JPS645277B2 - - Google Patents

Info

Publication number
JPS645277B2
JPS645277B2 JP56004325A JP432581A JPS645277B2 JP S645277 B2 JPS645277 B2 JP S645277B2 JP 56004325 A JP56004325 A JP 56004325A JP 432581 A JP432581 A JP 432581A JP S645277 B2 JPS645277 B2 JP S645277B2
Authority
JP
Japan
Prior art keywords
tube
movable shaft
outer tube
neutron measurement
force transmitting
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
JP56004325A
Other languages
Japanese (ja)
Other versions
JPS57118197A (en
Inventor
Shigeru Watanabe
Taketoshi Murozumi
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 JP56004325A priority Critical patent/JPS57118197A/en
Publication of JPS57118197A publication Critical patent/JPS57118197A/en
Publication of JPS645277B2 publication Critical patent/JPS645277B2/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)
  • Measurement Of Radiation (AREA)

Description

【発明の詳細な説明】 この発明は、原子炉の炉心に挿入される中性子
計測管が案内管などに固着した場合に、固着を解
除するために使用する装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a device used to release a neutron measurement tube inserted into the core of a nuclear reactor from sticking to a guide tube or the like.

沸騰水形原子炉には原子炉圧力容器底部を貫通
して中性子計測管が内装される。この中性子計測
管は下部をインコア案内管に挿入して支持させて
いるが、原子炉運転中に炉内に持ち込まれるクラ
ツドなどの不純混入物が上記案内管と中性子計測
管との間に入り込むなどして中性子計測管が案内
管に固着する事態を想定しておく必要がある。こ
のような固着を生じると、定期点検時などにおい
て中性子計測管を交換する際に、炉上部側から中
性子計測管を吊り上げることができなくなること
が考えられる。
A boiling water reactor is equipped with a neutron measurement tube that penetrates the bottom of the reactor pressure vessel. This neutron measurement tube is supported by inserting its lower part into the in-core guide tube, but impurities such as crud brought into the reactor during reactor operation can get between the guide tube and the neutron measurement tube. It is necessary to assume the situation where the neutron measurement tube becomes stuck to the guide tube. If such sticking occurs, it may become impossible to lift the neutron measurement tube from the upper part of the reactor when replacing the neutron measurement tube during periodic inspection or the like.

この発明は上記事情にもとづきなされたもので
その目的とするところは、中性子計測管の固着を
生じた場合に、原子炉圧力容器の底部側から中性
子計測管に対し軸方向および周方向に直接外力を
与え、中性子計測管を傷めることなく固着を解除
できる中性子計測管の固着解除装置を提供するこ
とにある。
This invention was made based on the above circumstances, and its purpose is to apply direct external force to the neutron measurement tube from the bottom side of the reactor pressure vessel in the axial and circumferential directions when the neutron measurement tube becomes stuck. It is an object of the present invention to provide a fixation release device for a neutron measurement tube, which can release the fixation without damaging the neutron measurement tube.

