JPH09243775A - Connecting device for reactor control rod driving device - Google Patents

Connecting device for reactor control rod driving device

Info

Publication number
JPH09243775A
JPH09243775A JP8053304A JP5330496A JPH09243775A JP H09243775 A JPH09243775 A JP H09243775A JP 8053304 A JP8053304 A JP 8053304A JP 5330496 A JP5330496 A JP 5330496A JP H09243775 A JPH09243775 A JP H09243775A
Authority
JP
Japan
Prior art keywords
control rod
iron core
temperature
electromagnet
connecting 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.)
Withdrawn
Application number
JP8053304A
Other languages
Japanese (ja)
Inventor
Jiyungo Katou
潤悟 加藤
Koichi Nakai
公一 中井
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 JP8053304A priority Critical patent/JPH09243775A/en
Publication of JPH09243775A publication Critical patent/JPH09243775A/en
Withdrawn legal-status Critical Current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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide, a highly reliable connecting device by providing the device with a push-up pin formed of a material having specified dimension and thermal expansion coefficient, and a thermosensitive member formed of a magnetic material having a specified curie temperature. SOLUTION: When the operation of a reactor is normal, and the temperature of liquid sodium is within a normal range less than 640 deg.C, a sufficient electromagnetic attractive force is generated on the attractive surface 23a of an electromagnet 11 to surely hold a control rod 5 through a control rod connecting shaft 41. When the temperature becomes 640 deg.C or more, the upper end of a thermal expanding pin 47 is flush with attractive surfaces 27a, 29a, and when the temperature is 680 deg.C, the pin 47 is further expanded to protrude its upper end from the upper surface of a self-fusion preventing hardware 45, pushing up the magnet 11 to extend the clearance between the surface 23a and the surfaces 27a, 29a, whereby magnetic flux leakage is increased to significantly reduce the holding force. Thus, the holding force cannot be supported by the dead weight of the control rod 5 and the connecting shaft 41, and is separated and naturally fallen into the reactor core, whereby the control rod 5 is fully inserted into the core to suppress the nuclear reaction.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は、原子炉制御棒駆動
装置に関し、特にそのための切り離し自在の連結装置に
関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor control rod drive device, and more particularly to a detachable connecting device therefor.

【0002】[0002]

【従来の技術】原子炉容器内の炉心の核反応は、一般に
中性子吸収能力を有する原子炉制御棒を原子炉容器外に
置かれた制御棒駆動装置により炉心内に挿入したり、或
いは炉心から引き抜いたりして制御される。そして、原
子炉の安全を守るため何か異常が発生したら原子炉制御
棒(以下制御棒と略称する。)を直ちに炉心内に挿入し
て核反応を停止することが求められている。制御棒の緊
急挿入には、作動の信頼性を確保するため重力落下乃至
自由落下が利用される。
2. Description of the Related Art Generally, a nuclear reaction in a reactor core is carried out by inserting a reactor control rod having a neutron absorption capability into the reactor core by a control rod driving device placed outside the reactor container, or from the reactor core. It is controlled by pulling it out. Then, in order to protect the safety of the reactor, it is required to immediately insert a reactor control rod (hereinafter abbreviated as control rod) into the core to stop the nuclear reaction when an abnormality occurs. For emergency insertion of the control rod, gravity drop or free fall is used to ensure the reliability of operation.

