JP2883701B2 - Reactor internal pump - Google Patents
Reactor internal pumpInfo
- Publication number
- JP2883701B2 JP2883701B2 JP2241256A JP24125690A JP2883701B2 JP 2883701 B2 JP2883701 B2 JP 2883701B2 JP 2241256 A JP2241256 A JP 2241256A JP 24125690 A JP24125690 A JP 24125690A JP 2883701 B2 JP2883701 B2 JP 2883701B2
- Authority
- JP
- Japan
- Prior art keywords
- internal pump
- pressure vessel
- reactor
- motor
- reactor pressure
- 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.)
- Expired - Lifetime
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
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、原子炉圧力容器に原子炉圧力容器内の冷却
流体を循環させる原子炉のインターナルポンプに関す
る。Description: Object of the Invention (Industrial application field) The present invention relates to an internal pump of a reactor for circulating a cooling fluid in a reactor pressure vessel to a reactor pressure vessel.
（従来の技術） 原子炉圧力容器１の底部に複数のインターナルポンプ
２が設けられた原子炉の部分破断斜視図を示す第４図
と、同図の部分破断縦断面図を示す第５図において、イ
ンターナルポンプ２は、原子炉圧力容器１の底部の外壁
の周りに、上端を原子炉圧力容器１の内側に突き出して
詳細後述するように縦に気密に貫設され、第５図の矢印
３で示すように、原子炉圧力容器１の内部の炉水を上方
から吸い込んで、矢印４のように下方にそれぞれ吐出す
ることで、原子炉圧力容器１の内部中央に収納された炉
心５を外側から所定の温度に冷却する。そして、このイ
ンターナルポンプ２は、通常８個又は10個が等間隔に配
設されている。(Prior Art) FIG. 4 is a partially cutaway perspective view of a reactor in which a plurality of internal pumps 2 are provided at the bottom of a reactor pressure vessel 1, and FIG. 5 is a partially cutaway longitudinal sectional view of FIG. In FIG. 5, the internal pump 2 extends vertically and airtightly around the outer wall at the bottom of the reactor pressure vessel 1 with its upper end protruding inside the reactor pressure vessel 1 as described later in detail. As indicated by an arrow 3, the reactor water inside the reactor pressure vessel 1 is sucked in from above and discharged downward as indicated by an arrow 4, whereby the reactor core 5 housed in the center of the reactor pressure vessel 1 is taken up. Is cooled from the outside to a predetermined temperature. Usually, eight or ten internal pumps 2 are arranged at equal intervals.
次に、第６図は、第１〜２図のインターナルポンプ２
の縦断面詳細図である。Next, FIG. 6 shows the internal pump 2 shown in FIGS.
FIG.
同図において、縦長のインターナルポンプ２は、原子
炉圧力容器１の底部側面の内部に突き出た後述するイン
ペラ部６と、原子炉圧力容器１の底部側面から下方に筒
状に突き出て原子炉圧力容器１と一体に構成されたモー
タ収納筒部1aの内部に挿着されて、上述の主インペラ部
６を駆動する詳細後述する水中モータ部７と、モータ収
納筒部1aの下端内部に挿着された逆転防止装置８で構成
されている。In the figure, a vertically long internal pump 2 has an impeller section 6 which will be described later protruding into the bottom side surface of the reactor pressure vessel 1, and a cylindrical shape which protrudes downward from the bottom side face of the reactor pressure vessel 1 to form a reactor. A submersible motor unit 7, which will be described later, which is inserted into a motor housing tube portion 1a integrally formed with the pressure vessel 1 and drives the above-mentioned main impeller unit 6, and is inserted inside the lower end of the motor housing tube portion 1a It is composed of the reverse rotation prevention device 8 worn.
このうち、主インペラ部６は、下半が水中モータ部７
内に嵌挿されたポンプ軸９の上端に嵌合固定された主イ
ンペラ10と、この主インペラ10の外周にこの主インペラ
10と同軸に設けられ外周と下端が原子炉圧力容器１に固
定された案内羽根11で構成されている。The lower half of the main impeller 6 is a submersible motor 7
A main impeller 10 fitted and fixed to the upper end of the pump shaft 9 inserted therein, and the main impeller
The guide vanes 11 are provided coaxially with the outer periphery 10 and fixed at their outer periphery and lower end to the reactor pressure vessel 1.
