[go: up one dir, main page]

JP2003270375A - Passive reactor shutdown mechanism - Google Patents

Passive reactor shutdown mechanism

Info

Publication number
JP2003270375A
JP2003270375A JP2002068039A JP2002068039A JP2003270375A JP 2003270375 A JP2003270375 A JP 2003270375A JP 2002068039 A JP2002068039 A JP 2002068039A JP 2002068039 A JP2002068039 A JP 2002068039A JP 2003270375 A JP2003270375 A JP 2003270375A
Authority
JP
Japan
Prior art keywords
reactor
control rod
water level
coil
temperature
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
JP2002068039A
Other languages
Japanese (ja)
Inventor
Norihisa Ishida
紀久 石田
Tsutomu Yoritsune
勉 頼経
Sho Imayoshi
祥 今吉
Minoru Nishihara
實 西原
Tsunehiro Sakamaki
凡浩 坂巻
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.)
SHINSEI GIKEN KK
Japan Atomic Energy Agency
Original Assignee
SHINSEI GIKEN KK
Japan Atomic Energy Research Institute
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 SHINSEI GIKEN KK, Japan Atomic Energy Research Institute filed Critical SHINSEI GIKEN KK
Priority to JP2002068039A priority Critical patent/JP2003270375A/en
Publication of JP2003270375A publication Critical patent/JP2003270375A/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

(57)【要約】 【課題】 制御棒ストロークが約1500mm又はそれ以下の
軽水型原子炉の受動的炉停止機構に関する。 【解決手段】 制御棒の全ストロークが磁気回路内に収
まる筒状の電磁石と、その中を貫通し、吸着部に温度感
知合金を挟んだ上下の2本の導磁軸から成る炉停止機構
を、自然循環冷却が出来る様、原子炉運転水位下に没し
て配置し、電磁石部分が水面上に露出するような異常事
象が発生すると、電磁石コイルの熱で温度感知合金の温度
を上昇せしめて吸着力を低下させ、制御棒を吊り下げた
下部導磁軸を切離す事が出来る。
(57) [Summary] A passive reactor shutdown mechanism of a light water reactor having a control rod stroke of about 1500 mm or less. SOLUTION: A furnace stop mechanism comprising a cylindrical electromagnet in which the entire stroke of a control rod is accommodated in a magnetic circuit, and two upper and lower magnetic conducting shafts penetrating therethrough and sandwiching a temperature sensing alloy in an adsorption portion. In order to allow natural circulation cooling, it is placed under the reactor operating water level, and if an abnormal event occurs such that the electromagnet part is exposed above the water surface, the temperature of the temperature sensing alloy is raised by the heat of the electromagnet coil. The suction force is reduced, and the lower magnetic pole on which the control rod is suspended can be separated.

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、適当な駆動機構と
組み合わせ、制御棒駆動ストロークが約1500mm又
はそれ以下の軽水型原子炉の後備炉停止装置として用ら
れる受動的原子炉停止機構に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a passive reactor shutdown mechanism used as a backup reactor shutdown device for a light water reactor having a control rod drive stroke of about 1500 mm or less in combination with an appropriate drive mechanism. is there.

【0002】[0002]

【従来の技術】現行の発電用原子炉において、配管破断
事故等により原子炉水位が下がる事象については、圧力
変化とか水位変化をセンサーで検出し、電気回路を介し
て制御棒駆動機構に原子炉停止の信号を送り、制御棒駆
動装置の電磁石と機構から成る駆動軸切離し機構を作動
し、制御棒を炉心に落下挿入するとか、前記信号により
弁を開け、蓄圧水を制御棒駆動装置の水圧シリンダーに
送り込み、水圧により制御棒を挿入する方法が取られ、
センサー及び電気回路に多重性、多様性を持たせる事で
安全性が確保されている。
2. Description of the Related Art In an existing nuclear reactor for power generation, when the reactor water level drops due to a pipe breakage accident or the like, a pressure change or water level change is detected by a sensor, and the reactor is connected to a control rod drive mechanism via an electric circuit. A stop signal is sent, the drive shaft disconnection mechanism consisting of the electromagnet and mechanism of the control rod drive device is operated, and the control rod is dropped into the core or inserted, or the valve is opened by the above signal and the accumulated water is stored in The method of sending it to the cylinder and inserting the control rod by water pressure is taken,
Safety is ensured by making sensors and electric circuits multiplicity and diversity.

【0003】しかし、今後、需要地近接設置等の小型炉
の実用化においては、従来の方法で出来るものに加え、
簡素で、受動的に作動する炉停止機構が必要である。更
に制御棒の飛び出し事故を無くする為、制御棒駆動機構
を原子炉に内装することも安全性上効果的である。
However, in the future, in the practical application of small furnaces such as installation close to demand areas, in addition to the conventional methods,
There is a need for a simple, passively operated furnace shutdown mechanism. Furthermore, in order to prevent accidents of the control rods popping out, it is also effective in terms of safety to install the control rod drive mechanism in the reactor.

