JPS58150891A - Control rod drive mechanism - Google Patents

Control rod drive mechanism

Info

Publication number
JPS58150891A
JPS58150891A JP57032369A JP3236982A JPS58150891A JP S58150891 A JPS58150891 A JP S58150891A JP 57032369 A JP57032369 A JP 57032369A JP 3236982 A JP3236982 A JP 3236982A JP S58150891 A JPS58150891 A JP S58150891A
Authority
JP
Japan
Prior art keywords
control rod
drive mechanism
gripper
finger
rod drive
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
Application number
JP57032369A
Other languages
Japanese (ja)
Inventor
城土井 崇
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57032369A priority Critical patent/JPS58150891A/en
Publication of JPS58150891A publication Critical patent/JPS58150891A/en
Pending 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

  • Vehicle Body Suspensions (AREA)
  • Control Of Throttle Valves Provided In The Intake System Or In The Exhaust System (AREA)
  • Fluid-Damping Devices (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、原子炉の制御棒駆動機構に係り、特に制御棒
の結合、切離、保持用のグリッパに形状記憶合金製のフ
ィンガ爪を有して、原子炉の事故時過熱状態に対して外
部からの指令なしでも自発スクラム可能な制御棒駆動機
構に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a control rod drive mechanism for a nuclear reactor, and in particular, a gripper for connecting, separating, and holding control rods has finger claws made of a shape memory alloy. This invention relates to a control rod drive mechanism that can spontaneously scram even without external commands in response to overheating during an accident.

本発明の従来例(FBRの場合)の制御棒駆動機構を第
1図、82図、および第3図に示す、第1図は制御棒駆
動機構の全体骨組であり、第2図はグリッパ部の詳細図
、そして第3図は第2図のA−A視図である。
The control rod drive mechanism of the conventional example (in the case of FBR) of the present invention is shown in FIGS. 1, 82, and 3. FIG. 1 shows the overall framework of the control rod drive mechanism, and FIG. 2 shows the gripper section 3 is a detailed view of FIG. 2, and FIG. 3 is an AA view of FIG.

制御棒駆動機構lは原子炉の遮蔽プラグ2の上面に設置
され、その内部には駆動軸3の駆動機構(後述)および
カム軸着の駆動機構(後述)を具えている。制御棒5に
連結し得る駆動軸3は、上下動可能に設けられると共に
、その下端にグリッパフィンガ爪6を具えて、遮蔽プラ
ダ2の開口に固設した駆動軸案内管7を挿通している。
The control rod drive mechanism 1 is installed on the upper surface of the shielding plug 2 of the nuclear reactor, and includes therein a drive mechanism for a drive shaft 3 (described later) and a camshaft-mounted drive mechanism (described later). A drive shaft 3 connectable to a control rod 5 is provided to be movable up and down, has a gripper finger claw 6 at its lower end, and is inserted through a drive shaft guide tube 7 fixedly installed in an opening of the shielding prada 2. .

駆動軸3を挿通して、上下動可能に設けられ九カム軸4
は、その下端に前記グリッパフィンガ爪6を開閉させる
カム部8tAえている。紡記グリッパフィンガへ6は、
311(場合により2.4.6個等も。
A nine cam shaft 4 is inserted through the drive shaft 3 and is provided so as to be movable up and down.
has a cam portion 8tA at its lower end that opens and closes the gripper finger claw 6. 6 to spinning gripper fingers,
311 (2, 4, 6, etc. depending on the case).

あり)のスプーン形のフィンガ爪6aをチューリップの
つぼみ状に配列し九構造となっている。そして、そのフ
ィンガ61内にカム軸4のカム部8が押し込められた時
に、各フィンガ6暑は外側に押し開かれ、かつカム部8
が各ライ/ガロ1から突出した時に、各ライ/ガロaは
閉じるようになっている。前記駆動軸3の駆動機構は、
駆動モータ9と、そのモータ9にギヤトレン1oを介し
て連結するボールスクリュー軸11と、そのスクリュー
軸11に螺合して上下動し得るボールスクリューナツト
12と、そのボールスクリューナツト12に連結し、か
つ駆動軸3と一体のアーマチュア14′を吸着し得る電
磁石13とから成っている。
The spoon-shaped finger claws 6a (with 1) are arranged in the shape of a tulip bud, resulting in a nine structure. When the cam portion 8 of the camshaft 4 is pushed into the finger 61, each finger 6 is pushed outward and the cam portion 8 is pushed open.
When protrudes from each lie/galo 1, each lie/galo a closes. The drive mechanism of the drive shaft 3 is as follows:
A drive motor 9, a ball screw shaft 11 connected to the motor 9 via a gear train 1o, a ball screw nut 12 screwed onto the screw shaft 11 and capable of moving up and down, and connected to the ball screw nut 12, It also comprises an electromagnet 13 capable of attracting an armature 14' integrated with the drive shaft 3.

