JPS63289487A - Nuclear reactor stopping apparatus - Google Patents

Nuclear reactor stopping apparatus

Info

Publication number
JPS63289487A
JPS63289487A JP62123716A JP12371687A JPS63289487A JP S63289487 A JPS63289487 A JP S63289487A JP 62123716 A JP62123716 A JP 62123716A JP 12371687 A JP12371687 A JP 12371687A JP S63289487 A JPS63289487 A JP S63289487A
Authority
JP
Japan
Prior art keywords
electromagnet
control rod
magnetic body
extended tube
vibration
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
JP62123716A
Other languages
Japanese (ja)
Other versions
JP2509620B2 (en
Inventor
Sadao Sakamoto
貞男 坂本
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 JP62123716A priority Critical patent/JP2509620B2/en
Publication of JPS63289487A publication Critical patent/JPS63289487A/en
Application granted granted Critical
Publication of JP2509620B2 publication Critical patent/JP2509620B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To prevent malfunctioning of a scram function due to an external force working on a control rod, by providing a universal coupling with an electromagnet retained on an extended tube. CONSTITUTION:A cover 17a is given the outline of a bottle and am neck part 17b thereof is inserted into an opening 21 of an extended tube 7b maintaining a clearance 22. Moreover, a nut 19a is screwed from inside of the extended tube 7 to put together an electromagnet 17 and the extended tube 7 forming a universal coupling 19. On the other hand, vibration or the like of the control rod 14 is transmitted to the electromagnet 17, while the universal coupling 19 is interposed between the electromagnet 17 and the extended tube 7, which especially allows lateral vibration of the electromagnet 17 to be absorbed by the clearance 22, making the vibration free from constraint by the extended tube 7. Therefore, a bending stress or the like become hard to occur in an attraction surface between the electromagnet 17 and a magnetic body 16 of the control rod 14 so that magnetic body 16 would not separate from electromagnet 17 eventually letting the control rod 14 drop by its own weight. The bottom of the cover 17a of the electromagnet 17 forms a convex in a truncated cone and is attracted fit in a concave of the upper end of the magnetic body to prevent a slide deviation of the attraction surface otherwise caused by vibration of the control rod 14, namely, the magnetic body 16.

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、液体金属冷却型の高速増殖炉の原子炉停止装
置に係り、特に電磁力による制御棒保持機構を有する原
子炉停止装置に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor shutdown device for a liquid metal cooled fast breeder reactor, and particularly relates to a nuclear reactor shutdown device for a liquid metal cooled fast breeder reactor, and particularly for an atomic reactor having a control rod holding mechanism using electromagnetic force. Regarding reactor shutdown equipment.

(従来の技術) 一般に原子炉は、中性子吸収材を内蔵した制御棒を炉心
に挿脱して出力制御を行ない、事故時等の緊急時にはこ
の制御棒を炉心に全挿入して炉の出力を停止させるよう
になっている。しがしてこのような緊急時には炉の運転
を確実に停止させる必要があるため、たとえば高速増殖
炉においては構造が簡単で確実に作動し得る原子炉停止
装置が設けられている。すなわちこの種の炉においては
、原子炉異常時に出力されるスクラム信号にもとづき、
制御棒駆動機構等の外部機器を用いて作動する原子炉停
止系と、このような外部機器を用いることなく独立して
動作する単独落下式原子炉停止系とを並用して2重の安
全対策を講じている。
(Conventional technology) Generally, in a nuclear reactor, power is controlled by inserting and removing a control rod containing a neutron absorbing material into the reactor core, and in the event of an emergency such as an accident, the control rod is fully inserted into the reactor core to stop the reactor's output. It is designed to let you do so. However, in such an emergency, it is necessary to reliably stop the operation of the reactor, so for example, fast breeder reactors are provided with a reactor shutdown device that has a simple structure and can operate reliably. In other words, in this type of reactor, based on the scram signal output at the time of reactor abnormality,
A double safety measure is achieved by using both a reactor shutdown system that operates using external equipment such as a control rod drive mechanism, and an independent drop-type reactor shutdown system that operates independently without using such external equipment. is being taught.