【0004】図7に、特開平11−30683号公報で
公開された小型炉用の制御棒駆動装置で原子炉内装型の
実施例を示す。51は下部導磁軸、52は上部導磁軸で
駆動ねじが加工されている。51の下部には制御棒が取
りつけられ、52の上部はボールナット55にかみ合
い、55はローター56に直結している。56の外側に
はステーター57が取り付けられ、56と併せて電気モ
ーター58を形成する。
FIG. 7 shows an embodiment of a control rod drive device for a small reactor disclosed in Japanese Patent Laid-Open No. 11-30683, which is a reactor internal type. Reference numeral 51 is a lower magnetic axis, 52 is an upper magnetic axis, and a drive screw is processed. A control rod is attached to a lower portion of 51, an upper portion of 52 is engaged with a ball nut 55, and 55 is directly connected to a rotor 56. A stator 57 is attached to the outside of 56 and together with 56 forms an electric motor 58.

【0005】51、52の外側には筒状のコイル53と
磁束案内部材54で構成する電磁石60が取り付けられ
る。60は制御棒の駆動ストロークSより長尺で、51
と52の切離し面59をS全域に渡り、60の磁界内に
収容している。従って、60に給電すると51と52は
吸着され、58を正回転すると51を吸着したまま52
は引き上げられるので、制御棒は引き抜かれ、58を逆
回転すると制御棒は挿入される。そしてS任意の位置で
60の給電を停止すると、52から51は切離され、制
御棒は自由落下にて挿入され、原子炉は緊急停止する。
An electromagnet 60 composed of a cylindrical coil 53 and a magnetic flux guide member 54 is attached to the outside of 51 and 52. 60 is longer than the drive stroke S of the control rod.
The separating surface 59 of the and 52 is accommodated in the magnetic field of 60 over the entire area of S. Therefore, when power is supplied to 60, 51 and 52 are adsorbed, and when 58 is rotated in the forward direction, 51 is adsorbed and 52
Is pulled up, the control rod is pulled out, and when 58 is rotated in the reverse direction, the control rod is inserted. Then, when the power supply of 60 is stopped at an arbitrary position of S, 52 to 51 are separated, the control rod is inserted by free fall, and the reactor is emergency stopped.

【0006】[0006]

【発明が解決しようとする課題】このように、この型式
の制御棒駆動装置は、現行発電用原子炉の制御棒駆動装
置に比べ、制御棒切離し部に機構とか弁を伴はない為、
簡素で信頼性が高い制御棒駆動装置であるが、現行発電
用原子炉の制御棒駆動装置と同様、電気回路からの信号
を受けて作動する方式で、受動的に作動する機能は持っ
ていない。
As described above, the control rod drive device of this type has no mechanism or valve in the control rod disconnection portion as compared with the control rod drive device of the existing nuclear reactor for power generation.
Although it is a simple and highly reliable control rod drive device, like the control rod drive device of the current nuclear reactor for power generation, it operates by receiving a signal from an electric circuit and does not have a passive operation function. .

【0007】又、配管破断事故等で、水位が低下すると
最悪の場合炉心冷却機能が喪失し、炉心溶融事故にな
る。従って水位低下は早急に検出し、即座に原子炉を停
止する事が絶対条件であり、例え電気回路に故障が生じ
ても受動的に作動する設備が要望される。
Further, when the water level is lowered due to a pipe breakage or the like, in the worst case, the core cooling function is lost, resulting in a core melting accident. Therefore, the absolute condition is to detect the water level drop immediately and immediately stop the reactor, and there is a demand for equipment that operates passively even if a failure occurs in the electric circuit.

【0008】特に小型炉では、安全性確保とコスト削減
の要望から、自然循環型で、原子炉に接続する配管を最
小にする事から充填系を削除する事も有るので、運転時
変動幅が大きい水位計だけで対応せざるを得ない状況で
あるから、安全性を保障する多様性の面からも受動的炉
停止装置は不可欠となる。
In particular, in the case of a small reactor, in order to secure safety and reduce costs, the filling system may be deleted in order to minimize the piping connected to the nuclear reactor, so that the fluctuation range during operation may be small. Since there is no choice but to deal with large water level gauges, a passive reactor shutdown device is indispensable from the viewpoint of diversity to ensure safety.

