JPH022987A - Reactor shutdown device - Google Patents

Reactor shutdown device

Info

Publication number
JPH022987A
JPH022987A JP63143742A JP14374288A JPH022987A JP H022987 A JPH022987 A JP H022987A JP 63143742 A JP63143742 A JP 63143742A JP 14374288 A JP14374288 A JP 14374288A JP H022987 A JPH022987 A JP H022987A
Authority
JP
Japan
Prior art keywords
tube
control rod
extension tube
electromagnet
acceleration
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
JP63143742A
Other languages
Japanese (ja)
Inventor
Mineo Sekiguchi
関口 峰生
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP63143742A priority Critical patent/JPH022987A/en
Publication of JPH022987A publication Critical patent/JPH022987A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To contrive the improvement of reliability of a control rod reactor core inserting detector function at the time of scram by providing an acoustic sensor at the position out of a reactor shielding body of a guiding tube. CONSTITUTION:The energy of an electromagnet 6 is absorbed, an inside extension tube 12 drops and a finger rod 13 is pushed out downward of a latch fin 3 for the position detection by an acoustic sensor 26. At this time, a stopper 22 provided on an outside extension tube 4 collides with the partition provided on a guide tube 1 to generate a first sound. Next an acceleration tube 18 abuts to a dash pot 21 to stop under decelerating by the dash pot 21 to generate a second sound. An control rod 14 continues to drop further and its lower end reaches and touches the bottom part of a reactor core to generate a third sound. A sensor 26 detects these first - third sounds to convert into electrical signals. The signals and the like corresponding to a scram signal and each acoustic signal are recorded in a recorder in a time history and a control inserting condition can precisely by known at and after scram signal generation.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は制御棒をその駆動機構から切り離して炉心に落
下させ、これにより核反応を停止させる方式の原子炉停
止装置に係る。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention is directed to a nuclear reactor shutdown device in which a control rod is separated from its drive mechanism and dropped into a reactor core, thereby stopping a nuclear reaction. It depends.

(従来の技術) 高速増殖炉に使用される制御棒駆動機構の原子炉緊急停
止(以下スクラムと呼ぶ)方式には、ガス加圧方式とス
プリング加速方式とがある。ガス加圧方式においては、
制御棒に駆動源から加速力および上下動を伝達する延長
棒に常時ガス圧を作用させておき、スクラム時にこのガ
ス圧により制御棒を炉心内に緊急挿入するようにしてい
る。また、スプリング加速方式においては、制御棒に加
速力を加える手段として圧縮したスプリングを使用し、
このスプリングのばね力を利用してスクラム時に緊急挿
入するようにしている。
(Prior Art) Nuclear reactor emergency shutdown (hereinafter referred to as scram) methods for control rod drive mechanisms used in fast breeder reactors include a gas pressurization method and a spring acceleration method. In the gas pressurization method,
Gas pressure is constantly applied to the extension rod that transmits acceleration force and vertical motion from the drive source to the control rod, and this gas pressure is used to emergencyly insert the control rod into the reactor core during scram. In addition, in the spring acceleration method, a compressed spring is used as a means to apply acceleration force to the control rod.
The spring force of this spring is used for emergency insertion during a scram.

第2図はスプリング加速方式を採用した制御棒駆動機構
の従来例を示す縦断面図である。この図において1図示
しない原子炉容器の上部開口を閉鎖する遮蔽体2を貫通
する案内管1内には、下端部に拡径自在のラッチフィン
ガ3を具えた外側延長管/lが上端部を延長管ラッチフ
ィンガ5に保持させて設置されている。
FIG. 2 is a longitudinal cross-sectional view showing a conventional example of a control rod drive mechanism employing a spring acceleration method. In this figure, inside a guide tube 1 that passes through a shield 2 that closes the upper opening of the reactor vessel (not shown), there is an outer extension tube /l whose upper end is provided with a latch finger 3 whose diameter can be freely expanded at its lower end. It is held and installed by the extension pipe latch finger 5.