このような装置はたとえば第3図に示すように、原子炉
容器1に炉心2を収容し遮蔽プラグ3によって蓋をして
いる。この遮蔽プラグ3を貫通する炉心上部機構4には
制御棒駆動機構5が設けられている。制御棒駆動機構5
は第4図に拡大してその詳細を示したように上部案内管
6に延長管7が昇降自在に挿通され、この延長管7は炉
外に設けられた駆動部8によって昇降駆動されるように
なっている。
In such a device, for example, as shown in FIG. 3, a reactor core 2 is housed in a reactor vessel 1 and covered with a shielding plug 3. A control rod drive mechanism 5 is provided in the core upper mechanism 4 that passes through the shielding plug 3. Control rod drive mechanism 5
As shown in detail in an enlarged view of FIG. 4, an extension tube 7 is inserted into the upper guide tube 6 so as to be able to rise and fall freely, and this extension tube 7 is driven up and down by a drive unit 8 provided outside the furnace. It has become.

一方、炉心2には多数のラッパ管9と案内管10とが所
定の配置で鉛直に装荷されている。これらラッパ管9と
案内管lOは、高圧プレナム11を構成する上下の炉心
支持板12.12によって支持されており、各ラッパ管
9および案内管lO内には、高圧プレナムll内を流れ
る冷却材たとえば液体ナトリウムが流入して、各管内を
下方から上方に向って流通するようになっている。ラッ
パ管9には炉心燃料13が内蔵され、また案内管10に
は制御棒14が昇降自在に挿入されている。この制御棒
14は中性子吸収材15を内蔵するとともに、その上端
部に磁性体16を有している。
On the other hand, a large number of trumpet tubes 9 and guide tubes 10 are vertically loaded in the core 2 in a predetermined arrangement. These trumpet tubes 9 and guide tubes 1O are supported by upper and lower core support plates 12.12 constituting the high-pressure plenum 11, and inside each trumpet tube 9 and guide tubes 10, there is a coolant flowing inside the high-pressure plenum 11. For example, liquid sodium flows in and flows through each tube from the bottom to the top. A core fuel 13 is contained in the trumpet tube 9, and a control rod 14 is inserted into the guide tube 10 so as to be movable up and down. The control rod 14 contains a neutron absorbing material 15 and has a magnetic material 16 at its upper end.

しかして延長管7の下端には磁性体16を吸着する電磁
石17が取着されている。符号18はこの電磁石に給電
するケーブルである。又、電磁石17は案内管10の上
部開口10a、すなわち冷却材の出口近傍に位置するよ
うに、延長管7の下部に取着されており、冷却材温度が
通常の原子炉出力運転時よりも高温となった異常温度上
昇時に、電磁石17の磁性材の温度がそのキュリ一点近
傍に達すれば著しい磁力の低下が生じ、制御棒14は電
磁石17より切離されて自動的なスクラムが達成される
。また、ポンプトリップ等に対しては、スクラム信号に
より給電を停止して電磁石17を解磁し、制御棒14を
切離してスクラムを達成する。
An electromagnet 17 that attracts the magnetic material 16 is attached to the lower end of the extension tube 7. Reference numeral 18 is a cable that supplies power to this electromagnet. Further, the electromagnet 17 is attached to the lower part of the extension tube 7 so as to be located near the upper opening 10a of the guide tube 10, that is, the outlet of the coolant, so that the coolant temperature is lower than that during normal reactor power operation. When the temperature rises abnormally and the temperature of the magnetic material of the electromagnet 17 reaches near its single point, a significant drop in magnetic force occurs, and the control rod 14 is separated from the electromagnet 17 to achieve an automatic scram. . In addition, in response to a pump trip, etc., power supply is stopped by a scram signal, the electromagnet 17 is demagnetized, and the control rod 14 is disconnected to achieve a scram.