また、水中モータ部７は、軸心に貫設された上述のポ
ンプ軸９の下半に図示しないキーを介して挿着・固定さ
れた管状のモータ軸13と、このモータ軸13の外周に嵌挿
された回転子14と、モータ収納筒部1aの内周に嵌挿・固
定されたモータケーシング15と、このモータケーシング
15の内周に嵌挿・固定された固定子16で構成されてい
る。The underwater motor unit 7 has a tubular motor shaft 13 inserted and fixed via a key (not shown) in the lower half of the above-described pump shaft 9 penetrating the shaft. A rotor 14 inserted and inserted, a motor casing 15 inserted and fixed to the inner periphery of the motor housing cylindrical portion 1a, and the motor casing
It is composed of a stator 16 fitted and fixed to the inner periphery of 15.
そして、このうちモータ軸13の上端外周は、モータケ
ーシング15の上端内周に嵌挿固定された上ラジアル軸受
18で、同じく、モータ軸13の下端外周はモータケーシン
グ15の下端内周に嵌挿された下ラジアル軸受19で、それ
ぞれラジアル方向を支承されている。The outer periphery of the upper end of the motor shaft 13 is an upper radial bearing fitted and fixed to the inner periphery of the upper end of the motor casing 15.
Similarly, at the lower end of the motor shaft 13, a lower radial bearing 19 inserted into the inner periphery of the lower end of the motor casing 15 is supported in the radial direction.
一方、モータ軸13の下端には、インペラ17の上端が固
定され、このインペラ17の上面と対向するモータケーシ
ング15の下面には、上スラスト軸受20がそれぞれ設けら
れ、又、モータ収納筒部1aの下端に図示しないシールを
介して嵌合・固定された筒蓋1bの上面とインペラ10の下
面間には下スラスト軸受21がそれぞれ設けられて、主イ
ンペラ10による第５図の矢印３方向への炉水の吐出によ
る反力は、上スラスト軸受20で、また、静止時のポンプ
軸９、回転子14や主インペラ10、インペラ17などの荷重
は、下スラスト軸受21でそれぞれ支承されている。On the other hand, an upper end of an impeller 17 is fixed to a lower end of the motor shaft 13, and an upper thrust bearing 20 is provided on a lower surface of the motor casing 15 facing the upper surface of the impeller 17, respectively. Lower thrust bearings 21 are provided between the upper surface of the cylindrical lid 1b and the lower surface of the impeller 10 fitted and fixed via a seal (not shown) at the lower end of the main impeller 10, and the main impeller 10 moves in the direction of arrow 3 in FIG. The reaction force caused by the discharge of the reactor water is supported by the upper thrust bearing 20, and the load of the pump shaft 9, the rotor 14, the main impeller 10, the impeller 17 and the like at rest is supported by the lower thrust bearing 21. .
更に、筒蓋1bの中心部には、下側から下カバー23が図
示しないシールを介して挿着・固定され、これら筒蓋８
及び下カバー23とインペラ17との間には中心部にインペ
ラ吸込口31が形成されている。Further, a lower cover 23 is inserted and fixed from below into a central portion of the cylindrical lid 1b through a seal (not shown).
An impeller inlet 31 is formed at the center between the lower cover 23 and the impeller 17.
一方、モータケーシング15の上端上側には、モータ上
部室27が形成され、モータ収納筒部1aの上端にはモータ
上部室27に連通する貫通穴が設けられ、この貫通穴の外
側のめねじには図示しない小径の継手が螺合されて、こ
の継手には内部に高圧のパージ水を注入する配管12が接
続されている。On the other hand, a motor upper chamber 27 is formed on the upper side of the upper end of the motor casing 15, and a through hole communicating with the motor upper chamber 27 is provided on the upper end of the motor housing cylindrical portion 1a. Is screwed with a small-diameter joint (not shown), and a pipe 12 for injecting high-pressure purge water into the joint is connected to the joint.