従って、駆動モータ9の回転によってボールスクリュナ
ツト12を上下動させれば、電磁石13に吸着される駆
動軸3を駆動軸案内管7に沿って上下動させることがで
きる。前記カム軸4の駆動機構は、カム軸駆動モータ1
5、そのモータ15にギヤトレン16を介して連結する
ボールスクリュー軸17と、そのスクリュー軸17に螺
合して上下動し得るボールスクリュナツト18と、その
ボールスクリュ−ナツト18と連結するカム軸作動りツ
ド19と連結するカム軸作動用フランジ2゜とから成っ
ている。原子炉の炉心21に設置された制御棒案内管2
2内には、制御棒受金23が収納されている。この制御
棒受金23は、その下部に制御棒本体(図示せず)tF
!il!吊している。また制御棒受金23の上部には、
グリッパフィンガ6を挿入し得る開口部が設けられ、そ
の開口部内壁には、グリッパアイ/ガロの各フィンガ爪
61を接触させる自画が形成されている。
Therefore, if the ball screw nut 12 is moved up and down by the rotation of the drive motor 9, the drive shaft 3, which is attracted to the electromagnet 13, can be moved up and down along the drive shaft guide tube 7. The drive mechanism for the camshaft 4 includes a camshaft drive motor 1.
5. A ball screw shaft 17 that is connected to the motor 15 via a gear train 16, a ball screw nut 18 that is screwed onto the screw shaft 17 and can move up and down, and a camshaft that is connected to the ball screw nut 18. It consists of a camshaft operating flange 2° connected to a rod 19. Control rod guide tube 2 installed in the reactor core 21
A control rod receiver 23 is housed inside the control rod receiver 2 . This control rod receiver 23 has a control rod main body (not shown) tF at the bottom thereof.
! Il! It's hanging. Also, on the top of the control rod receiver 23,
An opening into which the gripper fingers 6 can be inserted is provided, and a self-portion with which each finger claw 61 of the gripper eye/gallo comes into contact is formed on the inner wall of the opening.

次に制御棒5の結合および保持の動作について説明する
。カム軸4のカム部8をグリッパフィンガ6から突出さ
せ丸状1、即ちグリッパフィンガ6を閉じ元状態で、駆
動軸3およびカム軸4を下降させ、駆動軸3の下端を制
御棒受金23の上端に当接させる。この時、グリッパフ
ィンガ6は制御棒受金23の開口部に位置する。その後
、カム軸4を上部内周面に設けたバネ240弾性力によ
抄僅かに上昇させて、そのカム部8t−グリッパフィン
ガ6内に押し込んで、そのグリッパフィンガ6の各フィ
ンガ爪6at押広げる。これによって各フィンガ6麿は
、制御棒受金23の内壁の自画に圧着される。即ち、制
御棒5は制御棒受金23を介して駆動軸3に結合され、
炉心21内に保持される。
Next, the operation of connecting and holding the control rod 5 will be explained. The cam part 8 of the camshaft 4 is made to protrude from the gripper finger 6, and the drive shaft 3 and the camshaft 4 are lowered with the round shape 1, that is, the gripper finger 6 in the closed original state, and the lower end of the drive shaft 3 is attached to the control rod holder 23. touch the top edge of the At this time, the gripper fingers 6 are located at the opening of the control rod receiver 23. Thereafter, the cam shaft 4 is slightly raised by the elastic force of a spring 240 provided on the upper inner circumferential surface, and the cam portion 8t is pushed into the gripper finger 6, and each finger claw 6at of the gripper finger 6 is expanded. . As a result, each finger 6 is pressed against the inner wall of the control rod holder 23. That is, the control rod 5 is coupled to the drive shaft 3 via the control rod holder 23,
It is held within the reactor core 21.

