitting body 43, the nut 40 can be removed.

尚こゝで第2図のbに示したものは、原子燃料
内挿物4の上部端栓4aに螺着したナツト40の
回り止め手段が前記のものと異なり、螺杆部30
に縦切した割溝46にピン47をナツト40に溶
接部48にて固定したものであるが、これまたナ
ツト40を螺回することで上記の溶接による固定
を破壊することができる。
The one shown in FIG. 2b is different from the above-mentioned one in that the locking means of the nut 40 screwed onto the upper end plug 4a of the nuclear fuel insert 4 is different from the one shown in FIG.
A pin 47 is fixed to a nut 40 by a welded portion 48 in a vertically cut groove 46, but the above-mentioned fixation by welding can be broken by screwing the nut 40.

このようにしてすべての原子燃料内挿物4につ
き、そのナツト40を外し終つたならば、上部構
造物2を前記ブリツジクレーンにより引き揚げる
ことによつて、前記解体用保持装置33に原子燃
料内挿物4を残置させる。
After the nuts 40 of all the nuclear fuel inserts 4 have been removed in this way, the superstructure 2 is lifted up by the bridge crane, and the nuclear fuel inserts are placed in the holding device 33 for disassembly. Leave insert 4 behind.

そこで使用済みのバーナブルポイズン棒41だ
けを、本考案による装置により引き揚げ、前記の
如く所望箇所に移送することになるが、それには
吊持部8のUボルト13を用いて建家内のブリツ
ジクレーン等により装置全体を吊持し、これを水
中残置の原子燃料内挿物たるバーナブルポイズン
棒41の直上から降下させるが、この際前記した
把手付ナツト18を回動することにより外筒10
を上動位置に配しておき、従つて外筒10のスリ
ーブ10′も上位にあつて、その押圧テーパ面3
1は受圧テーパ面32から離れて第4図の二点鎖
線位置にあり、これによりコレツトチヤツク27
の拡開状態にある挾持端口26に、バーナブルポ
イズン棒41の上部端栓4aにおける螺杆部30
を嵌入させ、次いで前記把手付ナツト18を逆方
向に回動操作する。
Therefore, only the used burnable poison rod 41 is lifted up by the device according to the present invention and transferred to the desired location as described above. The entire device is suspended by a Tsuji crane or the like and lowered from directly above the burnable poison rod 41 , which is the nuclear fuel inserted in the water. Cylinder 10
is placed in the upward movement position, and therefore the sleeve 10' of the outer cylinder 10 is also placed in the upper position, and its pressing tapered surface 3
1 is located away from the pressure-receiving tapered surface 32 at the position indicated by the two-dot chain line in FIG.
The threaded rod portion 30 of the upper end plug 4a of the burnable poison rod 41 is inserted into the clamping end port 26 which is in the expanded state.
, and then rotate the handle nut 18 in the opposite direction.

この操作により前記の通り外筒10が回り止め
状態で下動するからスリーブ10′の押圧テーパ
面31が受圧テーパ面32に摺接して、挾持爪2
5,25…を軸心側に押動させ挾持端口26が縮
径状態となるから、図示例では挾持爪25,25
…の螺子部29が螺杆部30に螺合状態となつて
コレツトチヤツク27による上部端栓4aの挾持
が行なわれる。
By this operation, the outer cylinder 10 moves downward in a non-rotating state as described above, so that the pressing tapered surface 31 of the sleeve 10' comes into sliding contact with the pressure receiving tapered surface 32, and the clamping claws 2
5, 25... are pushed toward the axis, and the clamping end opening 26 is brought into a reduced diameter state.
The threaded portion 29 of... is screwed into the threaded rod portion 30, and the upper end stopper 4a is held by the collection chuck 27.

次に前記ブリツジクレーンの操作により、当該
バーナブルポイズン棒41を解体用保持装置33
から引き揚げ所定収納容器等に当該放射性廃棄物
を移送するのである。
Next, by operating the bridge crane, the burnable poison rod 41 is moved to the demolition holding device 33.
The radioactive waste will be salvaged and transferred to a designated storage container.