延長管ラッチフィンガ5は、案内管1内に設けられ内部
に電磁石6を組み込まれたマグネットホルダ7下端に一
体化して設けられており、前記マグネットホルダ7とと
もに案内管1内を上下動可能とされている。また、案内
管1の上端近傍にはII駆動モータが設置され、この駆
動モータは前記電磁石ホルダ7に連結部材10を介して
取り付けたナラ1−11に螺合するボールねじ9を駆動
し、前記電磁石ホルダ7およびラッチフィンガ5を上下
動させるようにしである。
The extension tube latch finger 5 is provided integrally with the lower end of a magnet holder 7 which is provided inside the guide tube 1 and has an electromagnet 6 incorporated therein, and is movable up and down within the guide tube 1 together with the magnet holder 7. ing. Further, a II drive motor is installed near the upper end of the guide tube 1, and this drive motor drives a ball screw 9 that is screwed into a neck 1-11 attached to the electromagnet holder 7 via a connecting member 10. The electromagnet holder 7 and the latch finger 5 are moved up and down.

前記外側延長管4内には内側延長管12が同心的且つ可
摺動に配置され、この内側延長管12の下端には前記縮
径自在のラッチフィンガ3内に係合するフィンガロッド
13が設けられている。前記ラッチフィンガ3は、制御
棒14の上端部に設置したハンドリングヘッド15上端
の内フランジ付空洞15aに係合されている。
An inner extension tube 12 is disposed concentrically and slidably within the outer extension tube 4, and a finger rod 13 is provided at the lower end of the inner extension tube 12 to engage within the latch finger 3 whose diameter can be freely reduced. It is being The latch finger 3 is engaged with an inner flanged cavity 15a at the upper end of a handling head 15 installed at the upper end of the control rod 14.

また、前記内側延長管12の上端部は前記マグネットホ
ルダ7内に導入され、その上端をリンク機構16によっ
て支持されている。このリンク機構の端末は電磁石6に
吸着保持される吸着部材17と連結されており、電磁石
6の減勢時には吸着部材17の電磁石6からの離脱によ
り内側延長管12を開放するようにしである。
Further, the upper end of the inner extension tube 12 is introduced into the magnet holder 7, and its upper end is supported by a link mechanism 16. The end of this link mechanism is connected to an adsorption member 17 that is adsorbed and held by the electromagnet 6, and when the electromagnet 6 is deenergized, the adsorption member 17 is separated from the electromagnet 6 to open the inner extension tube 12.

さらに、前記外側延長管4の下部外周には加速管18が
係合されている。この加速管の下端は前記ハンドリング
ヘッド15の上端面に当接されている。案内管1内には
ばね受部19が設けられ、このばね受部と前記加速管1
8の上端面との間には、圧縮した状態の加速ばね20が
介在されてい。
Further, an acceleration tube 18 is engaged with the lower outer periphery of the outer extension tube 4. The lower end of this acceleration tube is in contact with the upper end surface of the handling head 15. A spring receiving part 19 is provided in the guide tube 1, and this spring receiving part and the acceleration pipe 1
An acceleration spring 20 in a compressed state is interposed between the spring 8 and the upper end surface of the spring 8 .

る。なお、加速ばね20の上端はばね受部19に固定さ
れ、下端は自由端とされている。このばね20は加速管
18を介して制御棒14に加速力を付与するものである
。また、前記加速管18の上端部は大径としてストッパ
18aを構成させてあり、このス1−ツバは前記案内管
1に設けた環状のダッシュボット21と協働して加速管
18の移動量を規制する。
Ru. Note that the upper end of the acceleration spring 20 is fixed to the spring receiving portion 19, and the lower end is a free end. This spring 20 applies acceleration force to the control rod 14 via the acceleration tube 18. Further, the upper end of the acceleration tube 18 has a large diameter and constitutes a stopper 18a, and this stopper cooperates with an annular dashbot 21 provided on the guide tube 1 to control the amount of movement of the acceleration tube 18. to regulate.

なお、図中22.23は外側延長管4、内側延長管12
の移動量を規制するストッパ、24は加速管18内に組
み込まれた永久磁石、25は案内管1外周に設けられ前
記永久磁石24と協働して前記加速管18の位置検出を
行うコイルをそれぞれ示している。
In addition, 22 and 23 in the figure are the outer extension pipe 4 and the inner extension pipe 12.
24 is a permanent magnet incorporated in the acceleration tube 18; 25 is a coil provided on the outer periphery of the guide tube 1 that cooperates with the permanent magnet 24 to detect the position of the acceleration tube 18; are shown respectively.