燃料交換作業の準備段階等において、制御棒5を切離す
必要のある時は、まず駆動軸3およびカム軸着をストロ
ーク下限付近まで、モータ9により下降させて、制御棒
5を炉心燃料集合体部21に収納する。その後、カム軸
4を僅かに下降させてそのカム部8tグリッパフィンガ
6から突出させる。これによって各フィンガ爪6aが閉
じて、グリッパフィンガ6と制御棒受金23との結合が
解かれる。即ち、駆動軸3と+ttt制御俸制御の結合
が解かれる。前述し友制御俸5と駆動−3の結合、およ
び切離動作の確認は、駆動軸3とカム軸4との相対的変
位を検出するリミットスイッチ(図示せず)およびロー
ドセル25の荷重信号によって行なってい友。
When it is necessary to disconnect the control rods 5 during the preparatory stage of refueling work, first lower the drive shaft 3 and the cam shaft attachment to near the lower stroke limit using the motor 9, and then remove the control rods 5 from the core fuel assembly. It is stored in the section 21. Thereafter, the camshaft 4 is lowered slightly to cause the cam portion 8t to protrude from the gripper fingers 6. As a result, each finger pawl 6a closes and the gripper fingers 6 and the control rod holder 23 are disconnected from each other. That is, the connection between the drive shaft 3 and the +ttt control salary control is released. The above-mentioned connection and disconnection between the control shaft 5 and the drive 3 are confirmed by a limit switch (not shown) that detects the relative displacement between the drive shaft 3 and the camshaft 4 and a load signal from the load cell 25. Good job, friend.

従来の制御棒駆動機構O場合スクラム始動は、大雑ばに
首えば電磁石13の消磁より、上記に示す例の如くアー
マチュア14以下の駆動軸3および制御棒5を一体とし
て切離し挿入させるかまたは、グリッパフィンガ6を開
放し、制御棒5を単体挿入する原理のものであった。従
がって原子炉の制傭俸駆動WA構には独立二系統の互い
に原理の異なり九構成が要請されているにもかかわらず
その原則スクラム始動という点からも厳密に準拠するこ
とは焦域であつ次、そのため従来タイプでは遮蔽プラグ
上部の駆動機構内又は駆動鵬楽内璽内で駆動軸又はカム
軸がスティックし九場合、たとえ制御棒駆動機構を二系
統設置されていても原理、構造が類似しているため、共
通モード故障により事故時に両系統ともスクラム挿入不
能という事態を招く可能性を有する欠点があった。
In the case of a conventional control rod drive mechanism O, scram starting is basically done by demagnetizing the electromagnet 13, or by separating and inserting the drive shaft 3 and control rod 5 below the armature 14 as one body, as in the example shown above. The principle was to open the gripper fingers 6 and insert the control rod 5 alone. Therefore, despite the requirement for nine configurations of two independent systems with different principles for the wage control WA structure of a nuclear reactor, strict compliance from the point of view of scram start-up is not a priority. Therefore, in the conventional type, if the drive shaft or camshaft sticks in the drive mechanism at the top of the shielding plug or in the drive mechanism, the principle and structure may be affected even if two control rod drive mechanisms are installed. Since these systems are similar, there is a drawback that there is a possibility that scram insertion will not be possible in both systems in the event of an accident due to a common mode failure.

本発明の目的は、従来技術における上述の問題点を解決
する方法として、原子炉事故時過熱状態に至るとグリッ
パが上部駆動機構の動作を受けることもなく、自発的に
制御棒を切離し、制御棒挿入によるスクラム動作が可能
なように、グリッパフィンガ爪を形状記憶合金製とし次
原子炉の制御棒駆動機構を提供することにある。
An object of the present invention is to provide a method for solving the above-mentioned problems in the prior art, in which the gripper automatically disconnects the control rods without being operated by the upper drive mechanism when an overheating state occurs during a nuclear reactor accident, and controls the control rods. An object of the present invention is to provide a control rod drive mechanism for a nuclear reactor in which gripper finger claws are made of a shape memory alloy so as to enable scram operation by rod insertion.