【0009】[0009]

【課題を解決するための手段】本発明は、制御棒ストロ
ークが約1500mm又はそれ以下の軽水型原子炉の受動的炉
停止機構に関する。即ち、本発明は、制御棒の全ストロ
ークが磁気回路内に収まる筒状の電磁石と、その中を貫
通し、吸着部に温度感知合金を挟んだ上下の2本の導磁
軸から成る炉停止機構を、自然循環冷却が出来る様、原
子炉運転水位下に没して配置し、電磁石部分が水面上に
露出するような異常事象が発生すると、電磁石コイルの熱
で温度感知合金の温度を上昇せしめて吸着力を低下さ
せ、制御棒を吊り下げた下部導磁軸を切離すことからな
る原子炉の制御棒駆動機構である。
SUMMARY OF THE INVENTION The present invention is directed to a passive shutdown mechanism for a light water nuclear reactor having a control rod stroke of about 1500 mm or less. That is, the present invention is a furnace stop consisting of a tubular electromagnet in which the entire stroke of the control rod is contained in the magnetic circuit, and two upper and lower magnetic conducting shafts that penetrate the electromagnet and sandwich the temperature sensing alloy in the adsorption part. The mechanism is placed under the reactor operating water level so that it can be cooled by natural circulation. When an abnormal event occurs such that the electromagnet part is exposed above the water surface, the temperature of the temperature sensing alloy rises due to the heat of the electromagnet coil. It is a control rod drive mechanism of a nuclear reactor, which is composed of at least reducing the attraction force and separating the lower magnetic pole shaft on which the control rod is suspended.

【0010】より詳しくは、本発明は、吸着接合した上
部及び下部2本の導磁軸から成る制御棒切離し機構を具
備し、前記上部の軸が駆動機構の駆動軸に、下部の軸が
原子炉制御棒に結合された原子炉の制御棒駆動機構に関
するものであり、その特徴は、前記駆動軸の吸着面に、
高温になると磁気飽和値が低下する温度感知合金を挟み
込み、これにより温度が異常上昇すると受動的に吸着面
を切離す機能を具備した機構を設け、コイル下端部から
上端部に抜ける流路を設けて原子炉冷却水を通す事によ
りコイル部の発熱を自然循環で冷却すると共に、この機
構の冷却水出口を原子炉の安全水位直下に配置し、原子
炉の水位が安全水位以下に低下した時、前記冷却流出口
が水面上に露出する事により、コイルの自然循環冷却機
能を喪失せしめて前記温度感知合金の温度を上昇させて
下部の軸を切離し、原子炉水位低で受動的に上下部の導
磁軸を切離し、制御棒を炉心に挿入し、原子炉を受動的
に停止せしめる機構である。
More specifically, the present invention comprises a control rod separating mechanism composed of two magnetically conductive shafts, an upper and a lower magnetically adsorbed shaft, wherein the upper shaft is the drive shaft of the drive mechanism and the lower shaft is the atomic shaft. The present invention relates to a control rod drive mechanism of a nuclear reactor connected to a reactor control rod, the feature of which is that the attraction surface of the drive shaft has:
A temperature-sensing alloy whose magnetic saturation value decreases at high temperatures is sandwiched, and a mechanism is provided that has a function to passively separate the adsorption surface when the temperature rises abnormally, and a flow path that leads from the coil lower end to the upper end is provided. When the cooling water of this mechanism is cooled by natural circulation by passing the reactor cooling water through it, and the cooling water outlet of this mechanism is located just below the safe water level of the reactor, the water level of the reactor drops below the safe water level. When the cooling outlet is exposed on the water surface, the natural circulation cooling function of the coil is lost, the temperature of the temperature sensing alloy is increased, and the lower shaft is cut off. This is a mechanism that cuts off the magnetism axis and inserts the control rod into the core to passively stop the reactor.

【0011】[0011]

【発明の実施の形態】(停止機構の構造)図1に、本発
明の受動的原子炉停止機構を組込んだ後備原子炉停止装
置の実施例を示す。1は下部導磁軸、2は上部導磁軸で
ある。1の下部には案内管3を介し制御棒に結合し、2
の上部には駆動ねじ軸4と結合し、4はボールナット5
にかみ合い、5はローター6に直結している。6の外側
にはステーター7が取り付けられ、6と併せて電気モー
ター8を形成する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS (Structure of Shutdown Mechanism) FIG. 1 shows an embodiment of a backup reactor shutdown device incorporating a passive reactor shutdown mechanism of the present invention. Reference numeral 1 is a lower magnetic axis, and 2 is an upper magnetic axis. The lower part of 1 is connected to the control rod through the guide tube 3, and 2
Is connected to the drive screw shaft 4 on the upper part of the
The meshing 5 is directly connected to the rotor 6. A stator 7 is attached to the outside of 6 and together with 6 forms an electric motor 8.

