JPS59164993A - Device of charging and discharging reactor control rod driveaxis - Google Patents

Device of charging and discharging reactor control rod driveaxis

Info

Publication number
JPS59164993A
JPS59164993A JP58039168A JP3916883A JPS59164993A JP S59164993 A JPS59164993 A JP S59164993A JP 58039168 A JP58039168 A JP 58039168A JP 3916883 A JP3916883 A JP 3916883A JP S59164993 A JPS59164993 A JP S59164993A
Authority
JP
Japan
Prior art keywords
control rod
reactor control
reactor
rod drive
drive shaft
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.)
Granted
Application number
JP58039168A
Other languages
Japanese (ja)
Other versions
JPH0423236B2 (en
Inventor
幸夫 多田
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP58039168A priority Critical patent/JPS59164993A/en
Publication of JPS59164993A publication Critical patent/JPS59164993A/en
Publication of JPH0423236B2 publication Critical patent/JPH0423236B2/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

  • Load-Engaging Elements For Cranes (AREA)
  • Elimination Of Static Electricity (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明は、原子炉制御棒駆動軸を炉内から搬出、炉内に
搬入する原子炉制御棒駆動軸の搬出入装置に関するもの
である。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor control rod drive shaft loading/unloading device for transporting a nuclear reactor control rod drive shaft from and into the reactor.

原子力発電所における定期検査の際には、発電プラント
を停止して原子炉から使用済燃料が取出され、それに先
立って原子炉の上部炉心構造物中の原子炉制御棒駆動軸
を引抜いて搬出し、また原子炉に核燃料を装入した後K
、上部炉心構造物中に搬入することが必要であるが、従
来は複数本の原子炉制御棒駆動軸を、工具を用いて1本
づつ引抜き搬出、搬入していたため、その搬出入に長時
間を要し極めて面倒な作業となる欠点があった。
During regular inspections at a nuclear power plant, the power plant is shut down and the spent fuel is removed from the reactor.Prior to this, the reactor control rod drive shaft in the upper core structure of the reactor is pulled out and transported. , and after charging nuclear fuel into the reactor, K
, it is necessary to carry them into the upper core structure, but conventionally, multiple reactor control rod drive shafts were pulled out and carried in one by one using a tool, so it took a long time to carry them in and out. This method has the disadvantage that it requires a lot of time and is extremely troublesome work.

本発明は、従来の原子炉制御棒駆動軸の搬出入装置にお
ける前記のような欠点を解消するために開発されたもの
であって、上下方向に延びた複数本の案内棒な有し原子
炉容器上に載置される移動枠、前記案内棒に嵌合し支持
されて昇降する昇降台、前耐移動枠上に装着された前記
昇降台の昇降駆動機構、および前記昇降台に所定間隔を
おいて配設された複数の原子炉制御棒駆動軸の掴持機構
を具備した点に特徴を有し、複数本の原子炉制御棒駆動
軸を同時に掴持して搬出入する構成により前記のような
欠点を解消した原子炉制御棒駆動軸の搬出入装置を供す
る点にある。
The present invention was developed in order to eliminate the above-mentioned drawbacks of the conventional nuclear reactor control rod drive shaft loading/unloading device, and is a nuclear reactor with a plurality of guide rods extending in the vertical direction. A moving frame placed on the container, a lifting platform that is fitted and supported by the guide rod and moves up and down, a lifting drive mechanism for the lifting table mounted on the front anti-movement frame, and a predetermined interval between the lifting tables. It is characterized in that it is equipped with a gripping mechanism for a plurality of reactor control rod drive shafts arranged at the same time. The object of the present invention is to provide a device for carrying in and out of a nuclear reactor control rod drive shaft that eliminates the above drawbacks.

本発明は、前記の構成になっており、上下方向に延びた
複数本の案内棒を有し原子炉容器上に載置される移動枠
、前記案内棒に嵌合し支持されて昇降する昇降台、前記
移動枠上に装着された前記昇降台の昇降駆動機構、およ
び前記昇降台に所定間隔をおいて配設された複数の原子
炉制御棒駆動軸の掴持機構を具備しているので、原子炉
容器上に前記移動枠を載置し昇降駆動機構により昇降台
を下降させると、複数の掴持機構によって上部炉心構造
物内の複数の原子炉制御棒駆動軸を同時に掴持てき、接
動台によって搬出できるとともに。
The present invention has the above-mentioned structure, and has a plurality of guide rods extending in the vertical direction and is placed on a reactor vessel, and a moving frame that is fitted and supported by the guide rods to move up and down. the platform, a lifting mechanism for driving the lifting table mounted on the moving frame, and a gripping mechanism for a plurality of reactor control rod drive shafts arranged at predetermined intervals on the lifting table. , when the moving frame is placed on the reactor vessel and the lifting platform is lowered by the lifting drive mechanism, the plurality of gripping mechanisms can simultaneously grip and hold the plurality of reactor control rod drive shafts in the upper reactor core structure; It can be carried out using the movable table.