以下この発明を図示する一実施例を参照して説
明する。図中1は中性子計測管である。この中性
子計測管1は、その下半部をインコア案内管2に
挿入し、また上半部を炉心支持板3と上部格子板
4との間の炉心領域Sに露出させてある。この炉
心領域Sには図示しない燃料集合体が装荷され
る。また上記中性子計測管1の頭部1aは下側の
本体部1bに対して突設自在に構成され、スプリ
ング5によつて突出方向に付勢されて上部格子板
4の係止凹部6に嵌合支持されている。7,8は
中性子計測管1の途中に設けた大径なガイド部で
あり、これらガイド部7,8はインコア案内管2
に対して自由に摺動できるようになつている。ま
た、インコア案内管2の下端部は原子炉圧力容器
10の底部を貫通して最下端部にハウジング11
を形成してある。そしてこのハウジング11の下
面には、シール材12を介してフランジ部13が
ボルト14によつて固定されている。これらハウ
ジング11およびフランジ部13に設けた貫通孔
15には中性子計測管1の下部が貫通している。
また中性子計測管1の下部の途中の外周面には雄
ねじ面16が形成されている。この雄ねじ面16
には、通常の原子炉運転中において図示しない締
付ナツトがねじ込まれ、フランジ部13の下面と
の間で中性子計測管1を下方に向つて締め付けて
いる。そしてこの締め付けによつて、フランジ部
13内に形成されているテーパ状のバルブシート
部17に中性子計測管1のシーリング段部18が
密着して、インコア案内管2内部の水密が保てる
ようになつている。また中性子計測管1の最下端
部には、センサーの端子を被う着脱自在なノーズ
ピース19が螺着されている。このノーズピース
19は中性子計測管1の交換時に螺着されるもの
であつて、交換後は取外されてセンサー端子に信
号ケーブルが接続される。
The present invention will be described below with reference to an illustrative embodiment. In the figure, 1 is a neutron measurement tube. The neutron measurement tube 1 has its lower half inserted into the in-core guide tube 2, and its upper half exposed in the core region S between the core support plate 3 and the upper grid plate 4. This core region S is loaded with fuel assemblies (not shown). Further, the head 1a of the neutron measuring tube 1 is constructed so as to be able to protrude from the lower main body 1b, and is biased in the protruding direction by a spring 5 to fit into the locking recess 6 of the upper grid plate 4. is supported. 7 and 8 are large-diameter guide sections provided in the middle of the neutron measurement tube 1, and these guide sections 7 and 8 are connected to the in-core guide tube 2.
It is designed to be able to slide freely against the surface. Further, the lower end of the in-core guide tube 2 penetrates the bottom of the reactor pressure vessel 10 and is connected to the housing 11 at the lowermost end.
has been formed. A flange portion 13 is fixed to the lower surface of the housing 11 with a sealing material 12 interposed therebetween by bolts 14. The lower part of the neutron measurement tube 1 passes through the through hole 15 provided in the housing 11 and the flange portion 13.
Further, a male threaded surface 16 is formed on the outer peripheral surface of the neutron measuring tube 1 in the middle of the lower part thereof. This male thread surface 16
During normal reactor operation, a tightening nut (not shown) is screwed into the flange portion 13 to tighten the neutron measuring tube 1 downward between the flange portion 13 and the lower surface of the flange portion 13. By this tightening, the sealing step part 18 of the neutron measurement tube 1 comes into close contact with the tapered valve seat part 17 formed in the flange part 13, and the inside of the in-core guide tube 2 can be kept watertight. ing. Further, a removable nose piece 19 that covers the terminal of the sensor is screwed onto the lowermost end of the neutron measurement tube 1. This nose piece 19 is screwed on when replacing the neutron measurement tube 1, and after replacement, it is removed and a signal cable is connected to the sensor terminal.

また、上記貫通孔15の開口部15aの内面に
はねじ部20を設けてあり、このねじ部20と上
記雄ねじ面16を利用して本願の固着解除装置2
5が取付けられるようになつている。以下この固
着解除装置25の構成について説明すると、26
は固定外管であつて、この固定外管26はその上
端部外周面に設けたねじ部を上記ねじ部20に螺
合させて締め付けることにより、フランジ部13
に液密に固定される。なお上記ねじ部20は奥側
が小径となるいわゆるテーパねじを採用して水密
性を高めてある。また固定外管26の下端部には
排水口27を設けてあり、この排水口27は図示
しないドレンホースを介してペデスタルのドレン
ピツトに連通させてある。さらに固定外管26の
最下端部にはスリーブ28が固定され、このスリ
ーブ28の外面には第1の力伝達体29が回転自
在に取着されている。この力伝達体29には周方
向に等間隔で複数の貫通孔30…が形成されてい
る。そしてこれら貫通孔30…には、後述する連
結ボルト41…が挿通され、ナツト31…をねじ
込んである。
Further, a threaded portion 20 is provided on the inner surface of the opening 15a of the through hole 15, and the fixing release device 2 of the present application utilizes this threaded portion 20 and the male threaded surface 16.
5 can be installed. The configuration of this fixing release device 25 will be explained below.
is a fixed outer tube, and this fixed outer tube 26 has a threaded portion provided on the outer circumferential surface of its upper end portion which is screwed into the threaded portion 20 and tightened to form a flange portion 13.
is fixed in a liquid-tight manner. The threaded portion 20 is a so-called tapered thread with a smaller diameter on the inner side to improve watertightness. Further, a drain port 27 is provided at the lower end of the fixed outer tube 26, and this drain port 27 is communicated with a drain pit of the pedestal via a drain hose (not shown). Further, a sleeve 28 is fixed to the lowermost end of the fixed outer tube 26, and a first force transmitting body 29 is rotatably attached to the outer surface of the sleeve 28. A plurality of through holes 30 are formed in the force transmitting body 29 at equal intervals in the circumferential direction. Connection bolts 41, which will be described later, are inserted into these through holes 30, and nuts 31 are screwed into them.