【0012】1と2の外側には筒状のコイル9と磁束案
内部材10で構成する電磁石11が取り付けられる。1
1は制御棒の駆動ストロークSより長尺で、1と2の切
離し面12をS全域に渡り、11の磁界内に収容してい
る。従って、11に給電すると1と2は吸着され、この
状態で8を正回転すると1を吸着したまま2は引き上げ
られ、制御棒は引き抜かれ、8を逆回転すると制御棒は
挿入される。そしてS任意の位置で11の給電を停止す
ると、2から1は切離され、制御棒は自由落下にて炉心
に挿入され、原子炉は緊急停止する。ここまでの作動原
理は引用した特開平11−30683号公報の実施例と
同様である。
An electromagnet 11 composed of a cylindrical coil 9 and a magnetic flux guide member 10 is attached to the outside of 1 and 2. 1
Reference numeral 1 is longer than the drive stroke S of the control rod, and the separation surfaces 12 of 1 and 2 are accommodated in the magnetic field of 11 over the entire area of S. Therefore, when power is supplied to 11, 1 and 2 are adsorbed, in this state, when 8 is rotated normally, 2 is pulled up while 1 is adsorbed, the control rod is pulled out, and when 8 is rotated reversely, the control rod is inserted. Then, when the power supply to 11 is stopped at an arbitrary position of S, 2 to 1 are separated, the control rod is inserted into the core by free fall, and the reactor is stopped urgently. The operation principle up to this point is the same as that of the embodiment disclosed in Japanese Patent Laid-Open No. 11-30683.

【0013】上部電気モーター8の廻りを駆動機構1
3、下部の電磁石11の廻りを受動的原子炉停止機構14
とすると、本発明は14に係わるもので、14を構成す
る下部導磁軸1の上端又は上部導磁軸2の下端に温度感
知合金15を組み込むと共に、コイル9を冷却するパス
として磁束案内部材10の下部に複数の下部冷却水孔1
6−1、及び上部に複数の上部冷却水孔16−2を設
け、これら原子炉停止機構14を、下部に前記冷却パスの
出口となる複数の冷却水出口孔16−3を加工した適正
な長さの案内管17を介して駆動機構13と連結したもの
である。
A drive mechanism 1 is provided around the upper electric motor 8.
3. Passive reactor shutdown mechanism 14 around the lower electromagnet 11
Then, the present invention relates to 14, in which the temperature-sensitive alloy 15 is incorporated into the upper end of the lower magnetic-conducting shaft 1 or the lower end of the upper magnetic-conducting shaft 2 constituting the magnetic flux guiding member 14 as a path for cooling the coil 9. Multiple lower cooling water holes 1 at the bottom of 10
6-1 and a plurality of upper cooling water holes 16-2 are provided in the upper part, and these reactor shutdown mechanism 14 is processed in the lower part with a plurality of cooling water outlet holes 16-3 serving as outlets of the cooling path. It is connected to the drive mechanism 13 via a guide tube 17 having a length.

【0014】図2は原子炉停止機構14の部分の詳細を
示したものである。9は、例えばインコネルとかオース
テナイト系ステンレス鋼の様な非磁性材で成るコイルボ
ビン9−1と、無機絶縁ケーブルを巻いたコイル9−2
及びケーブルを引き出すリード線保護管9−3及び9−
1を密封するキャン9−4で構成する。また1、2、及
び10、は、例えばマルテンサイト系ステンレス鋼の様
な磁性材で構成する。
FIG. 2 shows the details of the reactor shutdown mechanism 14. Reference numeral 9 denotes a coil bobbin 9-1 made of a non-magnetic material such as Inconel or austenitic stainless steel, and a coil 9-2 wound with an inorganic insulated cable.
And lead wire protection tubes 9-3 and 9- for pulling out the cable
It is composed of a can 9-4 for sealing 1. Further, 1, 2, and 10 are composed of a magnetic material such as martensitic stainless steel.

【0015】15は、原子炉通常運転温度を超える温度
で磁気飽和値が急落する、ニッケルとかニッケルー鉄合
金を用いる。例えば通常運転温度230℃の熱供給炉の場
合、図3に示す様に300℃を超えた当たりで磁気飽和値
が急落するニッケルを用いる。
As the material 15, nickel or a nickel-iron alloy whose magnetic saturation value drops sharply at a temperature exceeding the normal operating temperature of the reactor is used. For example, in the case of a heat supply furnace with a normal operating temperature of 230 ° C., nickel whose magnetic saturation value drops sharply when the temperature exceeds 300 ° C. as shown in FIG. 3 is used.

【0016】尚、9−2のコイル導線は、一般的には銅
を用いるが、温度感知合金15の温度応答性を高める目
的で、銅―ニッケル合金など電気抵抗の大きい材料を使
う事も出来る。これにより、水位低から原子炉停止まで
の時間を短縮する事が出来るので、比較的口径の大きい
配管破断事故を想定する場合に適用する。
The coil conductor 9-2 is generally made of copper, but a material having a large electric resistance such as a copper-nickel alloy may be used for the purpose of improving the temperature response of the temperature sensing alloy 15. . As a result, the time from low water level to reactor shutdown can be shortened, so it is applied when a pipe breakage accident with a relatively large diameter is assumed.

