JPH0321514Y2 - - Google Patents

Info

Publication number
JPH0321514Y2
JPH0321514Y2 JP1984169169U JP16916984U JPH0321514Y2 JP H0321514 Y2 JPH0321514 Y2 JP H0321514Y2 JP 1984169169 U JP1984169169 U JP 1984169169U JP 16916984 U JP16916984 U JP 16916984U JP H0321514 Y2 JPH0321514 Y2 JP H0321514Y2
Authority
JP
Japan
Prior art keywords
core structure
control rod
drive shaft
vertical rod
reactor
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
JP1984169169U
Other languages
Japanese (ja)
Other versions
JPS6184595U (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 JP1984169169U priority Critical patent/JPH0321514Y2/ja
Publication of JPS6184595U publication Critical patent/JPS6184595U/ja
Application granted granted Critical
Publication of JPH0321514Y2 publication Critical patent/JPH0321514Y2/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

  • Load-Engaging Elements For Cranes (AREA)

Description

【考案の詳細な説明】 [産業上の利用分野] 本考案は原子炉に関し、特にその原子炉圧力容
器内部の制御棒駆動軸及び炉心構造物を取り扱う
装置に関するものである。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a nuclear reactor, and particularly to a device for handling control rod drive shafts and core structures inside the reactor pressure vessel.

[従来の技術] 原子力発電所の定期検査の際、原子炉圧力容器
の上部蓋体を開き、上部炉心構造物から制御棒駆
動軸を引き抜いたり、上部炉心構造物へ制御棒駆
動軸を挿入したりするために、従来はそのための
工具を使用して1本づつ行つていたので、引き抜
き・挿入作業に長時間を要する問題があつた。こ
れを解消するため、制御棒駆動軸を集合体として
取り扱う原子炉制御棒駆動軸の搬出入装置が提案
されていたが、この搬出入装置では、制御棒駆動
軸のみを取り扱うため、炉心構造物を取り扱うた
めの取扱い装置が別に必要である。従つて、炉心
構造物取扱い装置及び制御棒駆動軸搬出入装置の
2つの装置を設置保管する場所を格納容器内に確
保しなければならないので、格納容器が大型にな
るだけでなく、装置が2つ必要なため製造コスト
が上昇する。また、これ等の装置の操作にはクレ
ーンが使用されるが、操作対象を炉心構造物取扱
い装置から取扱い装置に、或はその逆に変える場
合、その都度クレーンで吊り変える必要があり、
非常に操作性が悪い。
[Prior art] During periodic inspections of nuclear power plants, the upper lid of the reactor pressure vessel is opened and the control rod drive shafts are pulled out from the upper core structure or inserted into the upper core structure. Conventionally, a special tool was used to do this one by one, which resulted in the problem that the removal and insertion operations took a long time. To solve this problem, a reactor control rod drive shaft loading/unloading device that handles the control rod drive shaft as an assembly has been proposed, but this loading/unloading device handles only the control rod drive shaft, so Separate handling equipment is required. Therefore, it is necessary to secure a place within the containment vessel to install and store the two devices, the core structure handling device and the control rod drive shaft loading/unloading device. This increases manufacturing costs. In addition, cranes are used to operate these devices, but when changing the operation target from core structure handling equipment to handling equipment, or vice versa, it is necessary to change the equipment using a crane each time.
Very poor operability.

[考案が解決しようとする問題点] 従つて、従来の技術には、広い設置保管場所、
高い製造コスト、悪い操作性等の問題点があつ
た。本考案はこれ等の問題点を解決することを目
的とするものである。
[Problems to be solved by the invention] Therefore, the conventional technology requires a large installation and storage space,
There were problems such as high manufacturing costs and poor operability. The present invention aims to solve these problems.

[問題点を解決するための手段] この目的から本考案の取扱い装置は、原子炉圧
力容器内に垂下支持された炉心構造物と、炉心内
に挿入される制御棒駆動軸との双方を取り扱うこ
とができるように構成されており、該取扱い装置
は、炉心構造物の上面に載置される中空鉛直棒を
含む枠体と、前記制御棒駆動軸を把持する筒体を
有すると共に、前記枠体に固定された昇降装置に
連絡され、前記鉛直棒に上下動可能に取り付けら
れた昇降台と、前記中空鉛直棒に挿通され、前記
炉心構造物に係合自在な操作棒とを備える。
[Means for solving the problem] For this purpose, the handling device of the present invention handles both the reactor core structure suspended and supported within the reactor pressure vessel and the control rod drive shaft inserted into the reactor core. The handling device has a frame body including a hollow vertical rod placed on the top surface of the core structure, a cylinder body that grips the control rod drive shaft, and the handling device A lifting platform is connected to a lifting device fixed to the body and is attached to the vertical rod so as to be movable up and down, and an operating rod is inserted through the hollow vertical rod and can freely engage with the core structure.