上′記構成の従来の制御棒駆動機構の作動を以下に説明
する。先ず、原子炉運転中の制御棒駆動は駆動モータ8
によって行われる。すなわち、駆動モータ8の回転によ
りボールねじ9が回転される。
The operation of the conventional control rod drive mechanism configured as described above will be explained below. First, the control rods are driven by the drive motor 8 during reactor operation.
carried out by. That is, the ball screw 9 is rotated by the rotation of the drive motor 8.

このボールねじの回転方向により、ナツト11、マグネ
ットホルダ7、延長管ラッチフィンガ5が案内管1内を
上昇または下降し、制御棒14を保持する外側延長管4
 内側延長管11が昇降され、制御棒14が昇降される
。このようにして制御棒14の図示しない炉心に対する
挿入、抜去が行われ、原子炉出力制御がなされる。
Depending on the direction of rotation of this ball screw, the nut 11, magnet holder 7, and extension tube latch finger 5 move up or down in the guide tube 1, and the outer extension tube 4 holding the control rod 14 moves up or down inside the guide tube 1.
The inner extension tube 11 is raised and lowered, and the control rod 14 is raised and lowered. In this way, the control rods 14 are inserted into and removed from the reactor core (not shown), and the reactor output is controlled.

次に、地震発生等の非常事態に際して原子炉をスクラム
させる場合の作動を説明する。先ず、上記のような場合
には図示しない手段によりスクラム信号が発生される。
Next, we will explain the operation when scramming a nuclear reactor in an emergency situation such as an earthquake. First, in the above case, a scram signal is generated by means not shown.

このスクラム信号により電磁石6が減勢され吸着部材1
7が電磁石6から離脱し、内側延長管12の上端を保持
していたリンク16が開放される。これにより内側延長
管12は落下し、その下端のフィンガロッド13をラッ
チフィンガ3下端より下方に突出させる。ラッチフィン
ガ3はフィンガロッド13の拘束がなくなるので、縮径
してハンドリングヘッド15との結合が解除され、制御
棒14は炉心内に落下しスクラムがなされる。なお、こ
の時加速ばね20により加速力を付与されていた加速管
18は、前記制御棒14の落下を加速し炉心内への急速
挿入を可能としている。
The electromagnet 6 is deenergized by this scram signal, and the adsorption member 1
7 is separated from the electromagnet 6, and the link 16 holding the upper end of the inner extension tube 12 is released. As a result, the inner extension tube 12 falls, causing the finger rod 13 at its lower end to protrude below the lower end of the latch finger 3. Since the latch finger 3 is no longer restrained by the finger rod 13, its diameter is reduced and the connection with the handling head 15 is released, and the control rod 14 falls into the reactor core and is scrammed. At this time, the acceleration tube 18 to which acceleration force is applied by the acceleration spring 20 accelerates the fall of the control rod 14 and enables rapid insertion into the reactor core.

なお、落下の初期は加速管18、制御棒14は一体とな
って落下するが、加速管18は間もなく環状ダッシュポ
ット21に減速されなから当接、停止する。その後、制
御棒14は前記の加速管18の減速、停止とは無関係に
急速落下を継続する。
Note that at the beginning of the fall, the accelerating tube 18 and the control rod 14 fall together, but the accelerating tube 18 soon comes into contact with the annular dashpot 21 and stops without being decelerated. Thereafter, the control rod 14 continues its rapid fall regardless of the deceleration or stoppage of the acceleration tube 18 described above.