そして、上記固定外管26内に可動軸32が挿
通されている。この可動軸32の上部には、中性
子計測管1の下端部を挿入するパイプ状の内管部
32aが設けられている。この内管部32aの先
端内面には雌ねじ面33が形成されており、この
雌ねじ面33を中性子計測管1の雄ねじ面16に
螺合できるようになつている。34,34はこれ
ら固定外管26と可動軸32相互の液密を保つた
めのシール材である。さらに、可動軸32の下部
に形成した大径部32bには、スラスト軸受35
およびラジアル軸受36,37を介して第2の力
伝達体40が回転自在に取付けられている。この
力伝達体40の上面には連結ボルト41…が鉛直
に固定されている。そしてこれら連結ボルト41
…は上記した力伝達体29の貫通孔30…を挿通
して、ナツト31…を螺合させてある。すなわ
ち、これらナツト31…の螺進位置を変えること
により可動軸側の力伝達体40は昇降し、この移
動に伴なつて可動軸32が固定外管26に対して
軸線方向に移動するようになつている。すなわ
ち、これら力伝達体29,40および連結ボルト
41…とナツト31…等によつて軸方向駆動機構
38を構成している。42はゴミよけのカバーで
あつて、スラスト軸受35にゴミが入ることを防
止している。また、43は力伝達体40の下面を
覆うカバーであり、ボルト44,44によつて固
定されている。また、ラジアル軸受37はナツト
45によつて固定されている。また、可動軸32
との摺動面にはシール材46が取付けられてい
る。
A movable shaft 32 is inserted into the fixed outer tube 26. A pipe-shaped inner tube portion 32a into which the lower end portion of the neutron measurement tube 1 is inserted is provided at the upper portion of the movable shaft 32. A female threaded surface 33 is formed on the inner surface of the distal end of this inner tube portion 32a, and this female threaded surface 33 can be screwed into the male threaded surface 16 of the neutron measurement tube 1. Numerals 34 and 34 are sealing materials for maintaining fluid tightness between the fixed outer tube 26 and the movable shaft 32. Furthermore, a thrust bearing 35 is provided in the large diameter portion 32b formed at the lower part of the movable shaft 32.
A second force transmitting body 40 is rotatably mounted via radial bearings 36 and 37. Connecting bolts 41 are fixed vertically to the upper surface of this force transmitting body 40. And these connecting bolts 41
... are inserted through the through holes 30 of the force transmitting body 29 described above, and nuts 31 are screwed together. That is, by changing the screwing position of these nuts 31..., the force transmitting body 40 on the movable shaft side is raised and lowered, and along with this movement, the movable shaft 32 is moved in the axial direction with respect to the fixed outer tube 26. It's summery. That is, the force transmitting bodies 29, 40, the connecting bolts 41, the nuts 31, and the like constitute an axial drive mechanism 38. A dust cover 42 prevents dust from entering the thrust bearing 35. Further, 43 is a cover that covers the lower surface of the force transmitting body 40, and is fixed with bolts 44,44. Further, the radial bearing 37 is fixed by a nut 45. In addition, the movable shaft 32
A sealing material 46 is attached to the sliding surface between.