【0003】原子炉制御装置の概要を、液体金属冷却型
高速増殖炉の場合を例に取り説明する。図5において原
子炉の炉心を構成する燃料集合体1の間にこれと同一外
形の制御棒案内管3が設けられ、その中に制御棒5が昇
降自在に設けられている。そして、原子炉容器の上蓋乃
至遮蔽プラグの上の制御棒駆動装置7から制御棒駆動軸
9が垂下し、その下端の電磁石11に制御棒5の連結軸
13の上端が連結されている。このような炉心構成にお
いて、下方から上昇してきた冷却材例えば液体ナトリウ
ム15は、燃料集合体1の中の炉心燃料17に接触して
流れて高温になり、一旦上部の冷却材導入管19に流入
し、その後側方のフローホール21より横方向へ流出す
る。このような冷却材は例えば図示しない中間熱交換器
等に案内されて、外部の熱利用装置への熱搬送媒体と熱
交換される。制御棒5は、制御棒駆動装置7により炉心
内の上下方向位置が変えられ、あるいは炉心から上方に
引き抜かれたり、炉心内に挿入されたりして、炉心内の
核反応或いは出力を調整する。
An outline of the nuclear reactor control device will be described by taking a liquid metal cooling type fast breeder reactor as an example. In FIG. 5, a control rod guide tube 3 having the same outer shape as that of the fuel assembly 1 constituting the core of the nuclear reactor is provided, and the control rod 5 is provided therein so as to be vertically movable. A control rod drive shaft 9 hangs down from the control rod drive device 7 on the upper lid or shield plug of the reactor vessel, and the upper end of the connecting shaft 13 of the control rod 5 is connected to the electromagnet 11 at the lower end thereof. In such a core structure, the coolant, such as liquid sodium 15, rising from below contacts the core fuel 17 in the fuel assembly 1 to flow to a high temperature, and once flows into the coolant introduction pipe 19 in the upper part. After that, it flows out laterally from the flow hole 21 on the side. Such a coolant is guided to, for example, an intermediate heat exchanger (not shown) and exchanges heat with a heat carrier medium to an external heat utilization device. The control rod 5 is adjusted in the vertical position in the core by the control rod drive device 7, is pulled upward from the core, or is inserted into the core to adjust the nuclear reaction or power in the core.

【0004】電磁石11は冷却材導入管19の中に位置
し、燃料集合体1から出てくる加熱冷却材15の温度に
感応して異常時に制御棒駆動軸9と制御棒5との連結を
解放し、制御棒5の自由落下を行わしめるものである。
電磁石11の構造が図6に示されているが、制御棒駆動
軸9の下端に固定された電磁石鉄芯23にコイル25が
埋設されて電磁石11が形成され、コイル25は制御棒
駆動軸9内を通るリード線を介して電源に連絡してい
る。電磁石鉄芯23は、冷却材15の通常温度より20
0℃程度高いキュリー点を持ち且つ飽和磁束密度が高い
磁性材料である純鉄乃至クロムモリブデン鋼からできて
いて、その下端には平らな吸着面23aが形成されてい
る。電磁石11に対向して、制御棒連結軸13の上端に
内側鉄芯27と外側鉄芯29とが配設されている。内側
鉄芯27と外側鉄芯29は、電磁石鉄芯23と同材料か
ら形成され、その上端に平らな吸着面27a,29aが
形成されている。電磁石11が作動すると、一点鎖線で
示す閉じた磁路31が形成されるが、その一部となる内
側鉄芯27と外側鉄芯29との間に温度感知部材33が
外方に露出して設けられている。この温度感知部材33
は、冷却材15の通常温度より50乃至150℃程度高
いキュリー点を持ち且つ飽和磁束密度が高い磁性合金か
らできている。吸着面23a,27a,29aに露出し
て自己融着防止金物35,37が設けられ、これらは吸
着面23a,27a,29aよりわずかに突出してい
て、高温の冷却材15の中での電磁石鉄芯23と内側鉄
芯27及び外側鉄芯29との自己融着を防止する。
The electromagnet 11 is located in the coolant introducing pipe 19 and is adapted to connect the control rod drive shaft 9 and the control rod 5 in the event of an abnormality in response to the temperature of the heating coolant 15 coming out of the fuel assembly 1. The control rod 5 is released to allow the control rod 5 to freely fall.
The structure of the electromagnet 11 is shown in FIG. 6, and the coil 25 is embedded in the electromagnet iron core 23 fixed to the lower end of the control rod drive shaft 9 to form the electromagnet 11. It connects to the power supply through a lead wire passing through. The electromagnet iron core 23 has a temperature of 20 degrees higher than the normal temperature of the coolant 15.
It is made of pure iron or chromium molybdenum steel, which is a magnetic material having a high Curie point of about 0 ° C. and a high saturation magnetic flux density, and a flat adsorption surface 23a is formed at its lower end. An inner iron core 27 and an outer iron core 29 are arranged at the upper end of the control rod connecting shaft 13 so as to face the electromagnet 11. The inner iron core 27 and the outer iron core 29 are made of the same material as the electromagnet iron core 23, and have flat attracting surfaces 27a and 29a formed at the upper ends thereof. When the electromagnet 11 is actuated, a closed magnetic path 31 shown by the alternate long and short dash line is formed. It is provided. This temperature sensing member 33
Is made of a magnetic alloy having a Curie point higher than the normal temperature of the coolant 15 by about 50 to 150 ° C. and a high saturation magnetic flux density. Self-fusing prevention metal fittings 35, 37 are provided so as to be exposed on the adsorbing surfaces 23a, 27a, 29a, and these are slightly protruding from the adsorbing surfaces 23a, 27a, 29a, and are electromagnet irons in the high temperature coolant 15. The self-bonding of the core 23 with the inner iron core 27 and the outer iron core 29 is prevented.