逆操作により複数本の原子炉制御棒駆動軸を同時に上部
炉心構造物内に搬入、配置でき、原子炉容器上への移動
枠の載置、その位置決めKより、複数の前記掴持機構が
上部炉心構造物中の原子炉制御棒駆動軸上あるいはその
配置予定箇所上に正確に位置づけられ、昇降台の昇降操
作によって複数の原子炉制御棒駆動軸の掴持、炉内への
位置づけが極めて容易、迅速かつ正確に行われるととも
に。
By reverse operation, a plurality of reactor control rod drive shafts can be carried into and placed in the upper core structure at the same time, and by placing the moving frame on the reactor vessel and positioning it, the plurality of gripping mechanisms are placed in the upper core structure. It is precisely positioned on the reactor control rod drive shaft in the reactor core structure or on the planned location, and it is extremely easy to grasp and position multiple reactor control rod drive shafts in the reactor by raising and lowering the lifting platform. , as well as being done quickly and accurately.

複数本を同時に搬出入可能であって、原子炉制御棒駆動
軸の搬出入性能、信頼性および能率が著しく向上される
A plurality of rods can be carried in and out at the same time, and the performance, reliability, and efficiency of carrying in and out of the reactor control rod drive shaft are significantly improved.

以下、本発明の実施例を図示について説明する。Hereinafter, embodiments of the present invention will be described with reference to the drawings.

第1図、第2図に本発明の一実施例を示してお、す、図
中(alは原子炉(圧力)容器、(b)は原子炉容q(
al中の炉心槽、(c)は炉心槽(bl内の上部炉心構
造物、(d)は上部炉心構造物(al内に配設される複
数本の原子炉制御棒駆動軸であって、外周部に配設され
た複数本のガイドスタンド(1)、ガイドスタンド(1
)上部に設けた連結片(2)、上部に昇降駆動機構の据
付台(3)が取付けられた上下方向に延びる複数本の案
内棒(4)、連結片(6)によって前記ガイドスタン)
”(1)に取付げられたガイF’!(5)、および前記
案内棒(4)の上部に連結された吊金具(20)等に・
よって移動枠が構成され、該移動枠は、クレーン等で吊
金具−により吊持されて移動されるとともに、原子炉容
器(al上へ運ばれて、案内棒(4)の下端部に設けた
穴を上部炉心構造物(clのフランジに立設されたガイ
ドビンQυに嵌装し位置決めして載置し、ガイドスタン
F”(1)の下端は原子炉容器(a)のフランジ上に安
定される構造になっている。
An embodiment of the present invention is shown in Figs. 1 and 2.
(c) is the core tank (upper core structure in BL); (d) is the upper core structure (multiple reactor control rod drive shafts arranged in AL; Multiple guide stands (1) arranged on the outer periphery, guide stands (1)
) A connecting piece (2) provided at the top, a plurality of guide rods (4) extending in the vertical direction to which a lifting drive mechanism installation stand (3) is attached, and a connecting piece (6) to connect the guide stand)
``Guy F'! (5) attached to ``(1)'' and the hanging fitting (20) connected to the upper part of the guide rod (4), etc.
Therefore, a moving frame is constructed, and the moving frame is moved by being suspended by a hanging fitting by a crane or the like, and is also carried onto the reactor vessel (al) and attached to the lower end of the guide rod (4). Fit the hole into the guide bin Qυ installed upright on the flange of the upper core structure (cl), position and place it, and place the lower end of the guide stand F'' (1) stably on the flange of the reactor vessel (a). The structure is such that

さらに、昇降台(7)が前記移動枠の複数の案内棒(4
)にスリーブ(7a)の嵌合によって昇降自在に取付は
支持されているとともに、前記据付台(3)上には駆動
機(8)、駆動機(8)によって回転駆動、される伝導
軸(9)、伝導軸(9)の端部に連設されたギヤボック
スa@、ギヤボックス(10を介し回転駆動される縦設
されたボールスクリュー(11)、およびポールスゲリ
ューα1)K螺合し前記昇降台(7)側に固着されたナ
ツトa2とからなる昇降台(7)の昇降駆動機構が配設
されている。
Further, the lifting platform (7) is arranged so that the plurality of guide rods (4) of the moving frame
) is mounted and supported so as to be able to rise and fall freely by fitting the sleeve (7a), and on the installation base (3) is a drive machine (8), a transmission shaft ( 9), a gear box a @ connected to the end of the transmission shaft (9), a vertically installed ball screw (11) that is rotationally driven via the gear box (10), and a Paulsgelyu α1) K screw connection An elevating and lowering drive mechanism for the elevating table (7) is provided, which comprises a nut a2 fixed to the elevating table (7) side.