【0017】図4及び図5は、本発明の受動的原子炉停
止機構を組込んだ制御棒駆動機構を小型炉に組込んだ例
を示す。この炉は、出力100Mwtの一体型自然循環
炉で、循環ループ、充填系等一切無く、原子炉容器の貫
通配管を最小限にしたものである。
4 and 5 show an example in which a control rod drive mechanism incorporating the passive reactor shutdown mechanism of the present invention is incorporated in a small reactor. This furnace is an integrated natural circulation furnace with an output of 100 Mwt, and has no circulation loop, filling system, etc., and minimizes the through piping of the reactor vessel.

【0018】図4で左半分(a)が原子炉停止状態を示
し、右半分(b)が原子炉運転状態を示す。また、図5
は例えば安全弁系の配管が破損する等して漏れが発生
し、原子炉水位が異常に低下した時、受動的原子炉停止
機構が作動し、原子炉が停止した状態を示す。
In FIG. 4, the left half (a) shows the reactor shutdown state, and the right half (b) shows the reactor operating state. Also, FIG.
Indicates a state in which the passive reactor shutdown mechanism is activated and the reactor is shut down when the reactor water level is abnormally lowered due to leakage such as damage to the piping of the safety valve system.

【0019】図4及び図5で、21は原子炉容器、22
は原子炉容器上蓋で、21の中に原子燃料から成る炉心
23、23を支持する炉内構造物24、炉心燃料の浮き
上がりを防止したり制御棒を案内規制する炉心上部機構
25、及び蒸気発生器26が組込まれる。
In FIGS. 4 and 5, reference numeral 21 denotes a reactor vessel, 22
Reference numeral denotes a reactor vessel upper lid, in which a core 23 composed of a nuclear fuel, a core internal structure 24 for supporting the core 23, an upper core mechanism 25 for preventing the core fuel from floating and guiding and controlling the control rod, and steam generation The container 26 is incorporated.

【0020】(停止機構の操作)原子炉の制御は、制御
棒27を炉心23に挿入又は引き抜く事により行うが、
安全性確保の要求から27は駆動原理の異なる2種の駆動
装置で駆動される。一つは原子炉の出力を制御する主制
御棒駆動装置、もう一つは本発明に係わる後備炉停止装
置で、夫々複数体設置されるが、図4及び図5には後者
を示している。
(Operation of Stopping Mechanism) The reactor is controlled by inserting or withdrawing the control rod 27 into or from the core 23.
27 is driven by two types of drive devices with different drive principles in order to ensure safety. One is a main control rod drive device for controlling the output of the nuclear reactor, and the other is a backup reactor stop device according to the present invention. A plurality of units are installed, respectively, and the latter is shown in FIGS. 4 and 5. .

【0021】図4中、13が駆動機構、14が炉停止機
構、12が切離し部である。また、28は運転前水位、
29は運転中水位である。前述のように、この炉には冷
却水の充填系が無いため、運転温度により、水位が大き
く変化する。しかながら炉停止機構14は原子炉が正常
な運転状態では常に水中に没する様、水位28の直下に
配置されているので、原子炉起動に際し、後備炉停止系
の制御棒は総て上限まで引き抜かれ原子炉運転中上限で
保持されるが、14は常に水中にあり、冷却が保証され
ている。
In FIG. 4, 13 is a driving mechanism, 14 is a furnace stopping mechanism, and 12 is a separating part. 28 is the water level before operation,
29 is the water level during operation. As described above, since this furnace does not have a cooling water filling system, the water level changes greatly depending on the operating temperature. However, since the reactor shutdown mechanism 14 is arranged immediately below the water level 28 so that it is always submerged in water when the reactor is in a normal operating state, at the time of reactor startup, all control rods in the post-shutdown system will reach the upper limit. Although pulled out and held at the upper limit during reactor operation, 14 is always in water and cooling is guaranteed.

【0022】原子炉運転中、万一安全弁などの小口径配
管破断事故等により、水位が低下した場合は、水位計等
の手段で異常水位を検出し、原子炉停止機構14の電源
を切り制御棒27を炉心に挿入、原子炉を停止するが、
検出器又は制御系の電気回路が故障した場合を想定する
と、水位は更に低下し、最悪の場合炉心が破損する事故
に至る。しかし、水位が図5に示す様に、14の冷却パ
ス出口が水面上に露出する異常水位30まで下がると、
14の自然循環冷却が断たれ、内部温度が上昇し、温度
感知合金15の温度も上昇するので、下部導磁軸1と上
部導磁軸2を吸着する磁束密度が低下し、1は切離さ
れ、原子炉は停止する。
If the water level drops due to accidents such as breakage of a small-diameter pipe such as a safety valve during operation of the reactor, an abnormal water level is detected by means such as a water level gauge, and the reactor shutdown mechanism 14 is powered off and controlled. Insert rod 27 into the core and shut down the reactor,
Assuming a failure of the detector or the electric circuit of the control system, the water level will further drop, and in the worst case, the core will be damaged. However, as shown in FIG. 5, when the cooling path outlet 14 is lowered to the abnormal water level 30 where it is exposed on the water surface,
Since the natural circulation cooling of 14 is cut off, the internal temperature rises, and the temperature of the temperature sensing alloy 15 also rises, the magnetic flux density for adsorbing the lower magnetic pole 1 and the upper magnetic pole 2 decreases, and 1 is separated. And the reactor shuts down.