また、可動軸32の最下端部には断面を非円形
状たとえば角頭状に形成した可動軸回転用の操作
部47が設けられており、この操作部47をトル
クレンチ等の回動具で回わすことにより、回動軸
32が一体に回転するようになつている。
Further, at the lowermost end of the movable shaft 32, there is provided an operating section 47 for rotating the movable shaft, which has a non-circular cross-section, for example, a square head shape. By turning, the rotation shaft 32 rotates together.

次に上記一実施例装置の作用について説明す
る。原子炉の通常運転中は、固着解除装置25は
フランジ部13から取外されており、代りに図示
しない締付ナツトを雄ねじ面16に締めつけてあ
る。これによつて中性子計測管1のシーリング段
部18がバルブシート部17に圧着され、水密が
確保されている。また、ノーズピース19は取外
されていて、センサーの端子から信号ケーブルが
導出されている。
Next, the operation of the device of the above embodiment will be explained. During normal operation of the nuclear reactor, the unsticking device 25 is removed from the flange portion 13 and is instead tightened onto the externally threaded surface 16 by a tightening nut (not shown). As a result, the sealing step portion 18 of the neutron measurement tube 1 is pressed against the valve seat portion 17, and watertightness is ensured. Further, the nose piece 19 has been removed, and a signal cable has been led out from the terminal of the sensor.

そして定期点検時などにおいて中性子計測管1
を交換する場合は、上記締付ナツトを雄ねじ面1
6から取外し、信号ケーブルを外してノーズピー
ス19を取着する。そして燃料交換プラツトホー
ムに備わる補助ホイストに設けた機器取扱い装置
を炉心に吊り下ろしてゆき、中性子計測管1の頭
部1aに係合させ、この頭部1aをスプリング5
の弾発力に抗して本体部1b側に押し込むことに
よつて係止凹部6との嵌合が外れるから、ホイス
トを再び上昇させることにより中性子計測管1を
吊り出すことができる。しかしこのとき何らかの
原因で、たとえばシーリング段部18がバルブシ
ート部17に固着していたり、ガイド部7,8が
インコア案内管2の内面に固着していると、中性
子計測管1の吊り上げは困難となり、無理に吊り
上げようとすると中性子計測管1の破損を招くお
それがある。
Then, during periodic inspections, etc., the neutron measurement tube 1
When replacing the above tightening nut,
6, remove the signal cable, and attach the nose piece 19. Then, the equipment handling device installed on the auxiliary hoist provided on the fuel exchange platform is lowered into the reactor core, engaged with the head 1a of the neutron measurement tube 1, and this head 1a is attached to the spring 5.
The neutron measuring tube 1 can be lifted out by raising the hoist again by pushing it toward the main body 1b side against the elastic force of the neutron measuring tube 1, thereby disengaging the fitting from the locking recess 6. However, at this time, if for some reason, for example, the sealing step part 18 is stuck to the valve seat part 17 or the guide parts 7 and 8 are stuck to the inner surface of the in-core guide tube 2, it is difficult to lift the neutron measurement tube 1. Therefore, if you try to forcefully lift the neutron measurement tube 1, there is a risk that the neutron measurement tube 1 will be damaged.