[作用] この取扱い装置は、原子炉圧力容器の蓋体を取
り外した後に露出する炉心構造物の上面に置かれ
る。その際、中空鉛直棒内に挿通された操作棒を
炉心構造物に係合させることができる。一方、こ
の鉛直棒には、制御棒駆動軸を把持できる筒体及
び昇降装置を有する昇降台が上下動可能に設けら
れている。従つて、取扱い装置自体を上下動させ
れば炉心構造物を取り扱うことができ、昇降台を
上下動させれば制御棒駆動軸集合体を取り扱うこ
とができる。。
[Operation] This handling device is placed on the upper surface of the core structure exposed after removing the lid of the reactor pressure vessel. At that time, the operating rod inserted into the hollow vertical rod can be engaged with the core structure. On the other hand, this vertical rod is provided with a cylindrical body capable of gripping the control rod drive shaft and an elevating platform having an elevating device so as to be movable up and down. Therefore, the core structure can be handled by moving the handling device itself up and down, and the control rod drive shaft assembly can be handled by moving the lifting platform up and down. .

[実施例] 次に、本考案の好適な実施例を添付図面に関連
して詳細に説明する。
[Embodiments] Next, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings.

第1図は、原子炉圧力容器11の蓋体(図示せ
ず)を取り除くことによつて露出した上部炉心構
造物15のフランジ上面15bに載置された本考
案の取扱い装置を示している。該取扱い装置は、
複数本の鉛直棒1(図には左右2本を示す)と、
この鉛直棒1の上方部位に固定的に取り付けられ
た昇降装置据付け台2と、鉛直棒1の下方部位に
配設されたガイド環3とで枠体を構成している。
ガイド環3の適所には、貫通口を有するガイド部
13が設けられている。図示しない蓋体を取り除
いた後に露出する原子炉圧力容器11のフランジ
11aには、図示しないボルト穴があり、該ボル
ト穴に螺合したガイドスタツド14は、前記ガイ
ド部13の貫通口に挿通している。
FIG. 1 shows the handling device of the present invention placed on the flange top surface 15b of the upper core structure 15 exposed by removing the lid (not shown) of the reactor pressure vessel 11. The handling device is
Multiple vertical rods 1 (two on the left and right are shown in the figure),
A frame is constituted by a lifting device mounting base 2 fixedly attached to an upper portion of the vertical rod 1 and a guide ring 3 disposed at a lower portion of the vertical rod 1.
A guide portion 13 having a through hole is provided at a proper position of the guide ring 3. The flange 11a of the reactor pressure vessel 11, which is exposed after removing the lid (not shown), has a bolt hole (not shown), and the guide stud 14 screwed into the bolt hole is inserted into the through hole of the guide part 13. ing.

鉛直棒1には、上下の保持板4a及び4bによ
つて多数の制御棒駆動軸保護用筒体17を保持す
る昇降台4が上下動可能に設けられており、各筒
体17の上端には適宜の構造のものでよい制御棒
駆動軸把持装置18が設けられている。
The vertical rod 1 is provided with a vertically movable lifting platform 4 that holds a large number of control rod drive shaft protection cylinders 17 by means of upper and lower holding plates 4a and 4b. A control rod drive shaft gripping device 18 is provided, which may be of any suitable construction.

この昇降台4を駆動するため、枠体を構成する
据付け台2には、モータのような適宜の駆動源7
と、該駆動源7により駆動される伝動軸5に接続
されたギヤボツクス6とが設けられており、ま
た、同様に枠体を構成する鉛直棒1には、ギヤボ
ツクス6を介して回転駆動されるボールスクリユ
ー8の下端が回転自在に支持されている。該ボー
ルスクリユー8に螺合するナツト9は昇降台4に
固定されている。従つて、駆動源7を作動するこ
とによつて、昇降台4は筒体17と共に鉛直棒1
に沿つて上下動可能である。これ等の諸部材5〜
9が昇降台4の昇降装置を構成する。
In order to drive this elevating table 4, an appropriate drive source 7 such as a motor is provided on the installation table 2 constituting the frame.
and a gear box 6 connected to a transmission shaft 5 driven by the drive source 7. Similarly, the vertical rod 1 constituting the frame is rotatably driven via the gear box 6. The lower end of the ball screw 8 is rotatably supported. A nut 9 screwed onto the ball screw 8 is fixed to the lifting platform 4. Therefore, by operating the drive source 7, the lifting platform 4 moves along with the vertical rod 1 along with the cylindrical body 17.
It is possible to move up and down along the These various parts 5~
9 constitutes an elevating device for the elevating table 4.