上記のスクラム時の制御棒炉心内挿入の確認は次のよう
にして行われる。すなわち、加速管18に組み込まれた
永久磁石24がコイル25を通過する時に、コイル25
に発生する正弦波状の電磁誘導起電力を取り出し、ビジ
コーダ等で記録するようにしたもので、加速管18の位
置から制御棒14の位置を間接的に求めるようにしてい
る。コイル25を設置する位置によって、前記電磁誘導
起電力が制御棒14のどの挿入深さにおいて発生される
かが定められる。なお、前記ビジコーダの記録から、ス
クラム信号発生〜前記コイル設置位置により定まる制御
棒挿入深さまでの挿入に要した時間、制御棒落下速度等
を求めることができる。
Confirmation of control rod insertion into the core during the scram described above is performed as follows. That is, when the permanent magnet 24 incorporated in the acceleration tube 18 passes the coil 25, the coil 25
The sinusoidal electromagnetic induced electromotive force generated in the acceleration tube 18 is extracted and recorded with a visicorder, etc., and the position of the control rod 14 is indirectly determined from the position of the accelerator tube 18. Depending on the position where the coil 25 is installed, it is determined at which insertion depth of the control rod 14 the electromagnetic induced electromotive force is generated. From the record of the visicoder, it is possible to determine the time required for insertion from the scram signal generation to the control rod insertion depth determined by the coil installation position, control rod falling speed, etc.

(発明が解決しようとする課題) 前記説明した従来の制御棒駆動機構には次のような問題
がある。すなわち、できるだけ制御棒全挿入に近い位置
で位置検出を行うには、加速管18の停止位置に近い部
位にコイル25を設ける必要があるが、加速管18はダ
ッシュポット21により減速されながら停止するもので
あるから、前記のコイル設は位置は減速領域にあること
となり、大きな電磁誘導起電力を得ることはできない(
電磁誘導起電力の大きさは時速の変化の大きさに比例)
。この場合、制御棒落下速度は小さく検出されるだけで
なく、記録された電磁誘導起電力の判読精度は低下する
。また、永久磁石24.コイル25の機能が喪失された
場合には、原子炉を停止させて原子炉停止装置の交換を
行う必要がある。
(Problems to be Solved by the Invention) The conventional control rod drive mechanism described above has the following problems. That is, in order to detect the position as close as possible to the fully inserted control rod, it is necessary to provide the coil 25 at a location close to the stop position of the accelerator tube 18, but the accelerator tube 18 is decelerated by the dashpot 21 and stopped. Therefore, the position of the above-mentioned coil arrangement is in the deceleration region, and it is not possible to obtain a large electromagnetic induced electromotive force (
The magnitude of the electromagnetic induced electromotive force is proportional to the magnitude of the change in speed)
. In this case, not only the control rod falling speed is detected to be small, but also the accuracy of reading the recorded electromagnetic induced electromotive force is reduced. Moreover, the permanent magnet 24. If the function of the coil 25 is lost, it is necessary to shut down the reactor and replace the reactor shutdown device.

本発明は上記の事情に基づきなされたもので、スクラム
時の制御棒炉心内挿入検知機能の信頼性を向」ニさせた
原子炉停止装置を得ることを目的としている。
The present invention has been made based on the above-mentioned circumstances, and an object of the present invention is to obtain a nuclear reactor shutdown device that improves the reliability of the control rod insertion detection function during scram.

[発明の構成] (課題を解決するための手段) 本発明の原子炉停止装置は、案内管と、この案内管内に
設けられたyJA!flJモータと、この駆動モータに
よって駆動され前記案内管内で昇降されるマグネットホ
ルダと、このマグネットホルダ内に保持されスクラム信
号によって威勢される電磁石と、この電磁石の付勢時に
はこれに上端を保持された内側延長管と、この内側延長
管を同心的に包囲し上端を延長管ラッチフィンガに支持
された外側延長管と、この外側延長管下端に設けられ縮
径自在で前記内側延長管下端のフィンガロンド係合時に
は拡開して制御棒上端のハンドリングヘッド上端空洞内
面に係合し前記制御棒を保持するラッチフィンガと、前
記外側延長管に係合して設けられ下端面を前記ハンドリ
ングヘッド上端面に当接され制御棒下降方向のばね圧を
印加された加速管と。
[Structure of the Invention] (Means for Solving the Problems) The nuclear reactor shutdown device of the present invention includes a guide tube and a yJA! an flJ motor, a magnet holder driven by the drive motor and raised and lowered within the guide tube, an electromagnet held within the magnet holder and energized by a scram signal, and an upper end held by this when the electromagnet is energized. an inner extension tube, an outer extension tube that concentrically surrounds the inner extension tube and whose upper end is supported by an extension tube latch finger, and an outer extension tube that is provided at the lower end of the outer extension tube and is capable of contracting in diameter; a latch finger that expands when engaged and engages with the inner surface of the upper end cavity of the handling head at the upper end of the control rod to hold the control rod; The accelerator tube is in contact with the control rod and spring pressure is applied in the downward direction of the control rod.