【0005】原子炉の運転時には前述した電磁石11の
コイル25に電流が流され、図6に示すように制御棒駆
動軸9と制御棒連結軸13とは連結され、図5に示すよ
うに制御棒駆動装置7により制御棒5が上下される。し
かるに燃料集合体1を出る冷却材15の温度に異常上昇
があると、その冷却材温度が温度感知部材33に伝えら
れ、その温度がキュリー点に近づき、飽和磁束密度が急
激に低下する。このため磁路31を流れる磁束が減少し
て電磁石11の保持力が減少し、制御棒5の自重を支え
られなくなって制御棒5が制御棒案内管3の中に落下す
る。要するに、何か異常があって燃料集合体1を出る冷
却材15の温度が通常時より高くなると、電磁石11の
保持力が低下して制御棒5を炉心内に自由落下せしめ、
炉心内の核反応を抑制し、事故の発生を防止する。
During operation of the nuclear reactor, a current is applied to the coil 25 of the electromagnet 11 described above, the control rod drive shaft 9 and the control rod connecting shaft 13 are connected as shown in FIG. 6, and the control is performed as shown in FIG. The control rod 5 is moved up and down by the rod drive device 7. However, if the temperature of the coolant 15 exiting the fuel assembly 1 is abnormally increased, the coolant temperature is transmitted to the temperature sensing member 33, the temperature approaches the Curie point, and the saturation magnetic flux density sharply decreases. Therefore, the magnetic flux flowing through the magnetic path 31 is reduced, the holding force of the electromagnet 11 is reduced, the weight of the control rod 5 cannot be supported, and the control rod 5 falls into the control rod guide tube 3. In short, if there is something abnormal and the temperature of the coolant 15 exiting the fuel assembly 1 becomes higher than normal, the holding force of the electromagnet 11 decreases and the control rod 5 is allowed to fall freely into the core.
Suppress nuclear reactions in the core to prevent accidents.

【0006】[0006]

【発明が解決しようとする課題】以上説明したような制
御棒駆動軸と制御棒との連結装置は、若干幅のある正常
温度範囲では絶対に制御棒を切り離してはならず(切り
離しが起きると別の事故が発生する可能性がある。)、
且つ正常温度範囲を逸脱したら直ちに切り離しを行わな
ければならない。前述のような温度感知部材のみを用い
て冷却材の異常温度を感知し、電磁石の作動を解放する
連結装置では、その作動が材料の磁気特性に大きく依存
するため、これを冷却材の正常温度範囲が550〜60
0℃であり、且つ切り離し温度が680℃である実用型
の高速増殖炉に適用した場合、信頼性に問題がある。従
って、本発明の課題は信頼性の高い温度感知解放型の原
子炉制御棒駆動装置用連結装置を提供するにある。
The control rod drive shaft-control rod connecting device as described above must never disconnect the control rod in the normal temperature range where the control rod drive shaft and control rod are slightly wide (when disconnection occurs, Another accident may occur.),
And if it deviates from the normal temperature range, it must be disconnected immediately. In the coupling device that detects the abnormal temperature of the coolant by using only the temperature sensing member as described above and releases the operation of the electromagnet, the operation greatly depends on the magnetic characteristics of the material. Range is 550-60
When applied to a practical fast breeder reactor having a temperature of 0 ° C. and a disconnection temperature of 680 ° C., there is a problem in reliability. SUMMARY OF THE INVENTION Therefore, an object of the present invention is to provide a highly reliable temperature sensing and releasing type reactor control rod drive coupling device.

【0007】[0007]