また、上記小径の継手の下方にもやや大径の継手28a
が螺合され、この継手28aには配管28の片側が接続さ
れ、この配管28の他側は熱交換器29の片側に接続され、
この熱交換器29の他側には配管30の片側が接続され、こ
の配管30の他側はインペラ吸込口31の側面のモータ収納
筒1aに螺合されたやや大径の継手30aに接続されてい
る。Also, a slightly larger joint 28a is located below the smaller joint.
Is connected to one side of a pipe 28 to the joint 28a, and the other side of the pipe 28 is connected to one side of a heat exchanger 29,
One side of a pipe 30 is connected to the other side of the heat exchanger 29, and the other side of the pipe 30 is connected to a slightly large-diameter joint 30a screwed into the motor housing 1a on the side of the impeller suction port 31. ing.
このような構成のインターナルポンプ２においては、
配管12から内部に高圧で注入されるパージ水で、水中モ
ータ部７の内部は原子炉容器１の内部とは完全に遮断さ
れ、熱交換器29から還流される冷却水で約40℃以下に冷
却される。In the internal pump 2 having such a configuration,
Purge water injected into the interior from the pipe 12 at high pressure, the interior of the underwater motor unit 7 is completely shut off from the interior of the reactor vessel 1, and the cooling water refluxed from the heat exchanger 29 reduces the temperature to about 40 ° C or less. Cooled.
また、下カバー23を気密に貫通して水中モータ部７に
供給される電源がもし切れても、主インペラ10は所定の
時間、所定の減速率（例えば、1/2回転数になるまでに
0.8秒以上）となるようにして、電源停電時の炉心５の
図示しない燃料棒の温度が急上昇しないように、回転部
分の慣性が大きく設計されている。Further, even if the power supplied to the underwater motor unit 7 through the lower cover 23 in an airtight manner is cut off, the main impeller 10 is kept at a predetermined deceleration rate for a predetermined period of time (for example, until the rotation speed becomes 1/2)
0.8 seconds or more), and the inertia of the rotating part is designed to be large so that the temperature of a fuel rod (not shown) of the reactor core 5 at the time of power failure does not suddenly rise.
そして、この減速率の検証作業は、インターナルポン
プ２の工場出荷試験ではできないので、稼働前の原子力
発電所で、原子炉圧力容器１に組込まれて各インターナ
ルポンプ２についてそれぞれ行なわれる。Since the verification of the deceleration rate cannot be performed by the factory shipment test of the internal pump 2, the internal pump 2 is installed in the reactor pressure vessel 1 and performed for each internal pump 2 at the nuclear power plant before operation.
（発明が解決しようとする課題） ところが、このように構成された原子炉の冷却装置に
おいては、シール部を減らすために、上述のように水中
モータ部７は原子炉圧力容器１と一体のモータ収納筒部
1aの内部に収納されていて、ポンプ軸９も同じく内部に
収納されている。そのため、ポンプ軸９の減衰回転数を
測るためには、モータ収納筒部1a又は原子炉圧力容器１
の内部に特殊な回転検出器を設けなければならないが、
すると、回転検出器の出力信号を取り出すためにシール
穴を増やさなくてはならないので、原子炉圧力容器１密
封の信頼性が低下する。(Problems to be Solved by the Invention) However, in the reactor cooling device thus configured, in order to reduce the number of seals, the underwater motor unit 7 is a motor integrated with the reactor pressure vessel 1 as described above. Storage tube
1a, and the pump shaft 9 is also housed inside. Therefore, in order to measure the damped rotation speed of the pump shaft 9, the motor housing cylinder 1a or the reactor pressure vessel 1 is required.
Must have a special rotation detector inside the
Then, in order to extract the output signal of the rotation detector, the number of seal holes must be increased, so that the reliability of sealing the reactor pressure vessel 1 is reduced.
そこで、本発明の目的は、原子炉圧力容器の信頼性を
損うことなく、電源切断後のインターナルポンプの回転
減衰特性を検証することのできる原子炉のインターナル
ポンプを得ることである。Therefore, an object of the present invention is to obtain an internal pump of a nuclear reactor capable of verifying the rotation damping characteristics of the internal pump after power is turned off without impairing the reliability of the reactor pressure vessel.