この加速管に設けた永久磁石と、前記案内管に設けられ
前記永久磁石と協働するコイルを有するものにおいて、
前記案内管の原子炉遮蔽体外の部位に音響センサを設け
たことを特徴とする。
A permanent magnet provided in the accelerator tube and a coil provided in the guide tube that cooperates with the permanent magnet,
The present invention is characterized in that an acoustic sensor is provided at a portion of the guide tube outside the reactor shield.

(作用) 上記構成の本発明原子炉停止装置においては、従来の原
子炉停止装置におけるのと同様に加速管上の永久磁石お
よび案内管に設けたコイルの協働による制御棒の位置検
出もなされるが、それに加え音響センサが外側延長管の
ストッパが案内管隔壁と衝突して発する第1の音響、加
速管がダッシュポットにより減速されながらそれに衝突
する第2の音響、制御棒下端が炉心底面に到達接触する
第3の音響をそれぞれ検出するので、従来の永久磁石お
よびコイルによる電磁誘導起電力のみによった位置検出
よりも高精度で制御棒の位1面検出を行うことができる
(Function) In the nuclear reactor shutdown system of the present invention having the above configuration, the position of the control rod is also detected by the cooperation of the permanent magnet on the accelerator tube and the coil provided in the guide tube, as in the conventional nuclear shutdown system. In addition, acoustic sensors detect the first sound emitted when the stopper of the outer extension tube collides with the guide pipe bulkhead, the second sound emitted when the accelerator tube collides with it while being decelerated by the dashpot, and the lower end of the control rod is emitted from the bottom of the core. Since the third sound that reaches and comes into contact with the control rod is detected, it is possible to detect the position of the control rod with higher precision than conventional position detection using only electromagnetic induced electromotive force caused by permanent magnets and coils.

(実施例) 第2図と同一部分には同一符号を付した第1図は本発明
一実施例の縦断面図である。なお、この図中第2図と同
一の部分については説明を省略する。この実施例におい
ては、永久磁石24およびこれと協働するコイル25に
よる位置検出手段に加えて、案内管1内の適所で高温液
体ナトリウムに接触しない部位に音振動を電気信号に変
換する音響センサ26を設置する。第1図においては、
駆動モータ8の設置された案内管1横断方向の隔壁土に
設置されている。
(Embodiment) FIG. 1, in which the same parts as in FIG. 2 are given the same reference numerals, is a longitudinal cross-sectional view of one embodiment of the present invention. Note that the description of the same parts in this figure as in FIG. 2 will be omitted. In this embodiment, in addition to a position detection means consisting of a permanent magnet 24 and a coil 25 cooperating with the permanent magnet 24, an acoustic sensor for converting sound vibration into an electrical signal is installed at a suitable location within the guide tube 1 and not in contact with the high temperature liquid sodium. 26 will be installed. In Figure 1,
It is installed on the bulkhead soil in the transverse direction of the guide pipe 1 where the drive motor 8 is installed.

上記の本願制御棒駆動機構の構成は、第2図に示した従
来の制御棒駆動機構の構成に前記音響センサ26を付加
したのみであるから、原子炉の通常運転時には従来のも
のと同様にして原子炉出力の制御を行うことができ、非
常事態発生時にも従来のものと同様にして制御棒14の
急速挿入をなし得ることは勿論である。
The configuration of the control rod drive mechanism of the present invention described above is simply the addition of the acoustic sensor 26 to the configuration of the conventional control rod drive mechanism shown in FIG. It goes without saying that the reactor output can be controlled by using the control rod 14, and even in the event of an emergency, the control rods 14 can be rapidly inserted in the same manner as in the conventional system.