【課題を解決するための手段】上述の課題を解決するた
め本発明によれば、原子炉制御棒駆動装置から延びる制
御棒駆動軸と制御棒上部の制御棒連結軸との間に設けら
れる切り離し自在の原子炉制御棒駆動装置用連結装置
は、制御棒駆動軸の下端に固定され下向きの吸着面が形
成された電磁石と、その電磁石の下向き吸着面に対向し
て前記制御棒連結軸の上端に配設され上向きの吸着面が
形成された内側鉄芯及び外側鉄芯と、内側鉄芯及び外側
鉄芯と組み合わされて制御棒連結軸の上端に設けられ内
側鉄芯及び外側鉄芯と協働して前記電磁石を通る磁路を
形成する温度感知部材と、制御棒連結軸に沿って伸長自
在に設けられ内側鉄芯及び外側鉄芯の上向き吸着面に出
没する押し上げピンとから構成され、その押し上げピン
は、原子炉冷却材の正常温度範囲より上方に逸脱した異
常高温に対応する所定の温度で上向き吸着面から突出し
て下向き吸着面を押すような好適な寸法及び熱膨張係数
が得られる材料から構成されており、更に温度感知部材
は前記所定温度より若干高い温度のキュリー点を有する
磁性材料から構成される。一般に前記伸長ピンは細長い
部材から構成すると、前述のような条件を満足しやす
く、この場合には座屈防止リングで制御棒駆動軸に保持
されているが、少なくとも3本程度を等円周間隔で制御
棒連結軸の回りに配設するのが好適である。更に、本発
明の原子炉制御棒駆動装置用連結装置が、原子炉冷却材
が高温の液体金属ナトリウムのように、その中で接触す
る部材が自己融着を起こしやすいものであるときは、電
磁石の下向き吸着面とこれに対向する上向き吸着面に、
互いに対向する非磁性材料の自己融着防止部材をそれぞ
れ埋め込み、同自己融着防止部材の少なくとも一方は前
記両吸着面からそれぞれ僅かに突出させ、電磁石の磁路
の磁束に悪影響を与えないで両吸着面を僅かに離してい
るのが好適である。
In order to solve the above-mentioned problems, according to the present invention, a disconnection is provided between a control rod drive shaft extending from a reactor control rod drive device and a control rod connecting shaft above the control rod. A flexible reactor control rod drive connecting device comprises an electromagnet fixed to the lower end of the control rod drive shaft and having a downward attracting face formed thereon, and an upper end of the control rod connecting shaft facing the downward attracting face of the electromagnet. And an inner iron core and an outer iron core, each of which has an upwardly attracting surface and is combined with the inner iron core and the outer iron core, and is provided at the upper end of the control rod connecting shaft to cooperate with the inner iron core and the outer iron core. A temperature sensing member that works to form a magnetic path that passes through the electromagnet, and a push-up pin that is provided so as to be extendable along the control rod connecting shaft and that appears on the upwardly attracting surface of the inner iron core and the outer iron core. The push-up pin is for the reactor coolant. It is made of a material that has a suitable size and coefficient of thermal expansion such that it projects from the upward adsorption surface and pushes the downward adsorption surface at a predetermined temperature corresponding to an abnormally high temperature deviating above the normal temperature range. The member is made of a magnetic material having a Curie point slightly higher than the predetermined temperature. In general, if the extension pin is formed of an elongated member, it is easy to satisfy the above-mentioned conditions. In this case, the extension pin is held by the buckling prevention ring on the control rod drive shaft, but at least about three pins are arranged at equal circumferential intervals. It is preferable to dispose the control rod around the control rod connecting shaft. Further, when the reactor control rod drive connecting device of the present invention is such that the reactor coolant is such as hot liquid metal sodium, the members in contact therewith are likely to cause self-fusion, the electromagnet On the downward suction surface and the upward suction surface facing it,
Self-fusion prevention members made of non-magnetic material facing each other are embedded respectively, and at least one of the self-fusion prevention members is slightly protruded from each of the attraction surfaces to prevent adverse effects on the magnetic flux in the magnetic path of the electromagnet. It is preferable that the adsorption surfaces are slightly separated.

【0008】[0008]