また、前記昇降台(7)には、複数の原子炉制御棒駆動
軸(dlの掴持機構(t3)が固設され、各掴持機構α
■は、上部炉心構造物(c)内に配設されている各原子
炉制御棒駆動軸(d)に相対するように所定間隔をおい
て配設されており、さらに、各掴持機構α国には、それ
ぞれ駆動軸保護筒Q4)が下側に一連状に縦設されてい
る。なお、図中(至)は移動枠の上部に装備された作業
台である。
Furthermore, a plurality of gripping mechanisms (t3) for reactor control rod drive shafts (dl) are fixedly installed on the lifting platform (7), and each gripping mechanism α
(2) are arranged at a predetermined interval so as to face each reactor control rod drive shaft (d) arranged in the upper core structure (c), and each gripping mechanism α In each case, a drive shaft protection tube Q4) is installed vertically in a series on the lower side. Note that (to) in the figure is a workbench installed at the top of the moving frame.

図示した実施例は、前記のような構成になっているので
、図示外のクレーンで吊金具(20により移動枠を吊持
し原子炉容器(a)上へ運び、各案内棒(4)の下部に
設けた穴を上部炉心構造物(clのフランジ側のガイド
ビン(21)に嵌装して位置決めし、移動枠を原子炉容
器上に正確に載置する。
Since the illustrated embodiment has the above-mentioned configuration, the movable frame is lifted by a crane (not shown) using the hanging fittings (20) and carried onto the reactor vessel (a), and each guide rod (4) is The hole provided in the lower part is fitted into the guide bin (21) on the flange side of the upper core structure (cl) for positioning, and the moving frame is accurately placed on the reactor vessel.

次に、昇降駆動機構の駆動機(8)により伝導軸(9)
ギヤボックスa0を介しボールスクリュー(LDを回転
させ、ボールスクリュー(L]+に螺合されているナラ
)Q21により昇降台(力を下降させると、上部炉心構
造物(al中に配設されその上面から突出している原子
炉制御棒駆動軸(d)のそれぞれの上部が、各駆動軸保
護筒Q4)内忙挿入され掴持機構(1謙に至った時点で
昇降台(7)を停止し、作業台(至)上の作業員が各掴
持機構Q3を操作して各原子炉制御棒駆動軸(d)の上
部を掴持することができ、さらに、前記昇降駆動機構の
逆駆動による昇降台(7)の上昇により各原子炉制御棒
駆動軸(d)を引抜いたのち、クレーン(図示省略)に
よって吊金具(20により移動枠を作業床面上の所定位
置に移動させて、複数の原子炉制御棒駆動軸(a)を同
時に搬出することができるとともに、前記の逆操作によ
って同時に原子炉容器(alの上部炉心構造物(al中
に搬入し配設することができる。
Next, the transmission shaft (9) is moved by the drive machine (8) of the lifting drive mechanism.
When the lifting platform (power is lowered) is lowered by the ball screw Q21 (rotating the LD and screwed into the ball screw (L)+) through the gear box a0, the upper core structure (located in the al When the upper part of each of the reactor control rod drive shafts (d) protruding from the upper surface is inserted into each drive shaft protection cylinder Q4) and the gripping mechanism (1) is reached, the elevator platform (7) is stopped. , the worker on the workbench (to) can operate each gripping mechanism Q3 to grip the upper part of each reactor control rod drive shaft (d), and furthermore, by the reverse drive of the lifting drive mechanism After pulling out each reactor control rod drive shaft (d) by raising the lifting platform (7), a crane (not shown) moves the movable frame to a predetermined position on the work floor using a hanging bracket (20), The reactor control rod drive shaft (a) of the reactor control rods (a) can be carried out at the same time, and by the above-mentioned reverse operation, they can be simultaneously carried into the upper core structure (AL) of the reactor vessel (AL) and arranged therein.