(発明が解決しようとする問題点) 一般に磁石の吸着力は、吸着面に対して垂直に働く引張
り力荷重には抵抗力が大きい。しかし、曲げ・ねじり等
の荷重に対しては抵抗力が小さく、比較的小さい荷重で
吸着面を分離することが可能である。
(Problems to be Solved by the Invention) Generally, the attraction force of a magnet has a large resistance to a tensile force load acting perpendicularly to the attraction surface. However, the resistance force against loads such as bending and twisting is small, and it is possible to separate the suction surfaces with a relatively small load.

ところが上述した装置における電磁石17は冷却材の出
口近傍に位置しており冷却材は高圧プレナム11より流
入させているためかなりの流速がある。
However, since the electromagnet 17 in the above-mentioned device is located near the coolant outlet and the coolant is introduced from the high-pressure plenum 11, there is a considerable flow velocity.

したがって、電磁石17と制御棒14の吸着面は、流力
振動等の流体力による曲げやねじり等の荷重及び振動そ
のものを受けることになり、電磁石17と制御棒14が
切離されるおそれがある。
Therefore, the adhesion surfaces of the electromagnet 17 and the control rod 14 are subjected to loads such as bending and twisting due to fluid forces such as hydrodynamic vibrations, as well as vibrations themselves, and there is a risk that the electromagnet 17 and the control rod 14 may be separated.

これは、スクラム信号の入力や冷却材温度の異常な上昇
等の原因がないのに制御棒14がスクラムされることで
あり、誤動作となる。この誤動作によるスクラム状態を
解除し原子炉を平常運転状態に復旧する為には、スクラ
ムの原因を種々調査した上で原因が何らかの異常による
ものでは無いことを確認する必要がある。これらの調査
、確認には非常に長時間を要し、原子炉の稼動率の低下
乃至は運転コストの増加等を招いていた。
This is when the control rod 14 is scrammed even though there is no cause such as input of a scram signal or abnormal rise in coolant temperature, resulting in a malfunction. In order to release the scram caused by this malfunction and restore the reactor to normal operation, it is necessary to investigate various causes of the scram and confirm that the cause is not due to some kind of abnormality. These investigations and confirmations require a very long time, leading to a decrease in the operating rate of the reactor or an increase in operating costs.

本発明の目的は、制御棒に及ぼされる外力に基因するス
クラム機構の誤動作を防止した原子炉停止装置を提供す
ることにある。
An object of the present invention is to provide a nuclear reactor shutdown device that prevents malfunctions of a scram mechanism caused by external forces applied to control rods.

〔発明の構成〕[Structure of the invention]

(問題点を解決するための手段) 本発明においては、制御棒駆動機構に設けられた延長管
に案内されて昇降自在とされた電磁石と、上端部に固着
された磁性体が電磁石に吸着されて垂下され、炉心内に
設置された案内管内に挿抜自在とされた制御棒とを有す
る原子炉停止装置に、電磁石を延長管に係止する自在継
手を設けた。
(Means for Solving the Problems) In the present invention, an electromagnet that can be raised and lowered by being guided by an extension tube provided in a control rod drive mechanism, and a magnetic body fixed to the upper end are attracted to the electromagnet. The nuclear reactor shutdown device has a control rod that hangs down and can be inserted into and removed from a guide tube installed in the reactor core, and is equipped with a universal joint that locks an electromagnet to an extension tube.

(作用) 電磁石に吸着されて保持された制御棒は、原子炉の通常
運転中に、たとえばそれが浸漬されている冷却材の挙動
に励起されて振動などを起しても、この振動力は自在継
手に吸収されるので制御棒と電磁石間の吸着面を離反す
るような応力は作用しない。したがって電磁石の吸着力
を積極的に失わせて制御棒を落下させ、原子炉を停止さ
せる本来のスクラム動作以外の原因によって、原子炉停
止機能が誤動作することは防止される。
(Function) Even if a control rod held by an electromagnet vibrates during normal operation of a nuclear reactor, for example due to the behavior of the coolant in which it is immersed, this vibrational force will be suppressed. Since it is absorbed by the universal joint, there is no stress that would cause the attraction surface between the control rod and the electromagnet to separate. Therefore, the nuclear reactor shutdown function is prevented from malfunctioning due to causes other than the original scram operation in which the control rods are dropped by actively losing the attraction force of the electromagnets and the reactor is shut down.