【発明の実施の形態】以下、添付の図面を参照して本発
明の実施形態を説明するが、従来の装置の部材と同じも
のには同一の符号を付しており、それらについての前述
の説明は本実施形態においても適用される。先ず図1を
参照するに、制御棒駆動軸9の下端に固定された電磁石
鉄芯23にコイル25が埋設されて電磁石11が形成さ
れ、コイル25は駆動軸9内を通るリード線を介して図
示しない電源に連絡している。電磁石鉄芯23は、クロ
ムモリブデン鋼からできているが、これは冷却材である
液体ナトリウムの通常温度より200℃程度高いキュリ
ー点を持ち且つ飽和磁束密度が高い磁性材料である。こ
の電磁石鉄芯23は、同様な磁気特性を持つ純鉄で製作
しても良い。そしてその下端には平らな吸着面23aが
下向きに形成され、中央部には案内作用を行う突起が形
成されている。そしてコイル25の下方に環状の非磁性
材料からなる自己融着防止金物35が、吸着面23aよ
り僅かに突出して埋め込まれている。
BEST MODE FOR CARRYING OUT THE INVENTION Embodiments of the present invention will be described below with reference to the accompanying drawings, in which the same members as those of the conventional apparatus are designated by the same reference numerals, and the above-mentioned description will be given thereto. The description also applies to this embodiment. First, referring to FIG. 1, an electromagnet 11 is formed by embedding a coil 25 in an electromagnet iron core 23 fixed to the lower end of the control rod drive shaft 9, and the coil 25 is formed through a lead wire passing through the drive shaft 9. Contacting a power source (not shown). The electromagnet iron core 23 is made of chromium molybdenum steel, which is a magnetic material having a Curie point higher than the normal temperature of liquid sodium as a coolant by about 200 ° C. and a high saturation magnetic flux density. The electromagnet iron core 23 may be made of pure iron having similar magnetic characteristics. A flat suction surface 23a is formed downward at the lower end thereof, and a projection for guiding is formed at the center. Under the coil 25, a self-fusing prevention metal fitting 35 made of an annular non-magnetic material is embedded so as to slightly project from the attraction surface 23a.

【0009】一方制御棒5の上端に取り付けれた制御棒
連結軸41の上端には、内側鉄芯27とこれを取り囲む
外側鉄芯29とが配設されている。内側鉄芯27と外側
鉄芯29は、電磁石鉄芯23と同様なクロムモリブデン
鋼から製作されており、その上端に平らな吸着面27
a,29aが上向きに、即ち電磁石11の下向き吸着面
23aに対向して形成されている。内側鉄芯27を囲み
且つ外側鉄芯29の下方に位置して温度感知部材43が
設けられていて、これは外側を流れる液体ナトリウムに
接触するように外面が露出している。この温度感知部材
43は、冷却材である液体ナトリウムの通常温度より5
0乃至150℃程度高いキュリー点を持ち且つ飽和磁束
密度が高い磁性合金からできている。そして、図から明
らかなように吸着面27a,29aに囲まれて環状の非
磁性材料からなる自己融着防止金物45が設けられ、こ
れは自己融着防止金物35に対向している。自己融着防
止金物35、45は、図示のように接触したとき吸着面
27a,29aと吸着面23aとの間に0.05mm程度
の隙間を画成する。この程度の隙間は、後述するような
磁路の磁束に影響を及ぼさない。なお、自己融着防止金
物35、45は、冷却材が液体ナトリウムでなく、他の
材質のもので接触する材料が自己融着を起こす心配が無
いときは、これを省略して構造を簡単化しても良い。
On the other hand, an inner iron core 27 and an outer iron core 29 surrounding the inner iron core 27 are arranged at the upper end of a control rod connecting shaft 41 attached to the upper end of the control rod 5. The inner iron core 27 and the outer iron core 29 are made of chromium molybdenum steel similar to the electromagnet iron core 23, and have a flat attracting surface 27 on the upper end thereof.
a and 29a are formed upward, that is, facing the downward attracting surface 23a of the electromagnet 11. Surrounding the inner iron core 27 and below the outer iron core 29 is a temperature sensing member 43, the outer surface of which is exposed for contact with liquid sodium flowing outside. The temperature sensing member 43 has a temperature higher than the normal temperature of the liquid sodium as a coolant
It is made of a magnetic alloy having a high Curie point of about 0 to 150 ° C. and a high saturation magnetic flux density. Then, as is apparent from the figure, a self-fusing prevention metal fitting 45 made of an annular non-magnetic material is provided surrounded by the adsorption surfaces 27a and 29a, and it faces the self-fusing protection metal fitting 35. The self-fusing prevention hardware 35, 45 defines a gap of about 0.05 mm between the suction surfaces 27a, 29a and the suction surface 23a when they are in contact with each other as shown in the figure. The gap of this degree does not affect the magnetic flux in the magnetic path, which will be described later. Note that the self-fusing prevention metal parts 35, 45 are not liquid sodium as a coolant, and when there is no concern that the material in contact with another material will cause self-fusing, the structure is simplified and omitted. May be.