形状記憶合金が、外力を加えて塑性変形させても、ある
温度以上に加熱すると、マルテンサイト相が高温相に逆
変態して、変形的の形状を記憶しているかのように元の
形に戻る。この材料特性をグリッパフィンガの開閉動作
に応用することにより、通常時制御棒を保持し、事故時
の高温状態でフィンガを閉じ制御棒を自発時に切離せる
ようにした。tた燃料交換、メンテナンス時定期的炉停
止状態でのグリッパ開閉用にヒータをグリッパに内蔵さ
せ、局部加熱により雰囲気温度が冷い場合にも任意の時
グリッパ切離ができる構成としている。
Even if a shape memory alloy is plastically deformed by applying an external force, when heated above a certain temperature, the martensitic phase reversely transforms into a high temperature phase and returns to its original shape as if it had memorized the deformed shape. return. By applying this material property to the opening and closing operations of the gripper fingers, the control rods were held in place during normal conditions, and the fingers were closed in the high-temperature conditions of an accident, allowing the control rods to be detached spontaneously. A heater is built into the gripper for opening and closing the gripper when the furnace is periodically stopped during fuel exchange and maintenance, and the gripper can be disconnected at any time by local heating even when the ambient temperature is cold.

本発明の実施例を第1図、第4図、および第5図に基づ
いて説明する。第1図は制御棒駆動機構の全体骨組図で
グリッパWを除き本発明の実施例の構成を示す、第4図
は本発明のグリッパ部詳細図、纂5図は第4図0A−A
矢視図、第4図は高温相に逆変態する鵠で、グリッパフ
ィンガ爪26aが制御棒受金23の上部開口部内壁の掻
回に接触して、駆動軸3によって制御棒5が結合保持さ
れている状at示す、高温下で逆変態すると、グリッパ
フィンガ爪26aはつぼみ、同型26Mが制御棒受金t
a崩し、制@棒単独のスクラム挿入動作t−開始させる
。爪261がつぼむと先端部31aにセンタ本体を有す
るシース形感圧素子の先端31aに爪の内面が押圧し、
グリッパが切離され次ことを検出し、スクラム始動を検
出できる。
Embodiments of the present invention will be described based on FIGS. 1, 4, and 5. Fig. 1 is an overall framework diagram of the control rod drive mechanism, showing the configuration of an embodiment of the present invention excluding the gripper W; Fig. 4 is a detailed view of the gripper portion of the present invention;
The arrow view and FIG. 4 show the mouse undergoing reverse transformation to the high-temperature phase, and the gripper finger claw 26a comes into contact with the stirring of the inner wall of the upper opening of the control rod holder 23, and the control rod 5 is connected and held by the drive shaft 3. When reverse transformation occurs under high temperature, the gripper finger claw 26a becomes a bud, and the same type 26M becomes a control rod receiver t.
Break down a and start the scrum insertion movement of the control @ stick alone. When the claw 261 is retracted, the inner surface of the claw presses against the tip 31a of the sheath-type pressure sensitive element having the center body at the tip 31a.
It is possible to detect when the gripper is disconnected and to detect the start of a scram.

(バックアップとしてロードセルの荷重備考の変化でも
可能としている)燃料交換時、メンテナンス特等周囲温
度が材料の逆変態点よりかなり低い場合のグリッパ切離
し動作は、CRD駆動軸3に設けamt−とおして上方
より導びかれるステンレス鋼t#製シース管内蔵OMI
ケーブルを介して、駆動軸3先端のグリッパケースz7
の内装ヒータ(MIケーブル)K通電加熱し、形状記憶
合金のグリッパフィンガ爪261¥r局部加熱し、逆変
態させる0局部加熱を効皐嵐〈行なえるように、必4!
に応じてグリッパケース外形にセランツクコーティング
等による断熱層32を設ける。
(As a backup, it is also possible to change the load cell's load notes.) At the time of fuel exchange, when the maintenance special ambient temperature is considerably lower than the reverse transformation point of the material, the gripper disconnection operation is performed from above through the amt- installed on the CRD drive shaft 3. Built-in OMI guided stainless steel T# sheath tube
Gripper case z7 at the tip of drive shaft 3 via the cable
The internal heater (MI cable) K is electrically heated to locally heat the shape memory alloy gripper finger claws 261¥r, and to cause reverse transformation, the local heating is effective.
Depending on the requirements, a heat insulating layer 32 such as a selank coating is provided on the outer shape of the gripper case.