したがつてこの場合に固着解除装置25を使用
する。まず可動軸先端の雌ねじ面33を中性子計
測管1の雄ねじ面16にねじ込む。このとき固定
外管26は自重によつて力伝達体29とともにカ
バー42上に載置している状態となり、固定外管
26の上端部とフランジ部13との間には広い隙
間が確保されているから、雌ねじ面33のねじ込
み作業を容易に行なえる。次いで、固定外管26
の先端ねじ部をフランジ部13のねじ部20に螺
合させて締付ける。そしてナツト31…を連結ボ
ルト41…に締め付けてゆき、力伝達体29,4
0相互の距離を縮める。こうすることによつて、
第2の力伝達体40は相対的に上昇するから、ス
ラスト軸受35を介して可動軸32は上昇力を受
ける。このためバルブシート部17からシーリン
グ段部18を浮き上がらせることができる。この
ときインコア案内管2内の炉水がバルブシート部
17を通つて固定外管26と可動軸32との間の
隙間に浸入するが、固定外管26は液密に取付け
てあるから、炉水が漏れることはない。
Therefore, in this case, the fixing release device 25 is used. First, the female threaded surface 33 at the tip of the movable shaft is screwed into the male threaded surface 16 of the neutron measurement tube 1. At this time, the fixed outer tube 26 is placed on the cover 42 together with the force transmitting body 29 due to its own weight, and a wide gap is secured between the upper end of the fixed outer tube 26 and the flange portion 13. Therefore, the screwing operation of the female thread surface 33 can be easily performed. Next, the fixed outer tube 26
The tip threaded portion of the flange portion 13 is screwed into the threaded portion 20 of the flange portion 13 and tightened. Then, the nuts 31... are tightened to the connecting bolts 41..., and the force transmitting bodies 29, 4
0 Shorten the distance between each other. By doing this,
Since the second force transmitting body 40 rises relatively, the movable shaft 32 receives a rising force via the thrust bearing 35. Therefore, the sealing step portion 18 can be raised from the valve seat portion 17. At this time, the reactor water in the in-core guide tube 2 passes through the valve seat part 17 and enters the gap between the fixed outer tube 26 and the movable shaft 32, but since the fixed outer tube 26 is installed in a liquid-tight manner, Water never leaks.

次いで可動軸32の操作部47にトルクレンチ
を嵌合させ、可動軸32を回わして中性子計測管
1を強制的に回動させる。これによつて中性子計
測管1の固着を解除できる。なお、上記トルクレ
ンチは、中性子計測管1を破損させない程度の安
全トルクでトルクを伝達できるようにしておく。
Next, a torque wrench is fitted to the operating portion 47 of the movable shaft 32, and the movable shaft 32 is rotated to forcibly rotate the neutron measurement tube 1. This makes it possible to release the fixation of the neutron measurement tube 1. Note that the torque wrench is designed to be able to transmit torque with a safe torque that does not damage the neutron measurement tube 1.

以上のようにして固着を解除でき、中性子計測
管1が充分滑らかに回るようになつたら、再びナ
ツト31…を弛めて中性子計測管1を降下させ、
バルブシート部17にシーリング段部18を密着
させて、セルフシールドさせる。そして排水口2
7に連なるドレンホース(図示せず)を通じて固
定外管26内の炉水をドレンピツトに排出する。
そして排水が終了したら固定外管26をフランジ
部13から取外し、下側の力伝達体40上に下ろ
す。次いで操作部47をレンチで回わして、固定
軸先端の雌ねじ面33と雄ねじ面16との螺合を
解除し、作業台上に固着解除装置25を下ろす。
そしてフランジ部13の開口部15aに図示しな
いドレン管を螺着することにより、中性子計測管
1の吊り上げが可能な標準スタイルになるから、
燃料交換プラツトホームに合図を送り、中性子計
測管1を吊り上げ、新たな中性子計測管と交換す
る。
When the fixation can be released as described above and the neutron measurement tube 1 can rotate sufficiently smoothly, loosen the nuts 31 again and lower the neutron measurement tube 1.
A sealing step part 18 is brought into close contact with a valve seat part 17 to achieve self-shielding. and drain port 2
The reactor water in the fixed outer pipe 26 is discharged to the drain pit through a drain hose (not shown) connected to the pipe 7.
When the drainage is completed, the fixed outer tube 26 is removed from the flange portion 13 and lowered onto the force transmitting body 40 on the lower side. Next, the operation part 47 is turned with a wrench to release the threaded engagement between the female threaded surface 33 and the male threaded surface 16 at the tip of the fixed shaft, and the fixing release device 25 is lowered onto the workbench.
By screwing a drain pipe (not shown) into the opening 15a of the flange portion 13, a standard style is created in which the neutron measurement tube 1 can be lifted.
A signal is sent to the fuel exchange platform to lift up the neutron measurement tube 1 and replace it with a new neutron measurement tube.