(実施例) 以下本発明の一実施例を第1図を参照して説明する。(Example) An embodiment of the present invention will be described below with reference to FIG.

第1図は本発明の一実施例の要部を示す断面図であり、
第1図において高速増殖炉に設けられた延長管7は、下
端部の内側が球面形状7aをなして閉じられその中心に
開口21が設けられている。この延長管7に対して制御
棒14を吸着するための電磁石17は次のように取付け
られている。
FIG. 1 is a sectional view showing a main part of an embodiment of the present invention.
In FIG. 1, an extension tube 7 installed in a fast breeder reactor has a closed inner side at a lower end forming a spherical shape 7a, and an opening 21 is provided in the center thereof. An electromagnet 17 for attracting the control rod 14 to the extension tube 7 is attached as follows.

鉄心1.7e及びこれに巻回されたコイル17cからな
る電磁石17は、外側が非磁性金属たとえばステンレス
鋼製のカバー17aによって覆われている。 このカバ
ー17aは大略版状の外形とされ、 その頚状部17b
が延長管7の開口21に一定の間隙22を持って挿入さ
れている。頚状部17bの外側にはおねじが設けられ、
延長管7の内側からナツト19aがが螺合され、これに
よって電磁石17と延長管7は自在継手19を形成して
結合される。ナツト19aの底面は、延長管7の下端部
内側の球面形状7aと合致する形状にしておけばなお都
合がよい。頚状部17bにはコイル17cに接続される
ケーブル18が挿通されたうえ、 シール材17dによ
って封じられている。
An electromagnet 17 consisting of an iron core 1.7e and a coil 17c wound around the core 1.7e is covered on the outside by a cover 17a made of a non-magnetic metal such as stainless steel. This cover 17a has an approximately block-shaped outer shape, and its neck portion 17b
is inserted into the opening 21 of the extension tube 7 with a certain gap 22 in between. A male thread is provided on the outside of the neck portion 17b,
A nut 19a is screwed into the extension tube 7 from the inside thereof, whereby the electromagnet 17 and the extension tube 7 are connected by forming a universal joint 19. It is more convenient if the bottom surface of the nut 19a has a shape that matches the spherical shape 7a inside the lower end of the extension tube 7. A cable 18 connected to the coil 17c is inserted through the neck portion 17b and is sealed with a sealing material 17d.

またカバー17aの底面隅角部は全周にわたり斜めに裁
断され、円錐台が接続された形状とされている。
Further, the corner portions of the bottom surface of the cover 17a are cut obliquely over the entire circumference, and have a shape in which truncated cones are connected.

制御棒14の上端には磁性体16が固着され、その上端
はカバー17aの底面の円錐台形状に合致する凹陥形状
とされている。
A magnetic body 16 is fixed to the upper end of the control rod 14, and the upper end has a concave shape that matches the truncated cone shape of the bottom surface of the cover 17a.

次にこれの作用について述べる。Next, the effect of this will be described.

制御棒14は、通常の原子炉の運転状態においては、ケ
ーブル18を通じて適宜の電源から通電されたコイル1
7cによって励磁された電磁石17に吸着され、延長管
7が昇降調節されて原子炉の運転状態によって定められ
る一定の挿入位置に保たれている。
In normal nuclear reactor operating conditions, the control rods 14 are connected to coils 1 that are energized from an appropriate power source through a cable 18.
The extension tube 7 is attracted by the electromagnet 17 excited by the magnet 7c, and is adjusted up and down to be maintained at a constant insertion position determined by the operating state of the reactor.