本発明に使用可能な形状記憶合金としては、例えば特開
昭46−1502(フィリップ社出願)のパラジウム5
0gm子−一チタン50g厘子チ(逆変態点400〜5
50t)、tた逆変態点はやや低くなるがVe−Mn合
金(逆変態点240〜340℃)などが考えられる。
Examples of shape memory alloys that can be used in the present invention include palladium 5
0gm-1 titanium 50g (reverse transformation point 400-5
50t), Ve-Mn alloy (reverse transformation point: 240 to 340°C), although the reverse transformation point is slightly lower.

向上部の駆動機構は第1図のとおりでその構成、機能は
従来例で述べ九とおりである。
The driving mechanism of the improving part is as shown in FIG. 1, and its structure and functions are as described in the conventional example.

本発明により制御棒駆動機構の上部機構による制御棒の
スクラム挿入が不能となった場合で4、原子炉がクリッ
パフィンガ爪31aの逆変態点まで加熱状態に至ると、
グリッパは自発的に制御棒を切離しスクラム挿入可能と
なり、独立二系統原理の異なる原子炉停止機能を確保で
きることから、原子炉自体の信頼性を大巾に改善できる
。また従来例においてグリッパ開閉動作させる必要とし
た遮蔽プラグ2上の駆動機構、駆動軸3t−挿通するカ
ム軸4等の構造がこの発明では不用となり、部品数を大
巾削減でき、この点からも制御棒駆動機構信頼性向上に
大きく貢献できるものである。
According to the present invention, when scram insertion of control rods by the upper mechanism of the control rod drive mechanism becomes impossible, 4, when the reactor reaches a heated state to the reverse transformation point of the clipper finger pawl 31a,
The gripper can spontaneously detach the control rods and insert them in a scram, ensuring reactor shutdown functions based on two independent system principles, greatly improving the reliability of the reactor itself. In addition, the structure of the drive mechanism on the shielding plug 2, the camshaft 4 that passes through the drive shaft 3t, etc., which were required to open and close the gripper in the conventional example, is not required in the present invention, and the number of parts can be greatly reduced. This can greatly contribute to improving the reliability of the control rod drive mechanism.

本発明によれば、従来実施例にて十分対応できなかった
原子炉の独立二系統、原理の異った原子炉停止系の組合
せの提供を可能とできる効果がある。
According to the present invention, it is possible to provide a combination of two independent nuclear reactor systems and reactor shutdown systems with different principles, which could not be adequately supported in the conventional embodiments.

を念制御棒グリッパ動作用駆動部としての可動構造をな
くし部品数の大巾削減を計れ、制御棒駆動機構の信頼性
が大巾に向上できる。
By eliminating the movable structure as the drive section for the control rod gripper operation, the number of parts can be greatly reduced, and the reliability of the control rod drive mechanism can be greatly improved.

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

第1図は制御棒駆動機構の構造を示す概略骨組図である
。第2図は従来例のグリッパ部詳細図であり、第3図は
第2図のA−A矢視図、第4図は本発明の実施例のグリ
ッパ部詳細図であり、第5図は第4図0A−A矢視図で
ある。 26.268・・・グリッパフィンガ爪(形状記憶合金
製)、28・・・グリッパケース内装MIケーブル、i
11図
FIG. 1 is a schematic diagram showing the structure of the control rod drive mechanism. FIG. 2 is a detailed view of the gripper portion of the conventional example, FIG. 3 is a view taken along the arrow A-A in FIG. 2, FIG. 4 is a detailed view of the gripper portion of the embodiment of the present invention, and FIG. FIG. 4 is a view taken along arrows 0A-A. 26.268...Gripper finger claw (made of shape memory alloy), 28...Gripper case interior MI cable, i
Figure 11

Claims (1)