このように本実施例によれば、たとえ中性子計
測管1に固着を生じていても、中性子計測管1に
上昇力と回転力を直接与えて効果的に固着を解除
できるものである。また作業中に炉水が漏れるこ
ともなく、作業に伴なう被ばく量が少ない。ま
た、シーリング段部18をバルブシート部17か
ら浮き上がらせた状態で中性子計測管1を回転さ
せることができるから、バルブシート部17の損
傷を防止できる。
As described above, according to this embodiment, even if the neutron measuring tube 1 is stuck, the sticking can be effectively released by directly applying a lifting force and rotational force to the neutron measuring tube 1. Additionally, there is no leakage of reactor water during work, and the amount of radiation exposure associated with work is low. In addition, since the neutron measurement tube 1 can be rotated with the sealing step portion 18 raised above the valve seat portion 17, damage to the valve seat portion 17 can be prevented.

また、原子炉運転中に締付けナツトを螺合して
おく既設の雄ねじ面16をそのまま利用して可動
軸32を固定するものであるから、中性子計測管
1に新たな加工を施こす必要がないという利点も
ある。
Furthermore, since the movable shaft 32 is fixed by using the existing male threaded surface 16 into which a tightening nut is screwed during reactor operation, there is no need to perform any new processing on the neutron measurement tube 1. There is also an advantage.

なお上記実施例ではナツト31の螺進量を調節
することにより第2の力伝達体40を昇降させる
ように構成したが、たとえばこの力伝達体40の
上面に形成したねじ孔にボルトを進退自在に螺挿
し、このボルトの螺進量を変えることにより力伝
達体40を昇降させるようにしてもよい。要する
にこの発明は固定外管に対する可動軸の軸方向の
相対的位置を変化させることのできる軸方向駆動
機構を備えていればよい。したがつて、油圧ジヤ
ツキなどを使用して可動軸を軸方向に動かす機構
も採用可能である。
In the above embodiment, the second force transmitting body 40 is moved up and down by adjusting the amount of screwing of the nut 31. However, for example, it is possible to move the bolt into a threaded hole formed on the upper surface of the force transmitting body 40. The force transmitting body 40 may be raised and lowered by inserting a screw into the bolt and changing the amount of screwing of this bolt. In short, the present invention only needs to include an axial drive mechanism that can change the relative position of the movable shaft in the axial direction with respect to the fixed outer tube. Therefore, it is also possible to employ a mechanism that uses a hydraulic jack or the like to move the movable shaft in the axial direction.

この発明は以上説明したように、中性子計測管
に着脱自在に取付けた可動軸を介して中性子計測
管を直接軸方向および周方向に強制的に動かすこ
とができるようにしたものであり、単にホイスト
などで中性子計測管の上端部を把持して吊り上げ
る場合に比べて中性子計測管に損傷を与えること
なく固着を解除できる。また、インコア案内管フ
ランジ部の開口部に固定外管を液密に螺着するも
のであり、インコア案内管の液密を維持した状態
で作業を遂行できるから炉水の飛散を防止でき、
作業中の放射線被ばく量が少ないなど、固着を生
じた中性子計測管を能率良く安全に取り出する上
で効果的であり、ひいては原子炉の稼動率を向上
できるものである。
As explained above, this invention enables the neutron measurement tube to be forcibly moved directly in the axial direction and the circumferential direction via the movable shaft detachably attached to the neutron measurement tube, and is simply a hoist. Compared to the case where the upper end of the neutron measurement tube is grasped and lifted with a tool, the fixation can be released without damaging the neutron measurement tube. In addition, the fixed outer tube is liquid-tightly screwed into the opening of the inner-core guide tube flange, and work can be carried out while maintaining the inner-core guide tube liquid-tight, which prevents reactor water from scattering.
This method is effective in efficiently and safely removing stuck neutron measurement tubes, since the amount of radiation exposure during work is small, and the operating rate of the reactor can be improved.