（課題を解決するための手段および作用） 本発明は、原子炉圧力容器にこの原子炉圧力容器内の
冷却流体を循環させるインターナルポンプにおいて、イ
ンターナルポンプの駆動電動機の電源側に、この電源切
断直後のインターナルポンプの回転数の低下率を検出す
る残留電圧検出部を設けることで、原子炉圧力容器の信
頼性を損うことなく、電源切断後のインターナルポンプ
の減衰特性を検証することのできる原子炉のインターン
ルポンプである。(Means and Actions for Solving the Problems) The present invention relates to an internal pump for circulating a cooling fluid in a reactor pressure vessel through a reactor pressure vessel. Providing a residual voltage detector that detects the rate of decrease in the number of rotations of the internal pump immediately after disconnection enables verification of the damping characteristics of the internal pump after power is cut off without reducing the reliability of the reactor pressure vessel It is an intern pump for a nuclear reactor.
（実施例） 以下、本発明の原子炉のインターナルポンプの一実施
例を図面を参照して説明する。(Embodiment) Hereinafter, an embodiment of an internal pump of a nuclear reactor according to the present invention will be described with reference to the drawings.
第１図は、本発明の原子炉のインターナルポンプを示
すブロック図である。FIG. 1 is a block diagram showing an internal pump of a nuclear reactor according to the present invention.
同図において、片側が高圧の三相電源に接続された遮
断器42の負荷側には、インターナルポンプ２の水中電動
機７が接続されている。In the figure, the underwater motor 7 of the internal pump 2 is connected to the load side of the circuit breaker 42 whose one side is connected to a high-voltage three-phase power supply.
更に、遮断器42の負荷側には、フィルタ38の片側が接
続され、このフィルタ38の他側にはパルス発振器39の入
力側が接続され、このパルス発振器の出力側には周波数
−電圧変換器（以下、F/V変換器という）40の入力側が
接続され、このF/V変換器42の出力側には記録計41が接
続されている。Further, one side of a filter 38 is connected to the load side of the circuit breaker 42, the input side of a pulse oscillator 39 is connected to the other side of the filter 38, and the frequency-voltage converter ( An input side of the F / V converter 40 is connected to the input side, and a recorder 41 is connected to an output side of the F / V converter 42.
なお、ここでフィルタ38は、電源が遮断されたときの
開閉サージによる高周波分のノイズによる電圧零点を除
いて、後述するパルス42との混同を防ぐためである。Here, the filter 38 is for preventing confusion with a pulse 42, which will be described later, except for a voltage zero point caused by high frequency noise due to switching surge when the power is cut off.
次に、第２図は、第１図のように遮断器42に水中電動
機７が接続された原子炉の冷却装置において、４極の水
中電動機７の電源側を遮断したときの、水中電動機７の
Ｕ相−Ｖ相間電圧35、Ｖ相−Ｗ相間電圧36とＷ相−Ｕ相
間電圧37の減衰状態を示すオシログラフで、同図及び第
３図のように、各相間電圧35,36,37は、水中電動機７が
１回転する毎に、水中電動機７の極数と同数だけ電圧０
点41を通過するので、４極ではそれぞれ４回通過する。Next, FIG. 2 shows the underwater motor 7 when the power supply side of the four-pole underwater motor 7 is cut off in the cooling device of the nuclear reactor in which the underwater motor 7 is connected to the circuit breaker 42 as shown in FIG. FIG. 3 is an oscillograph showing the attenuated state of the U-phase to V-phase voltage 35, the V-phase to W-phase voltage 36, and the W-phase to U-phase voltage 37, as shown in FIG. 37 is a voltage 0 equal to the number of poles of the underwater motor 7 every time the underwater motor 7 rotates once.
Since it passes through the point 41, it passes four times for each of the four poles.
そこで、本発明の原子炉の冷却装置においては、電源
が遮断された後の水中電動機７の相間電圧をフィルタ38
を介してパルス発振器39に入力して、電圧０点41におい
て第３図に示すようにパルス42を発生させて、F/V変換
器40に出力する。Therefore, in the cooling device for a nuclear reactor of the present invention, the inter-phase voltage of the underwater motor 7 after the power is cut off is filtered by the filter 38.