制、御捧14は、それが挿入されている図示を省略した
案内管内の冷却材の流れの影響をうけて、高周波数で振
動したり揺れたりしている。これらの振動乃至は揺れは
電磁石17にそのまま伝わるが、電磁石17と延長管7
の間には自在継手19が介在し、とくに電磁石17の横
方向の振動は、間隙22に吸収されて延長管7に拘束さ
れることはないので、電磁石17と制御棒14の磁性体
16の吸着面に曲げあるいはねじり応力が生じ難くなり
、電磁石17の吸着力が存在するにもかかわらず、磁性
体16が電磁石17から離脱し制御棒14がその自重に
よって落下するようなことはなくなる。
The controller 14 vibrates and shakes at a high frequency under the influence of the flow of coolant in a guide tube (not shown) into which it is inserted. These vibrations or shaking are directly transmitted to the electromagnet 17, but the electromagnet 17 and the extension tube 7
A universal joint 19 is interposed between the electromagnet 17 and the magnetic body 16 of the control rod 14, so that the lateral vibration of the electromagnet 17 is absorbed by the gap 22 and is not restrained by the extension tube 7. Bending or torsional stress is less likely to occur on the attracting surface, and even though the attracting force of the electromagnet 17 exists, the magnetic body 16 will not separate from the electromagnet 17 and the control rod 14 will not fall due to its own weight.

また電磁石17のカバー17aの底部は円錐台状に凸部
を形成し、磁性体16の上端の凹部に嵌入して吸着して
いるので、制御棒14すなわち磁性体16が振動しても
、吸着面の摺動ずれが起こらない。さらに正常のスクラ
ム動作によって電磁石17の磁力が失われた結果落下し
た制御棒14を、スクラム要因復帰後に再び励磁した電
磁石17を近付けて吸着する場合、たとえば電磁石17
と制御棒14の中心を一致させて吸着させる等適正な相
互位置関係を容易に得ることができる。
In addition, the bottom of the cover 17a of the electromagnet 17 forms a convex part in the shape of a truncated cone, which fits into the recess at the upper end of the magnetic body 16 and is attracted to it, so even if the control rod 14, that is, the magnetic body 16 vibrates, No sliding displacement of surfaces occurs. Further, when the control rod 14 that has fallen as a result of the loss of the magnetic force of the electromagnet 17 due to normal scram operation is attracted by bringing the electromagnet 17, which has been re-energized again after the scram factor has been restored, close to the electromagnet 17, for example, the electromagnet 17
An appropriate mutual positional relationship can be easily obtained, such as by aligning the centers of the control rods 14 and attracting them.

さらに本発明においては、上述した実施例に加えてたと
えば第2図に示すように、電磁石17の上端面と延長管
7の下端面の間にはね2oを設け、このばね20の中立
状態にて、電磁石17の頚状部17bが延長管7の開口
21の中心に位置する−ようににしてもよく、このばね
2oの求心力にょって、たとえば制御棒14が切離され
ているときの延長管7に対する電磁石17の位置を一定
に保つことができるので、分離している制御棒14に励
磁した電磁石17を近付けて吸着する場合などに、相互
の位置合わせが容易に行なえる。
Furthermore, in the present invention, in addition to the above-described embodiment, as shown in FIG. The neck portion 17b of the electromagnet 17 may be located at the center of the opening 21 of the extension tube 7, and the centripetal force of the spring 2o may be used, for example, when the control rod 14 is separated. Since the position of the electromagnet 17 with respect to the extension tube 7 can be kept constant, mutual alignment can be easily performed when the excited electromagnet 17 is brought close to the separated control rod 14 and attracted.

なお上述したものにおいては自在継手を延長管7と電磁
石17の間に設けたが、これを制御棒14と磁性体16
の間に設けてもよい。
In addition, in the above-described example, a universal joint is provided between the extension tube 7 and the electromagnet 17, but this is also provided between the control rod 14 and the magnetic body 16.
It may be provided in between.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、電磁石によって保持された制御棒が、
電磁石の保磁力が維持されているにもかかわらず、冷却
材の流力振動あるいは地震による揺れ等の流体力によっ
て電磁石から分離落下し、原子炉をスクラムしてしまう
誤動作を防止することが可能となり、誤動作によるスク
ラムならびにその調査・復旧作業を無くした信頼性の高
い原子炉停止装置を提供し、原子炉の稼動率を向上する
ことができるという効果がある。
According to the invention, the control rod held by the electromagnet is
Even though the coercive force of the electromagnet is maintained, it is possible to prevent malfunctions in which the coolant separates from the electromagnet and falls due to fluid force such as hydrodynamic vibration of the coolant or shaking caused by an earthquake, causing a scram of the reactor. The present invention provides a highly reliable nuclear reactor shutdown device that eliminates scrams caused by malfunctions and their investigation and recovery work, and has the effect of improving the operating rate of nuclear reactors.