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

図面はこの発明の一実施例を示す縦断面図であ
る。 1……中性子計測管、2……インコア案内管、
10……原子炉圧力容器、13……インコア案内
管フランジ部、15……貫通孔、15a……開口
部、16……雄ねじ面、25……固着解除装置、
26……固定外管、29……第1の力伝達体、3
2……可動軸、33……雌ねじ面、38……軸方
向駆動機構、40……第2の力伝達体、41……
連結ボルト、47……操作部。
The drawing is a longitudinal sectional view showing an embodiment of the present invention. 1... Neutron measurement tube, 2... In-core guide tube,
10...Reactor pressure vessel, 13...In-core guide pipe flange portion, 15...Through hole, 15a...Opening portion, 16...Male thread surface, 25...Fixing release device,
26... fixed outer tube, 29... first force transmitting body, 3
2... Movable shaft, 33... Female threaded surface, 38... Axial drive mechanism, 40... Second force transmission body, 41...
Connection bolt, 47...operation unit.

Claims (1)

【特許請求の範囲】 1 原子炉圧力容器底部に取付けられているイン
コア案内管フランジ部の開口部に上端部を着脱自
在にかつ液密に螺着する固定外管と、この外管内
に液密に挿入され外管に対して軸方向および周方
向に移動自在でかつ上端部内面に雌ねじ面を有し
この雌ねじ面を中性子計測管の下端部外周面に形
成されている雄ねじ面に着脱自在に螺着する可動
軸と、この可動軸を固定外管に対して軸方向に駆
動させる軸方向駆動機構と、上記可動軸に形成し
た可動軸回転用の操作部とを具備したことを特徴
とする中性子計測管の固着解除装置。 2 上記軸方向駆動機構は、固定外管に取着した
第1の力伝達体と、可動軸に取着した第2の力伝
達体と、これら2つの力伝達体相互を離間対向し
て連結する螺進量調節自在なボルト機構とからな
ることを特徴とする特許請求の範囲第1項記載の
中性子計測管の固着解除装置。
[Scope of Claims] 1. A fixed outer tube whose upper end is removably and liquid-tightly screwed into the opening of an in-core guide tube flange attached to the bottom of the reactor pressure vessel, and a fixed outer tube with a liquid-tight structure inside the outer tube. It is inserted into the neutron measuring tube and is movable in the axial and circumferential directions with respect to the outer tube, and has a female threaded surface on the inner surface of the upper end. It is characterized by comprising a movable shaft to which the movable shaft is screwed, an axial drive mechanism for driving the movable shaft in the axial direction with respect to the fixed outer tube, and an operating part for rotating the movable shaft formed on the movable shaft. Neutron measurement tube fixation release device. 2 The above-mentioned axial drive mechanism includes a first force transmitting body attached to a fixed outer tube, a second force transmitting body attached to a movable shaft, and a connection between these two force transmitting bodies with the two force transmitting bodies separated and facing each other. 2. A neutron measurement tube fixation release device according to claim 1, comprising a bolt mechanism that can freely adjust the amount of screw movement.
JP56004325A 1981-01-14 1981-01-14 Device of removing fixation of neutron measuring tube Granted JPS57118197A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56004325A JPS57118197A (en) 1981-01-14 1981-01-14 Device of removing fixation of neutron measuring tube

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56004325A JPS57118197A (en) 1981-01-14 1981-01-14 Device of removing fixation of neutron measuring tube

Publications (2)

Publication Number Publication Date
JPS57118197A JPS57118197A (en) 1982-07-22
JPS645277B2 true JPS645277B2 (en) 1989-01-30

Family

ID=11581292

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56004325A Granted JPS57118197A (en) 1981-01-14 1981-01-14 Device of removing fixation of neutron measuring tube

Country Status (1)

Country Link
JP (1) JPS57118197A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0213392B1 (en) * 1985-08-09 1990-02-28 Siemens Aktiengesellschaft Apparatus for mounting dry neutron thimble detectors and for cleaning their guide tubes in boiling water reactors
JPH055610Y2 (en) * 1985-12-23 1993-02-15
JP2003004858A (en) * 2001-06-26 2003-01-08 Nikkiso Co Ltd Filter cartridge holder

Also Published As

Publication number Publication date
JPS57118197A (en) 1982-07-22

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