JP2001310222A - Screw member remote fastening device of in-pile structure of nuclear reactor - Google Patents
Screw member remote fastening device of in-pile structure of nuclear reactorInfo
- Publication number
- JP2001310222A JP2001310222A JP2000131412A JP2000131412A JP2001310222A JP 2001310222 A JP2001310222 A JP 2001310222A JP 2000131412 A JP2000131412 A JP 2000131412A JP 2000131412 A JP2000131412 A JP 2000131412A JP 2001310222 A JP2001310222 A JP 2001310222A
- Authority
- JP
- Japan
- Prior art keywords
- socket
- main body
- body block
- gear
- tie rod
- 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.)
- Pending
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【発明の属する技術分野】本発明は構造物の締結に使用
されるねじ部材の締付装置に関し、特に原子炉炉内構造
物のねじ部材の遠隔締付装置に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a device for fastening a screw member used for fastening a structure, and more particularly to a device for remotely fastening a screw member of a reactor internal structure.
【0002】[0002]
【従来の技術】機械構造物において、構成部材間の締結
にボルトや少なくとも一端部にねじ加工されたタイロッ
ド等が使用される例が多い。而して、このようなボルト
やタイロッドでは、ナット等の締め付けによって発生し
た引張応力に応じた力により、部材同士を締結するもの
であるが、長期間使用すると応力緩和現象が生じて初期
締付力が低下することがある。最近の加圧水型原子炉に
おいて、組立構造の中性子反射体の使用が提案されてい
る。而して、このような組立構造の中性子反射体におい
て、締結に使用されるタイロッドは中性子の照射を受
け、高温条件下で使用されるので、その傾向は著しいも
のがある。従って、適宜増し締めを行って初期の締付力
を回復し、維持する必要がある。2. Description of the Related Art In mechanical structures, bolts and tie rods having at least one end threaded are often used for fastening components. In such bolts and tie rods, the members are fastened to each other by a force corresponding to the tensile stress generated by tightening the nut or the like. Power may decrease. In recent pressurized water reactors, the use of neutron reflectors in an assembled structure has been proposed. In the neutron reflector having such an assembled structure, the tie rod used for fastening is irradiated with neutrons and is used under high-temperature conditions. Therefore, it is necessary to restore and maintain the initial tightening force by appropriately performing additional tightening.
【0003】[0003]
【発明が解決しようとする課題】而して、上述のような
中性子反射体は、原子炉容器内の炉心を取り囲む炉内構
造物の一部として構成されているから、原子炉の運転開
始後はそれ自体放射化している可能性がある。このた
め、周囲は高放射線雰囲気となり、被爆防止の観点から
作業員の接近は難しく、その増し締め作業は簡単には実
施できない。又、炉内構造物を原子炉容器外に出すとし
ても、作業員の放射線被曝を効果的に防ぐ意味から、相
当の水深の遮蔽水内に保持してロッド類の増し締めを行
う必要がある。しかしながら、このような水中で増し締
め作業を信頼性良く遠隔的に行える装置が未だ開発され
ていなかった。従って、本発明の課題は、中性子反射体
のタイロッドの様な原子炉炉内構造物のねじ部材を遠隔
的に廻して、初期の締付力を回復せしめ得る締付装置を
提供することである。Since the above-mentioned neutron reflector is constituted as a part of the reactor internal structure surrounding the core in the reactor vessel, the neutron reflector is used after the start of operation of the reactor. May itself be activated. For this reason, the surroundings are in a high radiation atmosphere, and it is difficult for workers to approach from the viewpoint of the prevention of exposure, and the retightening work cannot be easily performed. Also, even if the reactor internals are taken out of the reactor vessel, it is necessary to retighten the rods while keeping them in shielded water at a considerable depth in order to effectively prevent radiation exposure of workers. . However, a device capable of performing such retightening work remotely underwater with high reliability has not yet been developed. Accordingly, an object of the present invention is to provide a tightening device capable of recovering an initial tightening force by remotely turning a screw member of a reactor internal structure such as a tie rod of a neutron reflector. .