従って、前記実施例によれtス、原子炉容器(al上ヘ
の移動枠の載置、位置決めにより、複数の掴持機構α9
゛が上部炉心構造物(c)中の各原子炉制御棒駆動軸(
dl上、あるいは上部炉心構造物(c)上に正確に配置
され、昇降台(7)の昇降操作によって複数の原子炉制
御棒゛駆動軸(a)の掴持、炉内への位置づけが極めて
容易、迅速かつ正確に行われるとともに、複数本を同時
に搬出入可能であって、原子炉制御棒駆動軸(d)の搬
出入性能、信頼性およ□び作業能率が著しく向上され、
作業員の被曝量低減上極めて効果的である。
Therefore, according to the above embodiment, by placing and positioning the movable frame on the reactor vessel (Al), a plurality of gripping mechanisms α9
゛ is each reactor control rod drive shaft (
dl or on the upper core structure (c), and by lifting and lowering the lifting platform (7), it is possible to grasp multiple reactor control rods (drive shafts (a)) and position them within the reactor. It is easy, quick, and accurate, and multiple rods can be carried in and out at the same time, and the performance, reliability, and work efficiency of the reactor control rod drive shaft (d) are significantly improved.
It is extremely effective in reducing radiation exposure for workers.

以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものではな(、本発
明の精神な′逸脱しない範囲内で種々の設計の改変を施
しうるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to these embodiments (and that various design modifications may be made without departing from the spirit of the present invention). It is.

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

第1′図は本発明の一実施例を一部断面で系1側面図、
第2図は第1図の1−1部分の横断面間である。 a:原子炉容器 C:上部炉心構造物 d:原子炉制御
棒駆動軸 1ニガイドスタンド6:据付台 4:案内棒
 7:昇降台 8:駆動機 9:伝導軸 10:ギャボ
ックス11:ボールスクリュー 12:ナット16:掴
持機構 14:駆動軸保饅筒 2o:吊金具 60:作
業台 復代理人 弁理士 岡 本 重 文 外2名
Figure 1' is a side view of a system 1 with a partial cross section showing an embodiment of the present invention;
FIG. 2 is a cross-sectional view of the section 1-1 in FIG. a: Reactor vessel C: Upper core structure d: Reactor control rod drive shaft 1 Guide stand 6: Installation stand 4: Guide rod 7: Lifting platform 8: Drive machine 9: Transmission shaft 10: Gabox 11: Ball Screw 12: Nut 16: Gripping mechanism 14: Drive shaft holding tube 2o: Hanging fitting 60: Workbench sub-agent Patent attorney Shige Okamoto 2 other people

Claims (1)

【特許請求の範囲】[Claims] 上下方向に延びた複数本の案内棒な有し原子炉容器上に
載置される移動枠、前記案内棒に嵌合し支持されて昇降
する昇降台、前記移動枠上に装着された前記昇降台の昇
降駆動機構、および前記昇降台に所定間隔をおいて配設
された複数の原子炉制御棒駆動軸の掴持機構を具備した
ことに特徴を有する原子炉制御棒駆動軸の搬出入装置。
A moving frame that has a plurality of guide rods extending in the vertical direction and is placed on the reactor vessel, a lifting platform that is fitted and supported by the guide rods and moves up and down, and the lifting platform that is mounted on the moving frame. A reactor control rod drive shaft loading/unloading device characterized in that it is equipped with a platform elevating and lowering drive mechanism, and a plurality of reactor control rod drive shaft gripping mechanisms arranged at predetermined intervals on the elevating platform. .
JP58039168A 1983-03-11 1983-03-11 Device of charging and discharging reactor control rod driveaxis Granted JPS59164993A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58039168A JPS59164993A (en) 1983-03-11 1983-03-11 Device of charging and discharging reactor control rod driveaxis

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58039168A JPS59164993A (en) 1983-03-11 1983-03-11 Device of charging and discharging reactor control rod driveaxis

Publications (2)

Publication Number Publication Date
JPS59164993A true JPS59164993A (en) 1984-09-18
JPH0423236B2 JPH0423236B2 (en) 1992-04-21

Family

ID=12545583

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58039168A Granted JPS59164993A (en) 1983-03-11 1983-03-11 Device of charging and discharging reactor control rod driveaxis

Country Status (1)

Country Link
JP (1) JPS59164993A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4973443A (en) * 1988-10-26 1990-11-27 Westinghouse Electric Corp. System for removing and installing a control rod drive
US5019325A (en) * 1988-10-26 1991-05-28 Westinghouse Electric Corp. Method for removing and installing a control rod drive

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4973443A (en) * 1988-10-26 1990-11-27 Westinghouse Electric Corp. System for removing and installing a control rod drive
US5019325A (en) * 1988-10-26 1991-05-28 Westinghouse Electric Corp. Method for removing and installing a control rod drive

Also Published As

Publication number Publication date
JPH0423236B2 (en) 1992-04-21

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