【0010】更に制御棒連結軸41の小径部の外周面に
は3本の軸方向溝が等円周間隔で形成され、これにそれ
ぞれ直径3mmのオーステナイト系ステンレス鋼製押し上
げピン即ち熱膨張ピン47が通されている。熱膨張ピン
47の下端は固定され、一方上部は制御棒連結軸41の
大径部、温度感知部材43及び自己融着防止部材45に
形成された貫通孔内を延びているが、この部分は図2に
拡大して示されている。熱膨張ピン47の長さは略1メ
ートルとなっており、インコネル(商標)に相当するニ
ッケル基合金からなる制御棒連結軸41に対しおよそ5
×10-6mm/mm/℃の実効熱膨張率を持つようになってい
て、温度が640℃のときにその上端が自己融着防止金
物45の上面(吸着面27a,29aと同一面)と面一
になるように寸法が設定されている。換言すれば、通常
の温度範囲では、図2に示すように熱膨張ピン47の上
端が、吸着面27a,29aより下位にある。図1に戻
って、熱膨張ピン47は、座屈変形防止リング49によ
って水平方向に支持されていて、上端が自己融着防止金
物35に突き当たっても座屈しない。
Further, on the outer peripheral surface of the small diameter portion of the control rod connecting shaft 41, three axial grooves are formed at equal circumferential intervals, and austenitic stainless steel push-up pins or thermal expansion pins 47 each having a diameter of 3 mm are formed on the grooves. Has been passed through. The lower end of the thermal expansion pin 47 is fixed, while the upper part thereof extends through the large diameter portion of the control rod connecting shaft 41, the through hole formed in the temperature sensing member 43 and the self-fusion prevention member 45. It is shown enlarged in FIG. The length of the thermal expansion pin 47 is approximately 1 meter, which is about 5 with respect to the control rod connecting shaft 41 made of a nickel-based alloy corresponding to Inconel (trademark).
It has an effective thermal expansion coefficient of × 10 -6 mm / mm / ° C, and its upper end is the upper surface of the self-fusing prevention metal 45 when the temperature is 640 ° C (the same surface as the adsorption surfaces 27a and 29a). The dimensions are set to be flush with. In other words, in the normal temperature range, the upper end of the thermal expansion pin 47 is below the adsorption surfaces 27a and 29a as shown in FIG. Returning to FIG. 1, the thermal expansion pin 47 is horizontally supported by the buckling deformation preventing ring 49, and does not buckle even if its upper end abuts against the self-fusion preventing metal 35.

【0011】上述の構成の連結装置40において、原子
炉の運転が正常に行われ、炉心の燃料集合体から流出し
て熱膨張ピン47及び温度感知部材43に接触する液体
ナトリウムの温度が640℃以下の正常範囲にあるとき
は、熱膨張ピン47の上端は図2に示すように自己融着
防止金物45の上面及び吸着面27a,29aより下方
にあり閉じた磁路51が形成される。即ち、電磁石11
の吸着面23aに十分大きな電磁吸着力が発生し、制御
棒連結軸41を介して制御棒5をしっかりと保持する。
これに対し、液体ナトリウムの温度が640℃になると
熱膨張により相対的に伸長した熱膨張ピン47の上端が
吸着面27a,29aと面一になり、更に680℃にな
ると図3に幾分誇張して示すように自己融着防止金物3
5,45の間に0.20mm程度の隙間が生ずる。更に前
述の温度上昇により温度感知部材43は、キュリー点に
近付き飽和磁束密度が減少し保持力も減少する。このよ
うな温度変化と保持力の変化の関係が図4のグラフに示
されている。図4において、実線が本実施形態による保
持力の変化を示し、破線が熱膨張ピンを有しない従来型
の連結装置の保持力の変化を示している。本実施形態に
よれば、熱膨張ピン47の熱膨張により、その上端が自
己融着防止金物45の上面から突き出し、電磁石11を
押し上げ、吸着面23aと吸着面27a,29aとの隙
間を拡大し、磁束の漏れを増大するので、従来のものに
比し大きく保持力が低下する。このようにして、保持力
は制御棒5及び制御棒連結軸41の自重を支持できなく
なり、切り離されて炉心内に自由落下して挿入される。
即ち制御棒5が炉心内に全挿入されて核反応を抑制す
る。
In the coupling device 40 having the above-described structure, the temperature of the liquid sodium which is normally operated and flows out from the fuel assembly of the core and contacts the thermal expansion pin 47 and the temperature sensing member 43 is 640 ° C. When in the normal range below, the upper end of the thermal expansion pin 47 is below the upper surface of the self-fusing prevention metal 45 and the adsorption surfaces 27a and 29a, and a closed magnetic path 51 is formed, as shown in FIG. That is, the electromagnet 11
A sufficiently large electromagnetic attraction force is generated on the attraction surface 23a of the above, and the control rod 5 is firmly held via the control rod connecting shaft 41.
On the other hand, when the temperature of the liquid sodium reaches 640 ° C., the upper end of the thermal expansion pin 47, which is relatively expanded due to thermal expansion, becomes flush with the adsorption surfaces 27 a and 29 a, and when it reaches 680 ° C., it is somewhat exaggerated in FIG. As shown, the self-fusing prevention hardware 3
A gap of about 0.20 mm is formed between 5,45. Further, due to the above-mentioned temperature rise, the temperature sensing member 43 approaches the Curie point, the saturation magnetic flux density decreases, and the holding force also decreases. The relationship between such temperature changes and holding force changes is shown in the graph of FIG. In FIG. 4, the solid line shows the change of the holding force according to the present embodiment, and the broken line shows the change of the holding force of the conventional coupling device having no thermal expansion pin. According to the present embodiment, due to the thermal expansion of the thermal expansion pin 47, the upper end thereof protrudes from the upper surface of the self-fusing prevention metal fitting 45, pushes up the electromagnet 11, and expands the gap between the adsorption surface 23a and the adsorption surfaces 27a and 29a. Since the leakage of magnetic flux is increased, the holding force is greatly reduced as compared with the conventional one. In this way, the holding force cannot support the own weight of the control rod 5 and the control rod connecting shaft 41, and is separated and inserted into the core by free fall.
That is, the control rod 5 is fully inserted into the core to suppress the nuclear reaction.