かくしてバーナブルポイズン棒41の引き抜き
が終れば、新規なバーナブルポイズン棒を上記操
作により挾持して、解体用保持装置33に移送装
填し、当該装填作業が終れば、前記上部構造物2
をブリツジクレーンにより搬入し、解体用保持装
置33に立置されている原子燃料内挿物4の上部
端栓4aにおける嵌合胴部43に端板3の角孔4
1を嵌合させ、筒部44付きのナツト40を螺杆
部30に所定の工具にて螺着し、かつ切欠45で
の筒部かしめ作業を行なえば、再生の原子燃料内
挿物構造体が組立てられるから、当該構造体はブ
リツジクレーンにより、解体用保持装置33から
引き揚げ、原子燃料集合体に装填されることゝな
る。
When the burnable poison rod 41 has been pulled out in this manner, a new burnable poison rod is clamped by the above operation and transferred and loaded into the dismantling holding device 33, and when the loading operation is completed, the upper structure 2
The square hole 4 of the end plate 3 is brought in by a bridge crane, and the square hole 4 of the end plate 3 is inserted into the fitting body 43 of the upper end plug 4a of the nuclear fuel insert 4 placed upright in the holding device 33 for disassembly.
1, screw the nut 40 with the cylindrical part 44 onto the threaded rod part 30 with a predetermined tool, and perform the crimping work on the cylindrical part at the notch 45, the regenerated nuclear fuel insert structure can be completed. Once assembled, the structure is lifted from the dismantling holding device 33 by a bridge crane and loaded into a nuclear fuel assembly.

本考案は上記実施例によつて具現される通り、
ブリツジクレーン等により吊持可能とした吊持部
8には、把持杆9を垂設固定すると共に、把持用
操作部11を固設し、上記把持杆9に回り止め状
態にて被嵌した外筒10を、前記把持用操作部1
1にあつて外筒10に螺嵌された把手付ナツト1
8の回動操作により昇降動自在となし、把持杆9
の先端には複数個に分割された挾持爪25,25
…を設けることにより、原子燃料内挿物構造体1
の上部構造物2に装着される原子燃料内挿物4の
上部端栓4aが挿入可能な把持端口26を開口し
てコレツトチヤツク27を形成し、当該挾持爪2
5,25…の外周面には、前記把手付ナツト18
の回動操作により下動した外筒10の先端内周面
に形成されている押圧テーパ面31が摺接して、
当該挾持爪25,25…を把持端口26の縮径方
向に押動させる受圧テーパ面32を形成して構成
したものであるから、従来想到し得なかつた原子
燃料内挿物構造体の解体後にあつて、使用済みの
放射性廃棄物だけを取り出して廃棄することがで
き、上部構造物やシンブルプラグ等の再使用可能
部材を有効に活用することができる。
The present invention, as embodied by the above embodiments,
A gripping rod 9 is vertically fixed to the hanging portion 8, which can be lifted by a bridge crane or the like, and a gripping operation portion 11 is also fixed thereon, and is fitted onto the gripping rod 9 in a non-rotating state. The outer cylinder 10 is attached to the gripping operation section 1
A nut with a handle 1 screwed into an outer cylinder 10 in accordance with 1.
It can be moved up and down freely by rotating the gripping rod 9.
At the tip, there are gripping claws 25, 25 divided into multiple pieces.
By providing... nuclear fuel insert structure 1
A collection chuck 27 is formed by opening the gripping end opening 26 into which the upper end plug 4a of the nuclear fuel insert 4 attached to the upper structure 2 of the nuclear fuel insert 4 can be inserted.
The handle nut 18 is attached to the outer circumferential surface of 5, 25...
The pressing tapered surface 31 formed on the inner circumferential surface of the tip of the outer cylinder 10 that has moved downward due to the rotation operation slides into contact with the outer cylinder 10.
Since the clamping claws 25, 25... are formed with a pressure-receiving tapered surface 32 that pushes them in the diametrical direction of the gripping end opening 26, it is possible to eliminate the pressure-receiving taper surface 32 after dismantling the nuclear fuel insert structure, which was previously unimaginable. Therefore, only used radioactive waste can be taken out and disposed of, and reusable members such as the superstructure and thimble plug can be effectively utilized.