前記鉛直棒1は中空体であり、その内部を操作
棒10が軸方向に延びている。各操作棒10の上
端には、取扱い装置のデツキ20から操作可能な
ハンドル10cが設けられている。鉛直棒1及び
操作棒10の下端A部の構造は第2図に示す通り
である。
The vertical rod 1 is a hollow body, and an operating rod 10 extends in the axial direction inside the vertical rod 1. A handle 10c that can be operated from the deck 20 of the handling device is provided at the upper end of each operating rod 10. The structure of the lower end A portion of the vertical rod 1 and the operating rod 10 is as shown in FIG.

第2図において、鉛直棒1の下端面は上部炉心
構造物15のフランジ上面15bに載置してい
る。操作棒10の最下端はねじ部10bになつて
おり、前述したハンドル10cの操作によつて上
部炉心構造物フランジのねじ穴15aに螺合でき
る。また、鉛直棒1の下端内部には突出部1aが
形成され、操作棒10のねじ部10b上方には拡
径部10aが形成されており、該突出部1a及び
拡径部10aが協働して操作棒10のストツパと
して機能する。
In FIG. 2, the lower end surface of the vertical rod 1 is placed on the flange upper surface 15b of the upper core structure 15. The lowermost end of the operating rod 10 is a threaded portion 10b, which can be screwed into a threaded hole 15a in the upper core structure flange by operating the handle 10c described above. Further, a protruding part 1a is formed inside the lower end of the vertical rod 1, and an enlarged diameter part 10a is formed above the threaded part 10b of the operating rod 10, and the protruding part 1a and the enlarged diameter part 10a cooperate with each other. It functions as a stopper for the operating rod 10.

次に、上述した構造を有する本考案の取扱い装
置の作動について説明する。
Next, the operation of the handling device of the present invention having the above-described structure will be explained.

第1図及び第2図において、原子炉圧力容器1
1の図示しない蓋体を取り除いた後、圧力容器1
1のフランジ11aにあるボルト穴にガイドスタ
ツド14を植え込む。然る後、吊り金具12をク
レーンで吊つて取扱い装置を原子炉圧力容器11
の上方へ運び降下させる。この時、ガイド環3の
ガイド部13にガイドスタツド14が挿入され、
取扱い装置の位置決めを行いながら、鉛直棒1の
下端面が上部炉心構造物15のフランジ上面15
bに安定的に載置する。
In Figures 1 and 2, reactor pressure vessel 1
After removing the lid body (not shown) of 1, the pressure vessel 1
The guide stud 14 is inserted into the bolt hole in the flange 11a of No. 1. After that, the lifting fitting 12 is lifted by a crane and the handling device is moved to the reactor pressure vessel 11.
carry it above and lower it. At this time, the guide stud 14 is inserted into the guide portion 13 of the guide ring 3,
While positioning the handling equipment, the lower end surface of the vertical rod 1 is aligned with the flange upper surface 15 of the upper core structure 15
Place it stably on b.

次に、操作棒10の上端ハンドル10cを回し
てねじ部10bを、操作棒10の拡径部10aの
底面が鉛直棒1の下端突出部1aに接触するま
で、上部炉心構造物15のフランジに設けたねじ
穴15aに挿入することによつて、取扱い装置を
上部炉心構造物15に螺合する。そして、昇降装
置を作動して昇降台4を下降せしめ、上部炉心構
造物15の上面より突出している制御棒駆動軸1
6の先端を制御棒駆動軸保護用の筒体17に挿入
させ、先端が把持装置18に達したところで昇降
台4を停止させる。その後、把持装置18を操作
して複数本の制御棒駆動軸16を把持してから、
昇降台4を上昇せしめ、第2図に示す位置まで制
御棒駆動軸16を取扱い装置の中に収納した後、
吊り金具12をクレーンで吊れば、制御棒駆動軸
16及び上部炉心構造物15を同時に所定の位置
に移動させることができる。
Next, turn the upper end handle 10c of the operating rod 10 to tighten the threaded portion 10b onto the flange of the upper core structure 15 until the bottom surface of the expanded diameter portion 10a of the operating rod 10 contacts the lower end protrusion 1a of the vertical rod 1. The handling device is screwed into the upper core structure 15 by inserting it into the provided screw hole 15a. Then, the elevating device is operated to lower the elevating table 4, and the control rod drive shaft 1 protruding from the upper surface of the upper core structure 15 is lowered.
6 is inserted into the cylindrical body 17 for protecting the control rod drive shaft, and when the tip reaches the gripping device 18, the lifting platform 4 is stopped. After that, after operating the gripping device 18 to grip the plurality of control rod drive shafts 16,
After raising the lifting platform 4 and storing the control rod drive shaft 16 in the handling device to the position shown in FIG.
If the hanging fitting 12 is lifted by a crane, the control rod drive shaft 16 and the upper core structure 15 can be moved to a predetermined position at the same time.