【特許請求の範囲】 1、制御棒駆動機構において制御棒の結合、切離、結合
保持用のグリッパが、形状記憶合金から有るフィンガ爪
、同上爪局部過熱シースヒータから成ることを特徴とす
る原子炉の制御棒駆動機構。 2、特許請求の範囲第1項において、原子炉の出力運転
時、事故によ秒原子炉が異常な高温になった場合フィン
ガ爪が材料の・マルテンサイト変態により変形し、制御
棒が切離され、原子炉の緊免停止機能を発揮することを
特徴とする原子炉の制御棒駆動機構。 3.1!#杵請求の範囲第1項において、原子炉の燃料
交換準備、まえは燃料交換作業完了後の後始末等任意の
時点で制御棒の結合、切離動作が必要な際、上記ヒータ
に通電加熱で、フィンガ爪を逆変態させ、制御棒を切離
動作させtた電気を遮断することにより、自然冷却等に
より冷却させて、フィンガ爪を元の制御棒つかみ状態に
戻すようにしたことを特徴とする原子炉の制御棒駆動機
構。 4、#許請求の範囲第1項において、制御棒のスクラム
時の切離動作が、グリッパ爪の内@に内設し九感圧素子
等の検出器が逆変態して変形し喪グリッパフィンガ爪内
面に押圧されることによって、速やかに検出できること
を特徴とする原子炉の制御棒駆動機構。
[Claims] 1. A nuclear reactor characterized in that in a control rod drive mechanism, a gripper for connecting, separating, and holding the control rods together is composed of finger pawls made of a shape memory alloy and a locally overheating sheath heater for the same nails. control rod drive mechanism. 2. In claim 1, if the reactor becomes abnormally high temperature due to an accident during power operation of the reactor, the finger claws are deformed due to martensitic transformation of the material, and the control rods are separated. A control rod drive mechanism for a nuclear reactor, which is characterized by being able to perform an emergency shutdown function for a nuclear reactor. 3.1! #Pestrel In claim 1, when the control rods need to be connected or disconnected at any time, such as in preparation for a reactor fuel change or in cleaning up after the completion of a fuel change operation, the above-mentioned heater is energized and heated. The feature is that the finger claws are reversely transformed, the control rod is separated, the electricity is cut off, the finger claws are cooled by natural cooling, etc., and the finger claws return to their original state of gripping the control rod. A control rod drive mechanism for a nuclear reactor. 4. #Claim 1 In claim 1, when the control rod is scrammed, the separation operation causes a detector such as a pressure-sensitive element installed inside the gripper claw to undergo reverse transformation and deform, causing the gripper finger to deform. A control rod drive mechanism for a nuclear reactor, characterized in that it can be quickly detected by being pressed against the inner surface of a claw.
JP57032369A 1982-03-03 1982-03-03 Control rod drive mechanism Pending JPS58150891A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57032369A JPS58150891A (en) 1982-03-03 1982-03-03 Control rod drive mechanism

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57032369A JPS58150891A (en) 1982-03-03 1982-03-03 Control rod drive mechanism

Publications (1)

Publication Number Publication Date
JPS58150891A true JPS58150891A (en) 1983-09-07

Family

ID=12357024

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57032369A Pending JPS58150891A (en) 1982-03-03 1982-03-03 Control rod drive mechanism

Country Status (1)

Country Link
JP (1) JPS58150891A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60164294A (en) * 1984-02-07 1985-08-27 動力炉・核燃料開発事業団 Driving mechanism of control rod for reactor
JPS61111489A (en) * 1984-10-09 1986-05-29 動力炉・核燃料開発事業団 Driving mechanism of control rod for nuclear reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60164294A (en) * 1984-02-07 1985-08-27 動力炉・核燃料開発事業団 Driving mechanism of control rod for reactor
JPH0133800B2 (en) * 1984-02-07 1989-07-14 Doryokuro Kakunenryo Kaihatsu Jigyodan
JPS61111489A (en) * 1984-10-09 1986-05-29 動力炉・核燃料開発事業団 Driving mechanism of control rod for nuclear reactor
JPH0315158B2 (en) * 1984-10-09 1991-02-28 Doryokuro Kakunenryo Kaihatsu Jigyodan

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