しかも吊持部8により垂持する遠隔操作によ
り、昇降また移送ができ、把手付ナツト18の回
動操作によつて原子燃料内挿物の上部端栓を遠隔
的安全位置における操作により迅速かつ確実に水
中にて把持することができ、放射性廃棄物の引き
揚げ移送と、新規な原子燃料内挿物の搬入が、不
本意に落下させてしまうといつた心配なしに能率
的に行ない得る。
In addition, it can be lifted, lowered, and transferred by remote control suspended by the hanging part 8, and by rotating the handle nut 18, the upper end plug of the nuclear fuel insert can be operated quickly and reliably from a remote safe position. It can be gripped underwater, allowing efficient removal of radioactive waste and installation of new nuclear fuel inserts without fear of accidental dropping.

尚本考案に係る装置を製作するにあたり、把持
杆、外筒は実際上十数mに及ぶ長尺なものとなる
ので、これらは適宜の接続部材により連設して形
成するのがよく、また外筒の昇降動を円滑にする
ため間隙空所に適宜数のガイド部材を介装するの
が望ましい。
In manufacturing the device according to the present invention, the gripping rod and outer cylinder will actually be long, reaching more than 10 meters, so it is best to connect them with appropriate connecting members, and In order to smoothly move the outer cylinder up and down, it is desirable to insert an appropriate number of guide members in the gap.

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

第1図は原子燃料内挿物構造体の一例を示した
正面図、第2図のa,bは同構造体にあつて原子
燃料内挿物の上部構造物への取着箇所を示した各
種例の一部切欠拡大斜視図、第3図は原子燃料内
挿物構造体を解体用保持装置に収納した状態の一
部切欠正面図、第4図は本考案に係る解体用原子
燃料内挿物遠隔把持移送装置の一実施例を示した
一部切欠の正面図である。 1……原子燃料内挿物構造体、2……上部構造
物、4……原子燃料内挿物、4a……上部端栓、
8……吊持部、9……把持杆、10……外筒、1
1……把持用操作部、12……端板、13……U
ボルト、17……ナツト受筒台、18……把手付
ナツト、19……螺筒、21……外筒の回り止め
機構、22……支持腕、23……昇降案内ピン、
24……ガイド環、25……挾持爪、26……把
持端口、27……コレツトチヤツク、31……押
圧テーパ面、32……受圧テーパ面。
Fig. 1 is a front view showing an example of a nuclear fuel insert structure, and Fig. 2 a and b show the attachment points of the nuclear fuel insert to the upper structure in the same structure. FIG. 3 is a partially cutaway front view of the nuclear fuel insert structure housed in the holding device for disassembly; FIG. 4 is a partially cutaway enlarged perspective view of various examples; FIG. FIG. 2 is a partially cutaway front view showing an embodiment of the insert remote grasping and transferring device. 1... Nuclear fuel insert structure, 2... Upper structure, 4... Nuclear fuel insert, 4a... Upper end plug,
8... Hanging part, 9... Gripping rod, 10... Outer cylinder, 1
1...Gripping operation unit, 12...End plate, 13...U
Bolt, 17... Nut receiver stand, 18... Nut with handle, 19... Screw tube, 21... Outer cylinder rotation prevention mechanism, 22... Support arm, 23... Lifting guide pin,
24... Guide ring, 25... Clamping claw, 26... Gripping end opening, 27... Collection chuck, 31... Pressing tapered surface, 32... Pressure receiving tapered surface.