制御棒駆動軸16及び上部炉心構造物15を原
子炉圧力容器11内に挿入する場合は、取扱い装
置をガイドスタツド14により位置決めした後、
上記と逆の手順で操作を行えばよい。
When inserting the control rod drive shaft 16 and the upper core structure 15 into the reactor pressure vessel 11, after positioning the handling device with the guide stud 14,
You can perform the operation in the reverse order of the above.

また、下部炉心構造物19を取り扱う場合に
は、前述した上部炉心構造物15の取り扱い要領
に準じればよい。
In addition, when handling the lower core structure 19, the handling procedure for the upper core structure 15 described above may be followed.

[考案の効果] 以上の説明から明らかなように、本考案による
取扱い装置は、多数の制御棒駆動軸と炉心構造物
とを同時に取り扱うことができるので、2つの装
置が必要であつた従来の技術と比較して、設置保
管場所が狭くてすみ、製造コストは低廉であり、
また操作性がよい。しかも、作業時間の短縮にな
るので、作業員の被曝量が低減するなど極めて重
要な効果を奏するものである。
[Effects of the invention] As is clear from the above explanation, the handling device according to the present invention can handle a large number of control rod drive shafts and reactor core structures at the same time. Compared to technology, it requires less space for installation and storage, and the manufacturing cost is low.
It is also easy to operate. Furthermore, since the working time is shortened, the radiation exposure of workers is reduced, which is an extremely important effect.

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

第1図は、原子炉圧力容器の蓋体取り除くこと
によつて露出した上部炉心構造物のフランジ上面
に載置された本考案の取扱い装置を示す概略側面
図、第2図は、第1図のA部の拡大断面図であ
る。 1……鉛直棒、2……昇降装置据付け台、3…
…ガイド環、4……昇降台、5……伝動軸、6…
…ギヤボツクス、7……駆動源、8……ボールス
クリユー、9……ナツト、10……操作棒、11
……原子炉圧力容器、15……上部炉心構造物、
15a……上面、16……制御棒駆動軸、17…
…筒体、18……把持装置、19……下部炉心構
造物。
Fig. 1 is a schematic side view showing the handling device of the present invention placed on the upper surface of the flange of the upper core structure exposed by removing the cover of the reactor pressure vessel, and Fig. 2 is the same as Fig. 1. FIG. 2 is an enlarged sectional view of part A of FIG. 1... Vertical rod, 2... Lifting device installation stand, 3...
...Guide ring, 4... Lifting platform, 5... Transmission shaft, 6...
... Gearbox, 7 ... Drive source, 8 ... Ball screw, 9 ... Nut, 10 ... Operation rod, 11
...Reactor pressure vessel, 15...Upper core structure,
15a...Top surface, 16...Control rod drive shaft, 17...
... cylinder body, 18 ... gripping device, 19 ... lower core structure.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 原子炉圧力容器内に垂下支持された炉心構造物
と、炉心内に挿入される制御棒駆動軸とを取り扱
うものであつて、該炉心構造物の上面に載置され
る中空鉛直棒を含む枠体と、前記制御棒駆動軸を
把持する筒体を有すると共に、前記枠体に固定さ
れた昇降装置に連絡され、前記鉛直棒に上下動可
能に取り付けられた昇降台と、前記中空鉛直棒に
挿通され、前記炉心構造物に係合自在な操作棒と
を有する、原子炉における取扱い装置。
A frame that handles a reactor core structure that is suspended and supported within a reactor pressure vessel and a control rod drive shaft that is inserted into the reactor core, and that includes a hollow vertical rod that is placed on the top surface of the reactor core structure. a lifting platform having a cylindrical body that grips the control rod drive shaft, connected to a lifting device fixed to the frame body, and attached to the vertical rod so as to be movable up and down; A handling device in a nuclear reactor, comprising an operating rod that is inserted through the control rod and can be freely engaged with the reactor core structure.
JP1984169169U 1984-11-09 1984-11-09 Expired JPH0321514Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1984169169U JPH0321514Y2 (en) 1984-11-09 1984-11-09

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1984169169U JPH0321514Y2 (en) 1984-11-09 1984-11-09

Publications (2)

Publication Number Publication Date
JPS6184595U JPS6184595U (en) 1986-06-04
JPH0321514Y2 true JPH0321514Y2 (en) 1991-05-10

Family

ID=30726916

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1984169169U Expired JPH0321514Y2 (en) 1984-11-09 1984-11-09

Country Status (1)

Country Link
JP (1) JPH0321514Y2 (en)

Also Published As

Publication number Publication date
JPS6184595U (en) 1986-06-04

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