【0023】[0023]

【発明の効果】このように本発明による受動的原子炉停
止機構は、異常検出の手段に頼る事なく、危険水位にな
る前に受動的に原子炉を停止する事が出来る。図6に原
子炉出力100Mwt、出口温度230℃、温度感知合
金15にニッケルを用いた時の解析例を示す。配管破断
事故が生じると水位が下がり、異常水位から感知合金の
温度が急上昇し、これに伴い制御棒を吊り下げている導
磁軸の吸着力が急低下するので、受動的に軸を切離す。
これにより危険水位に達する十分前に原子炉を停止する
事が示された。
As described above, the passive reactor shutdown mechanism according to the present invention can passively shut down the reactor before reaching the critical water level without relying on the means for detecting an abnormality. FIG. 6 shows an example of analysis when the reactor output is 100 Mwt, the outlet temperature is 230 ° C., and nickel is used for the temperature sensing alloy 15. If a pipe breakage accident occurs, the water level will drop, and the temperature of the sensing alloy will rise sharply from the abnormal water level, which will cause a sharp drop in the attraction force of the magnetic shaft that suspends the control rod. .
This indicated that the reactor would be shut down well before the critical water level was reached.

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

【図1】 本発明に係わる受動的原子炉停止機構を組込
んだ後備炉停止装置の縦断面図である。
FIG. 1 is a vertical cross-sectional view of a post-reactor shutdown device incorporating a passive reactor shutdown mechanism according to the present invention.

【図2】 本発明に係わる受動的原子炉停止機構の詳細
を示す縦断面図である。
FIG. 2 is a vertical sectional view showing details of a passive reactor shutdown mechanism according to the present invention.

【図3】 ニッケルの飽和磁束密度と温度との関係を示
す図である。
FIG. 3 is a diagram showing a relationship between saturation magnetic flux density of nickel and temperature.

【図4】 本発明の受動的原子炉停止機構を配置した原
子炉縦断面図である。
FIG. 4 is a vertical sectional view of a reactor in which a passive reactor shutdown mechanism of the present invention is arranged.

【図5】 図4における冷却水出口孔が水面上に露出し
た場合を示す図である。
5 is a diagram showing a case where a cooling water outlet hole in FIG. 4 is exposed on the water surface.

【図6】 本発明の受動的原子炉停止機構の効果を示す
解析例を示す図である。
FIG. 6 is a diagram showing an analysis example showing an effect of the passive reactor shutdown mechanism of the present invention.

【図7】 従来の炉停止機構を具備した原子炉制御棒駆
動装置を示す図である。
FIG. 7 is a diagram showing a reactor control rod driving device equipped with a conventional reactor shutdown mechanism.

【符号の説明】[Explanation of symbols]

1: 下部導磁軸 2: 上部導磁軸 3: 案内管 4: 駆動ネジ軸 5: ボールナット 6: ローター 7: ステーター 9: コイル 10: 磁束案内部材 12: 切離し面 15: 温度感知合金 16: 冷却水孔 17: 案内管 23: 炉心 26: 蒸気発生器 27: 制御棒 28: 運転前水位 29: 運転中水位 30: 異常水位 1: Lower magnetic axis 2: Upper magnetic axis 3: Guide tube 4: Drive screw shaft 5: Ball nut 6: rotor 7: Stator 9: coil 10: Magnetic flux guide member 12: Separation surface 15: Temperature sensing alloy 16: Cooling water hole 17: Guide tube 23: Core 26: Steam generator 27: Control rod 28: Water level before operation 29: Water level during operation 30: abnormal water level

───────────────────────────────────────────────────── フロントページの続き (72)発明者 頼経 勉 茨城県那珂郡東海村白方字白根2番地の4 日本原子力研究所東海研究所内 (72)発明者 今吉 祥 茨城県那珂郡東海村白方字白根2番地の4 日本原子力研究所東海研究所内 (72)発明者 西原 實 東京都港区西新橋2丁目21番2号 辰星技 研株式会社内 (72)発明者 坂巻 凡浩 東京都港区西新橋2丁目21番2号 辰星技 研株式会社内   ─────────────────────────────────────────────────── ─── Continued front page    (72) Inventor Tsutomu Yoritsuke             4 of 2 Shirane, Shikata, Tokai-mura, Naka-gun, Ibaraki Prefecture               Japan Atomic Energy Research Institute Tokai Research Center (72) Inventor Sho Imayoshi             4 of 2 Shirane, Shikata, Tokai-mura, Naka-gun, Ibaraki Prefecture               Japan Atomic Energy Research Institute Tokai Research Center (72) Inventor Minoru Nishihara             2-21-2 Nishishimbashi, Minato-ku, Tokyo             Ken Co., Ltd. (72) Inventor Norihiro Sakamaki             2-21-2 Nishishimbashi, Minato-ku, Tokyo             Ken Co., Ltd.