【0004】[0004]
【課題を解決するための手段】上述の課題を達成するた
め、本発明によれば、クレーンなどに垂下されるように
構成される遠隔締付装置は、本体ブロック、同本体ブロ
ックに互いに平行に貫設された回転自在の回転軸とソケ
ット、前記回転軸に連結され上方へ延びる回転操作軸、
前記ソケットに連結され上方へ延びるソケット操作軸、
前記本体ブロックの上部に設けられ前記ソケットを上向
きに引き上げるピストンシリンダ機構、及び前記ソケッ
トの下部に嵌合された歯車を含み前記回転軸に連絡した
ナット駆動機構を有して構成され、前記ソケットは原子
炉炉内構造物の締付対象ねじ部材であるタイロッドに螺
合するねじ面を下部内周面に形成している。According to the present invention, there is provided, in accordance with the present invention, a remote tightening device adapted to be suspended by a crane or the like, comprising: a main body block; A rotatable rotation shaft and a socket penetrated, a rotation operation shaft connected to the rotation shaft and extending upward,
A socket operation shaft connected to the socket and extending upward,
A piston cylinder mechanism provided at an upper part of the main body block to lift the socket upward, and a nut drive mechanism including a gear fitted to a lower part of the socket and connected to the rotation shaft, wherein the socket is A screw surface to be screwed to a tie rod, which is a screw member to be tightened, of the reactor internal structure is formed on a lower inner peripheral surface.
【0005】[0005]
【発明の実施の形態】以下添付の図面を参照して本発明
の実施形態を説明する。先ず、本実施形態に係る装置に
よって増し締めが行われる加圧水型原子炉の中性子反射
体を含む炉内構造物の構造を図1及び図2を参照して説
明する。図において、炉心槽1は円形の断面をした構造
物で、図示しない原子炉容器乃至原子炉圧力容器の中に
垂下して保持される。炉心槽1の外側には、環状の原子
炉冷却材下降空間所謂ダウンカマーが画成される。炉心
槽1の下部は、原子炉容器により横方向に支持される
が、内部には下部炉心板3が横方向に展延して設けられ
ている。炉心槽1の内部の中心部であって下部炉心板3
の上方に、図示しない多数の燃料集合体が並べて装荷さ
れ、炉心5を形成する。このような炉心を取り囲む中性
子反射体7が炉心槽1の内側に設けられ、下部炉心板3
に固定、支持される。中性子反射体7の平面形状は、特
に図1に示すように炉心5の中心軸を中心にして点対称
となっているが、多数のフローホール9が鉛直方向に延
びて穿設されている。フローホール9は、前述の冷却材
の一部を貫流させるもので、ガンマ加熱などによる温度
上昇を抑制する。中性子反射体7は、特に図2で明らか
なように、同様な平面形状を持つ板状構造体を多数積み
重ねて構成され、これらに貫通された複数のタイロッド
11がナット13により締め付けられて一体化され、下
部炉心板3に固定されている。原子炉の運転時には、上
部炉心板15を含む上部炉内構造物が取り付けられる。Embodiments of the present invention will be described below with reference to the accompanying drawings. First, a structure of a reactor internal structure including a neutron reflector of a pressurized water reactor in which retightening is performed by the apparatus according to the present embodiment will be described with reference to FIGS. 1 and 2. In the drawing, a reactor core vessel 1 is a structure having a circular cross section, and is suspended in a reactor vessel or a reactor pressure vessel (not shown). An annular reactor coolant descending space, so-called downcomer, is defined outside the core vessel 1. The lower portion of the core vessel 1 is supported laterally by a reactor vessel, and a lower core plate 3 is provided in the interior so as to extend in the lateral direction. The lower core plate 3 which is a central part of the inside of the core tank 1
A large number of fuel assemblies (not shown) are loaded side by side to form a core 5. A neutron reflector 7 surrounding such a core is provided inside the core vessel 1 and the lower core plate 3
Fixed to and supported by The plan shape of the neutron reflector 7 is point-symmetric with respect to the center axis of the reactor core 5 as shown in FIG. 1 in particular, but a number of flow holes 9 extend in the vertical direction. The flow hole 9 allows a part of the above-described coolant to flow through, and suppresses a temperature rise due to gamma heating or the like. The neutron reflector 7 is constituted by stacking a large number of plate-like structures having the same planar shape, as is apparent from FIG. 2, and a plurality of tie rods 11 penetrating therethrough are tightened by nuts 13 to be integrated. And is fixed to the lower core plate 3. During operation of the reactor, the upper reactor internal structure including the upper core plate 15 is attached.