【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の要部を示す断面図、第2図
は本発明の他の実施例の要部を示す断面図、第3図は高
速増殖炉の概略を示す断面図、第4図は第3図の要部を
拡大して示す断面図である。 2・・・炉心      5・・・制御棒駆動機構7・
・・延長管     10・・・案内管14・・・制御
棒     16・・・磁性体17・・・電磁石   
  19・・・自在継手20・・・ばね 代理人 弁理士 則 近 憲 佑 同  第子丸 健 第  1 図        第  2 図第  3 
図 第  4 図
FIG. 1 is a sectional view showing the main parts of one embodiment of the present invention, FIG. 2 is a sectional view showing the main parts of another embodiment of the invention, and FIG. 3 is a sectional view schematically showing a fast breeder reactor. , FIG. 4 is an enlarged cross-sectional view of the main part of FIG. 3. 2... Core 5... Control rod drive mechanism 7.
... Extension tube 10 ... Guide tube 14 ... Control rod 16 ... Magnetic body 17 ... Electromagnet
19...Universal joint 20...Spring agent Patent attorney Rule Chika Ken Yudo Daishimaru Kendai 1 Figure 2 Figure 3
Figure 4

Claims (1)

【特許請求の範囲】 1、制御棒駆動機構に設けられた延長管に案内されて昇
降自在とされた電磁石と、上端部に固着された磁性体が
前記電磁石に吸着されて垂下され炉心内に設置された案
内管内に挿抜自在とされた制御棒とを有する原子炉停止
装置において、前記電磁石を前記延長管に係止する自在
継手を設けたことを特徴とする原子炉停止装置。 2、前記磁性体と前記電磁石との吸着は凹部と凸部の係
合によって相互の位置関係が一義的に定まる接触面によ
って吸着されてなる特許請求の範囲第1項記載の原子炉
停止装置。 3、前記自在継手に調心手段を設けた特許請求の範囲第
1項記載の原子炉停止装置。
[Claims] 1. An electromagnet that can be raised and lowered by being guided by an extension tube provided in a control rod drive mechanism, and a magnetic body fixed to the upper end of the control rod is attracted to the electromagnet and hangs down into the reactor core. What is claimed is: 1. A nuclear reactor shutdown device comprising a control rod that can be inserted into and removed from an installed guide tube, the device comprising a universal joint for locking the electromagnet to the extension tube. 2. The nuclear reactor shutdown device according to claim 1, wherein the magnetic body and the electromagnet are attracted by a contact surface whose mutual positional relationship is uniquely determined by engagement between a concave portion and a convex portion. 3. The nuclear reactor shutdown device according to claim 1, wherein the universal joint is provided with alignment means.
JP62123716A 1987-05-22 1987-05-22 Reactor shutdown device Expired - Lifetime JP2509620B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62123716A JP2509620B2 (en) 1987-05-22 1987-05-22 Reactor shutdown device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62123716A JP2509620B2 (en) 1987-05-22 1987-05-22 Reactor shutdown device

Publications (2)

Publication Number Publication Date
JPS63289487A true JPS63289487A (en) 1988-11-25
JP2509620B2 JP2509620B2 (en) 1996-06-26

Family

ID=14867595

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62123716A Expired - Lifetime JP2509620B2 (en) 1987-05-22 1987-05-22 Reactor shutdown device

Country Status (1)

Country Link
JP (1) JP2509620B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02245695A (en) * 1989-03-20 1990-10-01 Hitachi Ltd Control rod supporting of nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02245695A (en) * 1989-03-20 1990-10-01 Hitachi Ltd Control rod supporting of nuclear reactor

Also Published As

Publication number Publication date
JP2509620B2 (en) 1996-06-26

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