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】 制御棒の駆動全ストロークを磁気回路内
に入れるような、筒状のコイルと、その外側に配置し磁
束を案内する磁束案内部材と、その軸芯に配置し上下2
個に分離され吸着面で吸着接合した上部及び下部2本の
導磁軸から成る制御棒切離し機構を具備し、前記上部の
軸は駆動機構の駆動軸に、下部の軸は原子炉制御棒に結
合された制御棒駆動装置において、 前記駆動軸の吸着面に、高温になると磁気飽和値が低下
する温度感知合金を挟み込み、これにより温度が異常上
昇すると受動的に吸着面を切離す機能を具備した機構を
設け、 コイル下端部から上端部に抜ける流路を設けて原子炉冷
却水を通す事によりコイル部の発熱を自然循環で冷却す
る機構を設け、 この冷却機構の冷却水出口を原子炉の安全水位直下に配
置し、 原子炉の水位が安全水位以下に低下した時、前記冷却水
出口が水面上に露出する事により、コイルの自然循環冷
却機能を喪失せしめて前記温度感知合金の温度を上昇さ
せて下部の軸を切離すことにより、 原子炉水位低で受動的に上下部の導磁軸を切離し、制御
棒を炉心に挿入して原子炉を停止せしめることを特徴と
する受動的原子炉停止機構。
1. A tubular coil for placing the entire driving stroke of a control rod in a magnetic circuit, a magnetic flux guide member arranged outside the tubular coil for guiding magnetic flux, and a magnetic flux guide member arranged on the axial center of the tubular coil.
It is equipped with a control rod separating mechanism consisting of two magnetic upper and lower magnetic shafts that are separated into individual pieces and adsorbed and joined at the adsorption surface.The upper shaft is the drive shaft of the drive mechanism and the lower shaft is the reactor control rod. In the coupled control rod drive device, a temperature sensing alloy whose magnetic saturation value decreases when the temperature becomes high is sandwiched between the adsorption surface of the drive shaft, and when the temperature rises abnormally, the adsorption surface is passively separated. The cooling water outlet of this cooling mechanism is installed by providing a mechanism that cools the heat generation of the coil part by natural circulation by providing a flow path from the lower end of the coil to the upper end and passing the reactor cooling water. Of the temperature-sensing alloy, which is located just below the safety water level of the reactor, and when the water level of the reactor drops below the safe water level, the cooling water outlet is exposed above the water surface, causing the coil to lose its natural circulation cooling function. Up and down By separating the axes, reactor water level low passively disconnecting the upper and lower portions of the conductive magnetic axis, passive reactor shutdown mechanism, characterized in that allowed to shut down the reactor was inserted into the reactor core control rods.
【請求項2】 前記温度感知合金がニッケル又はニッケ
ル系合金である請求項1記載の受動的原子炉停止機構。
2. The passive reactor shutdown mechanism according to claim 1, wherein the temperature-sensitive alloy is nickel or a nickel-based alloy.
【請求項3】 前記受動的原子炉停止機構のコイル材に
は、一般的には導体に銅等電気抵抗の小さい材料を用い
るが、必要により、銅にニッケルなどを添加した電気抵
抗の大きい材料を用い、水位低から原子炉停止までの応
答性を高めた請求項1記載の受動的原子炉停止機構。
3. The coil material of the passive reactor shutdown mechanism is generally made of a material such as copper having a low electric resistance as a conductor, but if necessary, a material having a high electric resistance obtained by adding nickel or the like to copper. The passive reactor shutdown mechanism according to claim 1, wherein the responsiveness from the low water level to the shutdown of the reactor is enhanced by using.
JP2002068039A 2002-03-13 2002-03-13 Passive reactor shutdown mechanism Pending JP2003270375A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2002068039A JP2003270375A (en) 2002-03-13 2002-03-13 Passive reactor shutdown mechanism

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2002068039A JP2003270375A (en) 2002-03-13 2002-03-13 Passive reactor shutdown mechanism

Publications (1)

Publication Number Publication Date
JP2003270375A true JP2003270375A (en) 2003-09-25

Family

ID=29199232

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2002068039A Pending JP2003270375A (en) 2002-03-13 2002-03-13 Passive reactor shutdown mechanism

Country Status (1)