【0006】次に図3乃至図6を参照して遠隔締付装置
20の構造を説明する。本装置は原子炉の運転開始前の
中性子反射体7の組立にも使用できるのであるが、運転
開始後の水中での増し締め作業時を中心にして説明す
る。遠隔締付装置20の本体ブロック21には、締付用
回転軸23が回転自在に設けられ、これはユニバーサル
継手25を介して回転操作軸27に連結されている。回
転操作軸27は、図示しない水面上まで鉛直方向に延
び、クレーンなどにより移動可能に支持されている。同
様に水面上まで延びたソケット操作軸29は、カップリ
ング31を介してソケット33に連結されている。ソケ
ット33は、中性子反射体7のタイロッド11の上端の
ねじ部に螺合できるようになっており、本体ブロック2
1内で回動自在且つ軸方向摺動自在となっている。更
に、ソケット33のシャンク部を取り囲んでシリンダブ
ロック35が設けられ、これは本体ブロック21の上面
に固定されている。シリンダブロック35の内側には2
段のシリンダ空間が画成され、この中にピストン37、
39がタンデム状態で配置されている。上方のピストン
39は、ロックナット41によりソケット33に固定さ
れているから、ソケット33はピストンストロークの範
囲内で本体ブロック21に対し軸方向に相対変位可能で
ある。図示されていないが、各シリンダ空間には、高圧
水を給排する水圧配管が連絡している。Next, the structure of the remote tightening device 20 will be described with reference to FIGS. Although this device can be used for assembling the neutron reflector 7 before the operation of the nuclear reactor, the explanation will be made mainly on the retightening work in water after the operation is started. The main body block 21 of the remote tightening device 20 is provided with a rotatable tightening rotary shaft 23, which is connected to a rotary operation shaft 27 via a universal joint 25. The rotary operation shaft 27 extends vertically to a water surface (not shown) and is movably supported by a crane or the like. Similarly, the socket operation shaft 29 extending to the surface of the water is connected to the socket 33 via the coupling 31. The socket 33 is adapted to be screwed into the threaded portion at the upper end of the tie rod 11 of the neutron reflector 7,
1 and is freely slidable in the axial direction. Further, a cylinder block 35 is provided surrounding the shank portion of the socket 33, and is fixed to the upper surface of the main body block 21. 2 inside the cylinder block 35
A step cylinder space is defined in which the piston 37,
39 are arranged in a tandem state. Since the upper piston 39 is fixed to the socket 33 by the lock nut 41, the socket 33 can be axially displaced relative to the main body block 21 within the range of the piston stroke. Although not shown, a hydraulic pipe for supplying and discharging high-pressure water is connected to each cylinder space.