【0012】[0012]

【発明の効果】以上説明したように、本発明によれば冷
却材の温度上昇に応じて熱膨張する押し上げピンが所定
温度以上になると制御棒駆動軸の下端の電磁石と、制御
棒連結軸の上端との間隔を増大し、温度感知部材の飽和
磁束密度の減少と相俟って電磁石の保持力を大きく減少
するので、異常時の制御棒の切り離しを確実に行うこと
ができる。更に冷却材の正常温度範囲では、前記間隔は
不変であるから十分な保持力が得られ、誤って制御棒を
切り離してしまうことはない。
As described above, according to the present invention, when the push-up pin that thermally expands in response to the temperature rise of the coolant reaches a predetermined temperature or higher, the electromagnet at the lower end of the control rod drive shaft and the control rod connecting shaft are connected. Since the distance from the upper end is increased and the holding force of the electromagnet is greatly reduced in combination with the decrease in the saturation magnetic flux density of the temperature sensing member, the control rod can be reliably disconnected in the event of an abnormality. Further, in the normal temperature range of the coolant, since the interval is unchanged, a sufficient holding force is obtained, and the control rod is not accidentally disconnected.

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

【図1】本発明の実施形態の全体構成を示す一部切欠き
立断面図である。
FIG. 1 is a partially cutaway vertical sectional view showing an overall configuration of an embodiment of the present invention.

【図2】前記実施形態の作用を説明する部分拡大図であ
る。
FIG. 2 is a partially enlarged view for explaining the operation of the embodiment.

【図3】前記実施形態の作用を説明する部分拡大図であ
る。
FIG. 3 is a partially enlarged view for explaining the operation of the embodiment.

【図4】前記実施形態による保持力の変化を従来のもの
と比較して示すグラフである。
FIG. 4 is a graph showing a change in holding force according to the above embodiment in comparison with a conventional one.

【図5】本発明が適用される原子炉制御棒駆動システム
の一例の全体概念図である。
FIG. 5 is an overall conceptual diagram of an example of a reactor control rod drive system to which the present invention is applied.

【図6】従来装置の概念的部分断面図である。FIG. 6 is a conceptual partial cross-sectional view of a conventional device.

【符号の説明】[Explanation of symbols]

7 制御棒駆動装置 9 制御棒駆動軸 11 電磁石 23 電磁石鉄芯 23a 吸着面 27 内側鉄芯 27a 吸着面 29 外側鉄芯 29a 吸着面 35 自己融着防止金物 40 連結装置 41 制御棒連結軸 43 温度感知部材 45 自己融着防止金物 47 熱膨張ピン 49 座屈防止リング 7 Control rod drive device 9 Control rod drive shaft 11 Electromagnet 23 Electromagnet Iron core 23a Adsorption surface 27 Inner iron core 27a Adsorption surface 29 Outer iron core 29a Adsorption surface 35 Self-fusing prevention hardware 40 Coupling device 41 Control rod connection shaft 43 Temperature sensing Member 45 Self-fusion prevention hardware 47 Thermal expansion pin 49 Buckling prevention ring