Claims (1)

【実用新案登録請求の範囲】 (1) ブリツジクレーン等により吊持可能とした吊
持部には、把持杆を垂設固定すると共に、把持
用操作部を固設し、上記把持杆に回り止め状態
にて被嵌した外筒を、前記把持用操作部にあつ
て外筒に螺嵌された把手付ナツトの回動操作に
より昇降動自在となし、把持杆の先端には複数
個に分割された挾持爪を設けることにより、原
子燃料内挿物構造体の上部構造物に装着される
原子燃料内挿物の上部端栓が挿入可能な把持端
口を開口してコレツトチヤツクを形成し、当該
挾持爪の外周面には、前記把手付ナツトの回動
操作により下動した外筒の先端内周面に形成さ
れている押圧テーパ面が摺接して、当該挾持爪
を把持端口の縮径方向に押動させる受圧テーパ
面を形成してなる原子燃料内挿物構造体の解体
用原子燃料内挿物遠隔把持移送装置。 (2) 吊持部は端板にUボルトを上向きに突設して
なり、把持用操作部は上記端板に下設したナツ
ト受筒台と、当該受筒台に回動操作自在なるよ
う載受された把手付ナツトと、当該ナツトに螺
嵌され外筒に固着の螺筒を具備し、外筒の回り
止め機構は外筒に構向固定した支持腕と、当該
支持腕から植立されて前記ナツト受筒台から突
設されたガイド環に装入された昇降案内ピンと
により構成されている実用新案登録請求の範囲
第1項記載の原子燃料内挿物構造体の解体用原
子燃料内挿物遠隔把持移送装置。
[Scope of Claim for Utility Model Registration] (1) A gripping rod is vertically fixed to a lifting part that can be lifted by a bridge crane, etc., and a gripping operation part is fixedly installed, and a lifting part that can be lifted by a bridge crane, etc. The outer cylinder fitted in the stopped state can be freely moved up and down by rotating a nut with a handle that is screwed into the outer cylinder in the gripping operation part, and the gripping rod is divided into a plurality of pieces at the tip. By providing a clamping claw with a handle, a gripping end opening into which the upper end plug of the nuclear fuel insert attached to the upper structure of the nuclear fuel insert structure can be inserted is opened to form a collector chuck, and the clamping The pressing tapered surface formed on the inner circumferential surface of the tip of the outer cylinder that has been moved downward by the rotation of the handle nut comes into sliding contact with the outer circumferential surface of the claw, and the gripping claw is moved in the diameter-reducing direction of the gripping end opening. A remote grasping and transferring device for a nuclear fuel insert for dismantling a nuclear fuel insert structure, which is formed with a pressure-receiving tapered surface to be pushed. (2) The hanging part is formed by a U-bolt protruding upward from the end plate, and the gripping operation part is attached to a nut receiving stand installed below the end plate, so that it can be rotated freely. A nut with a handle mounted thereon, a screw thread screwed into the nut and fixed to the outer cylinder, and a rotation prevention mechanism of the outer cylinder include a support arm fixed to the outer cylinder and a support arm that is raised from the support arm. and a lifting guide pin inserted into a guide ring protruding from the nut receiver base, the nuclear fuel for dismantling a nuclear fuel insert structure according to claim 1 Insert remote grasping and transfer device.
JP1982152996U 1982-10-08 1982-10-08 Remote gripping and transfer device for nuclear fuel debris for dismantling nuclear fuel debris structures Granted JPS5958395U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1982152996U JPS5958395U (en) 1982-10-08 1982-10-08 Remote gripping and transfer device for nuclear fuel debris for dismantling nuclear fuel debris structures

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1982152996U JPS5958395U (en) 1982-10-08 1982-10-08 Remote gripping and transfer device for nuclear fuel debris for dismantling nuclear fuel debris structures

Publications (2)

Publication Number Publication Date
JPS5958395U JPS5958395U (en) 1984-04-16
JPS643105Y2 true JPS643105Y2 (en) 1989-01-26

Family

ID=30338617

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1982152996U Granted JPS5958395U (en) 1982-10-08 1982-10-08 Remote gripping and transfer device for nuclear fuel debris for dismantling nuclear fuel debris structures

Country Status (1)

Country Link
JP (1) JPS5958395U (en)

Also Published As

Publication number Publication date
JPS5958395U (en) 1984-04-16

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