【0007】一方、本体ブロック21の下面中央部には
中間支持軸43が突設され、これに中間歯車乃至第2歯
車45が回転自在に支持されている。第2歯車45は、
回転軸23の下端に取りつけられた第3歯車47と噛み
合い、更に第1歯車49と噛み合っている。第1歯車4
9はソケット33の下端部に嵌合され、更に上部が本体
ブロック21の下面空所乃至後述のガイドブロックに支
持されている。第1歯車49の下端部は又、タイロッド
11に螺合したナット13の上部に嵌合できるようにな
っている。図示した状態では、第1歯車49はナット1
3に係合し、回転軸23の回転は、第3歯車47、第2
歯車45、第1歯車49の順に伝えられ、ナット13を
回転できる。更に、特に図6に示すように、本体ブロッ
ク21の下面には、ソケット33の下端部及び第1歯車
49を囲むガイドブロック51が設けられ、ガイドブロ
ック51に並んでガイドピン53も突設されている。On the other hand, an intermediate support shaft 43 is protruded from the center of the lower surface of the main body block 21, and an intermediate gear or a second gear 45 is rotatably supported on the intermediate support shaft 43. The second gear 45 is
It meshes with a third gear 47 attached to the lower end of the rotating shaft 23, and further meshes with a first gear 49. First gear 4
Numeral 9 is fitted to the lower end of the socket 33, and the upper part is supported by the lower space of the main body block 21 or a guide block described later. The lower end of the first gear 49 can be fitted to the upper part of the nut 13 screwed to the tie rod 11. In the illustrated state, the first gear 49 is the nut 1
3, the rotation of the rotating shaft 23 is controlled by the third gear 47, the second
The gear 45 and the first gear 49 are transmitted in this order, and the nut 13 can be rotated. Further, as shown in FIG. 6 in particular, a guide block 51 surrounding the lower end of the socket 33 and the first gear 49 is provided on the lower surface of the main body block 21, and guide pins 53 are also protruded alongside the guide block 51. ing.
【0008】次に以上のような構成の遠隔締付装置20
の作用を説明する。前述したように、遠隔締付装置20
は図示しないクレーンなどにより吊り下げられているか
ら、これを操作し、目標とするタイロッド11に近づ
け、隣接する所定のフローホール9にガイドピン53を
挿入するようにして装置本体の概略位置決めを行う。こ
の状態では、装置20を中性子反射体7から少し浮かせ
た状態とする。この状態で、第1歯車49の内面とナッ
ト13をナット13に設けたキー17を介して嵌合する
ため、回転操作軸27を操作し、回転を回転軸23、第
3歯車47及び第2歯車45を介して第1歯車49に伝
え、互いの嵌合部を一致させる。その後遠隔締付装置2
0を中性子反射体7の上に着座させ、ソケット操作軸2
9を回転して、ソケット33をタイロッド11の上端部
にねじ込む。その後シリンダ空間に水圧を加えてピスト
ン37、39を上昇させ、ロックナット41で連結した
ソケット33を上昇させれば、タイロッド11に引張り
荷重が加わって伸びる。このようにすると、ナット13
は中性子反射体7の上面から離れ、容易に回転し易くな
る。この際、引張り荷重を初期締付力に等しくなるよう
に前記水圧を設定することにより、タイロッド11には
初期の締付力と等しい引張り荷重が作用する。Next, the remote tightening device 20 having the above-described configuration will be described.
The operation of will be described. As described above, the remote tightening device 20
Is suspended by a crane or the like (not shown), and is operated so as to approach the target tie rod 11 and insert the guide pin 53 into the adjacent predetermined flow hole 9 to roughly position the apparatus main body. . In this state, it is assumed that the device 20 is slightly lifted from the neutron reflector 7. In this state, the nut 13 is fitted to the inner surface of the first gear 49 via the key 17 provided on the nut 13, so that the rotation operation shaft 27 is operated to rotate the rotation shaft 23, the third gear 47 and the second gear 47. The signal is transmitted to the first gear 49 via the gear 45 so that the fitting portions of the gears match each other. Then remote tightening device 2
0 on the neutron reflector 7 and the socket operating shaft 2
9 is rotated to screw the socket 33 into the upper end of the tie rod 11. Thereafter, if the pistons 37 and 39 are raised by applying water pressure to the cylinder space and the socket 33 connected by the lock nut 41 is raised, the tie rod 11 is extended by a tensile load. By doing so, the nut 13
Is separated from the upper surface of the neutron reflector 7 and is easily rotated. At this time, by setting the water pressure so that the tensile load becomes equal to the initial tightening force, a tensile load equal to the initial tightening force acts on the tie rod 11.