而して、原子炉スクラム時にあっては、非常事態の発生
によって発せられるアラーム信号により。
During a reactor scram, an alarm signal is issued in response to an emergency situation.

電磁石6の威勢、吸着部材17の電磁石6から離脱、内
側延長管12の上端を保持していたリンク16の開放、
内側延長管12の落下、その下端のフィンガロットL:
3のラッチフィンガ3下端下方への突出、ラッチフィン
ガ3のフィンガロッド13離脱による縮径、ハンドリン
グヘッド15のランチフィンガからの離脱等の一連の動
きがあり、制御棒14が炉心内に落下しスクラムがなさ
れることは第2図に示した従来の制御棒駆動機構と全く
同様である。また、加速管18、環状ダッシュボット2
1の作動も前記説明した従来の制御棒駆動機構における
のと同様である。また、加速管18に設置した永久磁石
24、案内管1に設置したコイル25による位置検出も
従来の制御棒駆動機構におけるのと同様に行われている
The force of the electromagnet 6, the detachment of the adsorption member 17 from the electromagnet 6, the release of the link 16 holding the upper end of the inner extension tube 12,
Falling of the inner extension tube 12, its lower end fingerlot L:
There is a series of movements such as the lower end of the latch finger 3 protruding downward, the diameter of the latch finger 3 decreasing as the finger rod 13 detaches, and the handling head 15 detaching from the launch finger, causing the control rod 14 to fall into the reactor core and cause a scram. What is done is exactly the same as the conventional control rod drive mechanism shown in FIG. In addition, an acceleration tube 18, an annular dashbot 2
1 is also similar to that in the conventional control rod drive mechanism described above. Further, position detection by the permanent magnet 24 installed in the accelerator tube 18 and the coil 25 installed in the guide tube 1 is performed in the same manner as in the conventional control rod drive mechanism.

而して、本発明においては前記従来例における位置検出
と音響センサ26による位置検出とを並用する。
Thus, in the present invention, the position detection in the conventional example and the position detection by the acoustic sensor 26 are used simultaneously.

すなわち、音響センサ26による位置検出は次のように
してなされる。先ず、スクラム信号によって電磁石6が
威勢され、内側延長管12が落下をしフィンガロッド1
3がラッチフィンガ3下方に押し出される。この時、外
側延長管4に設けたストッパ22が案内管1に設けた隔
壁と衝突して第1の音響を発生する。次に、加速管18
がダッシュポット21による減速下にダッシュボット2
1に当接、停止し第2の音響を発生する。制御棒14は
さらに落下を継続し、その下端が炉心底部に到達接触し
て第3の音響を発生する。音響センサ26は前記第1〜
第3の音響を検出し、電気信号に変換する。
That is, position detection by the acoustic sensor 26 is performed as follows. First, the electromagnet 6 is activated by a scram signal, and the inner extension tube 12 falls, causing the finger rod 1 to fall.
3 is pushed out below the latch finger 3. At this time, the stopper 22 provided on the outer extension tube 4 collides with the partition wall provided on the guide tube 1 to generate the first sound. Next, the acceleration tube 18
Dashbot 2 is decelerated by Dashpot 21.
1, stops, and generates a second sound. The control rod 14 continues to fall, and its lower end reaches and contacts the bottom of the reactor core, generating a third sound. The acoustic sensor 26 is connected to the first to
Detecting the third sound and converting it into an electrical signal.

ビジコーダ等の記録計には、スクラム信号、前記各音響
に対応する信号、前記永久磁石24およびコイル25に
よる検出信号が共に時刻歴で記録される。これ等の記録
から、スクラム信号発生以降の制御棒挿入状態を正確に
知ることができる。
A recorder such as a visicorder records the scram signal, the signals corresponding to each of the sounds, and the detection signals from the permanent magnet 24 and the coil 25 as a time history. From these records, it is possible to accurately know the control rod insertion status after the scram signal was generated.