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】 原子炉制御棒駆動装置から延びる制御棒
駆動軸と制御棒上部の制御棒連結軸との間に設けられる
切り離し自在の連結装置であって、 前記制御棒駆動軸の下端に固定され下向きの吸着面が形
成された電磁石と、 前記電磁石の下向き吸着面に対向して前記制御棒連結軸
の上端に配設され上向きの吸着面が形成された内側鉄芯
及び外側鉄芯と、 前記内側鉄芯及び前記外側鉄芯と組み合わされて前記制
御棒連結軸の上端に設けられ前記内側鉄芯及び前記外側
鉄芯と協働して前記電磁石を通る磁路を形成する温度感
知部材と、 前記制御棒連結軸に沿って伸長自在に設けられ前記内側
鉄芯及び前記外側鉄芯の上向き吸着面に出没する押し上
げピンとを有し、 前記押し上げピンは所定の温度で前記上向き吸着面から
突出するように寸法及び熱膨張係数が選定された材料か
ら構成されており、 前記温度感知部材は、前記所定温度より若干高い温度の
キュリー点を有する磁性材料から構成されていることを
特徴とする原子炉制御棒駆動装置用連結装置。
1. A detachable connecting device provided between a control rod drive shaft extending from a reactor control rod drive device and a control rod connecting shaft above the control rod, the device being fixed to a lower end of the control rod drive shaft. An electromagnet having a downwardly attracting surface formed thereon, and an inner iron core and an outer iron core having an upwardly attracting surface formed at the upper end of the control rod connecting shaft so as to face the downwardly attracting surface of the electromagnet. A temperature sensing member which is provided at an upper end of the control rod connecting shaft in combination with the inner iron core and the outer iron core, and which cooperates with the inner iron core and the outer iron core to form a magnetic path passing through the electromagnet; A push-up pin protruding and retracting from the upward suction surface of the inner iron core and the outer iron core, the push-up pin protruding from the upward suction surface at a predetermined temperature. Size and For a reactor control rod drive, the temperature sensing member is made of a magnetic material having a Curie point at a temperature slightly higher than the predetermined temperature. Coupling device.
【請求項2】 前記下向き吸着面と前記上向き吸着面に
は、互いに対向する自己融着防止部材がそれぞれ埋め込
まれて設けられ、同自己融着防止部材の少なくとも一方
は前記両吸着面から僅かに突出し、同両吸着面の間に僅
かな隙間を形成することを特徴とする請求項1記載の原
子炉制御棒駆動装置用連結装置。
2. Self-fusion prevention members facing each other are embedded in the downward suction surface and the upward suction surface, respectively, and at least one of the self-fusion prevention members is slightly separated from both suction surfaces. 2. The coupling device for a reactor control rod driving device according to claim 1, wherein the coupling device projects and a small gap is formed between the suction surfaces.
【請求項3】 前記押し上げピンは細長い部材から構成
され、座屈防止リングにより前記制御棒連結軸に保持さ
れていることを特徴とする請求項1又は請求項2記載の
原子炉制御棒駆動装置用連結装置。
3. The reactor control rod drive device according to claim 1, wherein the push-up pin is composed of an elongated member and is held on the control rod connecting shaft by a buckling prevention ring. Connecting device.
JP8053304A 1996-03-11 1996-03-11 Connecting device for reactor control rod driving device Withdrawn JPH09243775A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP8053304A JPH09243775A (en) 1996-03-11 1996-03-11 Connecting device for reactor control rod driving device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP8053304A JPH09243775A (en) 1996-03-11 1996-03-11 Connecting device for reactor control rod driving device

Publications (1)

Publication Number Publication Date
JPH09243775A true JPH09243775A (en) 1997-09-19

Family

ID=12938989

Family Applications (1)

Application Number Title Priority Date Filing Date
JP8053304A Withdrawn JPH09243775A (en) 1996-03-11 1996-03-11 Connecting device for reactor control rod driving device

Country Status (1)

Country Link
JP (1) JPH09243775A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101663133B1 (en) * 2015-08-21 2016-10-07 한국원자력연구원 Extension Shaft Assembly of Bottom-Mounted Control Rod Drive Mechanism

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101663133B1 (en) * 2015-08-21 2016-10-07 한국원자력연구원 Extension Shaft Assembly of Bottom-Mounted Control Rod Drive Mechanism

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