【0009】次いで回転操作軸27を回転させ、ユニバ
ーサル継手25を介して回転軸23を締付方向に回転す
る。この回転角は、第3歯車47、第2歯車45を介し
て第1歯車49に伝えられ、第1歯車49がナット13
を回転する。ナット13の座面が中性子反射体7に接触
したとき、回転を止めると共にシリンダ空間に作用させ
ていた水圧を零にする。このようにすると、タイロッド
11には前述の引張り荷重が作用した儘となり、即ち初
期の締付力が再び与えられたことになる。この状態で遠
隔締付装置20を上方に引き上げれば、当該タイロッド
11の増し締めが完了したこととなる。増し締めを必要
とする他のタイロッド11に前述の操作を繰り返せば、
中性子反射体7のタイロッド11の増し締めが完了した
こととなる。Next, the rotary operation shaft 27 is rotated to rotate the rotary shaft 23 via the universal joint 25 in the tightening direction. This rotation angle is transmitted to the first gear 49 via the third gear 47 and the second gear 45, and the first gear 49
To rotate. When the bearing surface of the nut 13 contacts the neutron reflector 7, the rotation is stopped and the water pressure acting on the cylinder space is reduced to zero. In this manner, the tie rod 11 is still subjected to the above-described tensile load, that is, the initial tightening force is applied again. If the remote tightening device 20 is pulled up in this state, the retightening of the tie rod 11 is completed. If the above operation is repeated for other tie rods 11 that need to be retightened,
This means that the tightening of the tie rod 11 of the neutron reflector 7 has been completed.
【0010】[0010]
【発明の効果】以上説明したように本発明によれば、遠
隔締付装置20をクレーンなどにより垂下し支持し、タ
イロッド11に上方から接近してソケットをタイロッド
11に螺合させて引張り、遠隔的に回転される歯車の内
面をナットに嵌合させて回転すれば良いから、炉内構造
物の一部であるタイロッド11の増し締めを遠隔的に容
易に行うことができる。As described above, according to the present invention, the remote tightening device 20 is suspended and supported by a crane or the like, and the tie rod 11 is approached from above and the socket is screwed to the tie rod 11 to pull it. It is only necessary to fit the inner surface of the gear to be rotated to the nut and rotate it, so that the tightening of the tie rod 11, which is a part of the furnace internal structure, can be easily performed remotely.
【図1】本発明の装置によりねじ部材の締付が行われる
炉内構造物の一例を示す上面図である。FIG. 1 is a top view showing an example of a furnace internal structure in which a screw member is tightened by an apparatus of the present invention.
【図2】図1のII-II線に沿う部分立断面図である。FIG. 2 is a partial vertical sectional view taken along line II-II of FIG.
【図3】本発明の実施形態に係る遠隔締付装置の主要部
を示す部分立断面図である。FIG. 3 is a partial vertical sectional view showing a main part of the remote fastening device according to the embodiment of the present invention.