[発明の効果] 上記のように本発明の制御棒駆動機構においては、加速
管18に設置した永久磁石24およびこれと協働するコ
イル25からなる電磁誘導起電力による制御棒位置検出
手段に加え、音響センサを設置している。この音響検出
センサ26は、制御棒14の実際の状態に1:1で対応
する出力を発生するものであるから、前記加速管18の
減速領域での位置検出の精度が低下する電磁誘導起電力
による位置検出手段のバックアップとして作用し、制御
棒炉心内挿入検知機能の精度の向上を図ることができる
[Effects of the Invention] As described above, in the control rod drive mechanism of the present invention, in addition to the control rod position detection means using electromagnetic induced electromotive force, which is composed of the permanent magnet 24 installed in the acceleration tube 18 and the coil 25 cooperating with the permanent magnet 24, , acoustic sensors are installed. Since this acoustic detection sensor 26 generates an output that corresponds 1:1 to the actual state of the control rod 14, electromagnetic induced electromotive force that reduces the accuracy of position detection in the deceleration region of the acceleration tube 18 is generated. The control rod functions as a backup for the position detection means, and can improve the accuracy of the control rod insertion detection function.

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

第1図は本発明一実施例の縦断面図、第2図は従来の制
御棒駆動機構の縦断面図である。
FIG. 1 is a longitudinal sectional view of an embodiment of the present invention, and FIG. 2 is a longitudinal sectional view of a conventional control rod drive mechanism.

Claims (1)

【特許請求の範囲】[Claims] 案内管と、この案内管内に設けられた駆動モータと、こ
の駆動モータによって駆動され前記案内管内で昇降され
るマグネットホルダと、このマグネットホルダ内に保持
されスクラム信号によって減勢される電磁石と、この電
磁石の付勢時にはこれに上端を保持された内側延長管と
、この内側延長管を同心的に包囲し上端を延長管ラッチ
フィンガに支持された外側延長管と、この外側延長管下
端に設けられ縮径自在で前記内側延長管下端のフィンガ
ロッド係合時には拡開して制御棒上端のハンドリングヘ
ッド上端空洞内面に係合し前記制御棒を保持するラッチ
フィンガと、前記外側延長管に係合して設けられ下端面
を前記ハンドリングヘッド上端面に当接され制御棒下降
方向のばね圧を印加された加速管と、この加速管に設け
た永久磁石と、前記案内管に設けられ前記永久磁石と協
働するコイルを有するものにおいて、前記案内管の原子
炉遮蔽体外の部位に音響センサを設けたことを特徴とす
る原子炉停止装置。
A guide tube, a drive motor provided in the guide tube, a magnet holder driven by the drive motor and moved up and down in the guide tube, an electromagnet held in the magnet holder and deenergized by a scram signal, and An inner extension tube whose upper end is held by the electromagnet when the electromagnet is energized, an outer extension tube which concentrically surrounds the inner extension tube and whose upper end is supported by an extension tube latch finger, and an outer extension tube provided at the lower end of the outer extension tube. A latch finger that can freely contract in diameter and expands when the finger rod at the lower end of the inner extension tube is engaged and engages the inner surface of the upper end cavity of the handling head at the upper end of the control rod and holds the control rod, and the latch finger engages with the outer extension tube. an acceleration tube whose lower end surface is in contact with the upper end surface of the handling head and to which a spring pressure in the downward direction of the control rod is applied; a permanent magnet provided in the acceleration tube; and a permanent magnet provided in the guide tube. A nuclear reactor shutdown device having cooperating coils, characterized in that an acoustic sensor is provided at a portion of the guide tube outside the reactor shield.
JP63143742A 1988-06-13 1988-06-13 Reactor shutdown device Pending JPH022987A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63143742A JPH022987A (en) 1988-06-13 1988-06-13 Reactor shutdown device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63143742A JPH022987A (en) 1988-06-13 1988-06-13 Reactor shutdown device

Publications (1)

Publication Number Publication Date
JPH022987A true JPH022987A (en) 1990-01-08

Family

ID=15345961

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63143742A Pending JPH022987A (en) 1988-06-13 1988-06-13 Reactor shutdown device

Country Status (1)

Country Link
JP (1) JPH022987A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7873137B2 (en) * 2006-02-09 2011-01-18 Kabushiki Kaisha Toshiba Reactivity control arrangement and fast reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7873137B2 (en) * 2006-02-09 2011-01-18 Kabushiki Kaisha Toshiba Reactivity control arrangement and fast reactor

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