Country Link
JP (1) JP2003270375A (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008020405A (en) * 2006-07-14 2008-01-31 Japan Atom Power Co Ltd:The Control rod drive mechanism
KR101129463B1 (en) 2010-12-27 2012-03-29 주식회사 우진 The test facility for the cooling performance of the cedm coil
EP2441074A4 (en) * 2009-06-10 2016-07-27 Babcock & Wilcox Nuclear Operations Group Inc REGULATORY DRIVE MECHANISM FOR CORE REACTOR
CN106941014A (en) * 2015-11-23 2017-07-11 法国原子能源和替代能源委员会 It is equipped with the passive triggering type safety device of the nuclear reactor of damper
CN107068213A (en) * 2015-11-23 2017-08-18 法国原子能源和替代能源委员会 Nuclear reactor passive triggering type safety device when being reduced extremely for amount of coolant
CN109346195A (en) * 2018-11-12 2019-02-15 中国原子能科学研究院 A deep pool type heating stack control rod drive mechanism
KR20210082167A (en) * 2018-09-25 2021-07-02 뉴스케일 파워, 엘엘씨 Control rod drive mechanism with heat pipe cooling
JP2022023345A (en) * 2020-07-27 2022-02-08 三菱重工業株式会社 Control rod drive device and nuclear reactor
CN114141395A (en) * 2021-11-30 2022-03-04 上海第一机床厂有限公司 Sealed shell device and control rod drive mechanism

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008020405A (en) * 2006-07-14 2008-01-31 Japan Atom Power Co Ltd:The Control rod drive mechanism
EP2441074A4 (en) * 2009-06-10 2016-07-27 Babcock & Wilcox Nuclear Operations Group Inc REGULATORY DRIVE MECHANISM FOR CORE REACTOR
KR101129463B1 (en) 2010-12-27 2012-03-29 주식회사 우진 The test facility for the cooling performance of the cedm coil
CN106941014B (en) * 2015-11-23 2021-11-02 法国原子能源和替代能源委员会 Passive Triggered Safety Devices for Nuclear Reactors with Dampers
CN106941014A (en) * 2015-11-23 2017-07-11 法国原子能源和替代能源委员会 It is equipped with the passive triggering type safety device of the nuclear reactor of damper
CN107068213A (en) * 2015-11-23 2017-08-18 法国原子能源和替代能源委员会 Nuclear reactor passive triggering type safety device when being reduced extremely for amount of coolant
CN107068213B (en) * 2015-11-23 2021-11-02 法国原子能源和替代能源委员会 Passive-triggered safety device for nuclear reactors when the amount of coolant is abnormally reduced
KR20210082167A (en) * 2018-09-25 2021-07-02 뉴스케일 파워, 엘엘씨 Control rod drive mechanism with heat pipe cooling
KR102607783B1 (en) * 2018-09-25 2023-11-30 뉴스케일 파워, 엘엘씨 Control rod drive mechanism with heat pipe cooling
CN109346195A (en) * 2018-11-12 2019-02-15 中国原子能科学研究院 A deep pool type heating stack control rod drive mechanism
JP2022023345A (en) * 2020-07-27 2022-02-08 三菱重工業株式会社 Control rod drive device and nuclear reactor
JP7399044B2 (en) 2020-07-27 2023-12-15 三菱重工業株式会社 Control rod drives and reactors
CN114141395A (en) * 2021-11-30 2022-03-04 上海第一机床厂有限公司 Sealed shell device and control rod drive mechanism

Similar Documents

Publication Publication Date Title
JP5964058B2 (en) Superconducting magnet assembly
JP2003270375A (en) Passive reactor shutdown mechanism
JP6586502B2 (en) How to supply backup power
JP4733989B2 (en) Kenting monitoring control system and operation method thereof
CN103057682B (en) Underwater vehicle protection device and method based on depth control
JPH0122915B2 (en)
US5333160A (en) Control rod position transmitter
JPS6412352B2 (en)
JP2869294B2 (en) Control rod drop position detection device for self-actuated furnace shutdown mechanism
CN113390938A (en) Safety protection type liquid metal oxygen sensor
US4582675A (en) Magnetic switch for reactor control rod
KR100881616B1 (en) Controllable position sensor for life expectancy
JPS6319593A (en) Self-operation type control-rod drive mechanism
JPH049271B2 (en)
JPH0886898A (en) Control rod position detector
EP2093771A1 (en) Temperature sensitive safety device for systems susceptible of overheating
CN117223066A (en) Nuclear reactor protection device
JPS63290991A (en) Shutdown device for nuclear reactor
JPS6391592A (en) Self-operated type control-rod drive mechanism
JPH01206289A (en) Shut-down device
JPH068883B2 (en) Self-actuated control rod drive mechanism
JP2912973B2 (en) Stopper for fast breeder reactor
JP2007163513A (en) Control rod drive device, test method and test device, inspection device, storage method and storage device, and torque transmission device
JPH04104088A (en) Apparatus for shutting down nuclear reactor
CN120357377A (en) Cable joint for ship and fault processing method

Legal Events

Date Code Title Description
A711 Notification of change in applicant

Free format text: JAPANESE INTERMEDIATE CODE: A712

Effective date: 20060223

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20060705

A02 Decision of refusal

Free format text: JAPANESE INTERMEDIATE CODE: A02

Effective date: 20061031