【図4】図3のIV-IV線に沿う部分平断面図である。FIG. 4 is a partial plan sectional view taken along the line IV-IV in FIG. 3;
【図5】図3のV-V線に沿う部分平断面図である。FIG. 5 is a partial plan sectional view taken along line VV of FIG. 3;
【図6】図3のVI-VI線に沿う部分立断面図である。FIG. 6 is a partial vertical sectional view taken along line VI-VI of FIG. 3;
7 中性子反射体 9 フローホール 11 タイロッド 13 ナット 20 遠隔締付装置 21 本体ブロック 23 回転軸 25 ユニバーサル継手 27 回転操作軸 29 ソケット操作軸 33 ソケット 35 シリンダブロック 37、39 ピストン 41 ロックナット 43 中間支持軸 45 第2歯車 47 第3歯車 49 第1歯車 51 ガイドブロック 53 ガイドピン Reference Signs List 7 neutron reflector 9 flow hole 11 tie rod 13 nut 20 remote tightening device 21 body block 23 rotation shaft 25 universal joint 27 rotation operation shaft 29 socket operation shaft 33 socket 35 cylinder block 37, 39 piston 41 lock nut 43 intermediate support shaft 45 Second gear 47 Third gear 49 First gear 51 Guide block 53 Guide pin
Claims (1)
平行に貫設された回転自在の回転軸とソケット、前記回
転軸に連結され上方へ延びる回転操作軸、前記ソケット
に連結され上方へ延びるソケット操作軸、前記本体ブロ
ックの上部に設けられ前記ソケットを上向きに引き上げ
るピストンシリンダ機構、及び前記ソケットの下部に嵌
合された歯車を含み前記回転軸に連絡したナット駆動機
構を有し、前記ソケットは締付対象ねじ部材に螺合する
ねじ面を下部内周面に有することを特徴とする原子炉炉
内構造物のねじ部材遠隔締付装置。1. A main body block, a rotatable rotary shaft and a socket penetrating through the main body block in parallel with each other, a rotary operation shaft connected to the rotary shaft and extending upward, and a socket operation connected to the socket and extending upward. A shaft, a piston-cylinder mechanism provided at an upper part of the main body block to lift the socket upward, and a nut drive mechanism including a gear fitted to a lower part of the socket and connected to the rotating shaft, wherein the socket is tightened. A screw member remote tightening device for a reactor internal structure, wherein a screw surface to be screwed to a screw member to be attached is provided on a lower inner peripheral surface.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2000131412A JP2001310222A (en) | 2000-04-28 | 2000-04-28 | Screw member remote fastening device of in-pile structure of nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2000131412A JP2001310222A (en) | 2000-04-28 | 2000-04-28 | Screw member remote fastening device of in-pile structure of nuclear reactor |
Related Child Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2009164919A Division JP2009241253A (en) | 2009-07-13 | 2009-07-13 | Screw member remote fastening device for structure in nuclear reactor furnace |
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CN103612115A (en) * | 2013-12-11 | 2014-03-05 | 成都海光核电技术服务有限公司 | Implanting machine for nuclear power plant reactor king bolt and method for implanting bolt |
CN104668928A (en) * | 2015-01-29 | 2015-06-03 | 杭州沃镭智能科技股份有限公司 | Assembly line for brake master cylinders of vacuum boosters |
CN114939851A (en) * | 2022-04-29 | 2022-08-26 | 中广核研究院有限公司 | Bolt screwing device, bolt weight balance control method and bolt dismounting method |
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2000
- 2000-04-28 JP JP2000131412A patent/JP2001310222A/en active Pending
Cited By (5)
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CN103612115A (en) * | 2013-12-11 | 2014-03-05 | 成都海光核电技术服务有限公司 | Implanting machine for nuclear power plant reactor king bolt and method for implanting bolt |
CN104668928A (en) * | 2015-01-29 | 2015-06-03 | 杭州沃镭智能科技股份有限公司 | Assembly line for brake master cylinders of vacuum boosters |
CN104668928B (en) * | 2015-01-29 | 2016-09-28 | 杭州沃镭智能科技股份有限公司 | A kind of master cylinder assembly line of vacuum booster |
CN114939851A (en) * | 2022-04-29 | 2022-08-26 | 中广核研究院有限公司 | Bolt screwing device, bolt weight balance control method and bolt dismounting method |
CN114939851B (en) * | 2022-04-29 | 2023-06-13 | 中广核研究院有限公司 | Bolt screwing device, bolt weight balance control method and bolt dismounting method |
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