To generate a pulse 42 at the voltage 0 point 41 as shown in FIG. 3 and output it to the F / V converter 40.
すると、F/V変換器40ではこのパルス数をカウント
し、電圧に変換してアナログ信号に変えて記録計41に出
力し、記録計41ではこの電圧を回転速度に変換して表示
する。Then, the F / V converter 40 counts this pulse number, converts it into a voltage, converts it into an analog signal, and outputs it to the recorder 41. The recorder 41 converts this voltage into a rotational speed and displays it.
このように本発明の原子炉のインターナルポンプにお
いては、電源遮断時の水中電動機７の回転で発生する各
相の電圧の零点をそれぞれ検出して、パルスを発生させ
ることで、パルスの発生間隔の変化を分解能を上げて測
定することができるので、インターナルポンプの回転数
の減衰特性を精度よく検証することができる。As described above, in the internal pump of the nuclear reactor according to the present invention, the zero point of the voltage of each phase generated by the rotation of the underwater motor 7 when the power is turned off is detected, and the pulse is generated. Of the internal pump can be measured with higher resolution, so that the attenuation characteristic of the rotation speed of the internal pump can be verified with high accuracy.
なお、上記実施例においては、F/V変換器40でパルス4
2の発生頻度に比例した電圧に変換した例で説明した
が、第３図に示すパルス42の１回転当りの発生間隔43の
時間を直接測るようにしてもよい。Note that, in the above embodiment, the pulse 4 was output by the F / V converter 40.
Although the example has been described in which the voltage is converted into a voltage proportional to the frequency of occurrence of 2, the time of the generation interval 43 per one rotation of the pulse 42 shown in FIG. 3 may be directly measured.
また、上記実施例においては、パルス発振器39に入力
される電圧零点検出用の水中電動機７の誘起電圧は相間
電圧としたが、各相毎の端子相電圧としてもよい。In the above embodiment, the induced voltage of the underwater motor 7 for detecting the voltage zero point input to the pulse oscillator 39 is an inter-phase voltage, but may be a terminal phase voltage for each phase.
更に、回転数の変化の分解能を増やさなくてもよいと
きには、１相分だけ測定してもよい。Further, when it is not necessary to increase the resolution of the change in the number of rotations, measurement may be performed for only one phase.
以上、本発明によれば、原子炉圧力容器にこの原子炉
圧力容器内の冷却流体を循環させるインターナルポンプ
において、インターナルポンプの駆動電動機の電源側
に、この電源が切断された直後のインターナルポンプの
回転数の低下率を検出する残留電圧検出部を設けて、イ
ンターナルポンプの回転数を検出したので、原子炉圧力
容器の信頼性を損うことなく、電源切断後のインターナ
ルポンプの減衰特性を検証することのできる原子炉のイ
ンターナルポンプを得ることができる。As described above, according to the present invention, in the internal pump for circulating the cooling fluid in the reactor pressure vessel to the reactor pressure vessel, the power supply side of the drive motor of the internal pump is connected to the engine immediately after the power is cut off. A residual voltage detector that detects the rate of decrease in the rotation speed of the internal pump is provided to detect the rotation speed of the internal pump.Therefore, the internal pump after the power is turned off without impairing the reliability of the reactor pressure vessel It is possible to obtain an internal pump of a nuclear reactor capable of verifying the damping characteristics of the reactor.
第１図は本発明の原子炉のインターナルポンプの一実施
例を示すブロック図、第２図は第１図において電源が遮
断されたときのインターナルポンプの駆動電動機の誘起
電圧の推移を示すオシログラフ、第３図は本発明の原子
炉のインターナルポンプの作用を示す図、第４図は本発
明の原子炉のインターナルポンプが適用される原子炉の
斜視図、第５図は第４図の部分破断縦断面図、第６図は
第５図の要部を示す縦断面拡大詳細図である。 １……原子炉圧力容器 ２……インターナルポンプ ７……水中電動機 39……パルス発振器 40……周波数−電圧変換器 42……パルスFIG. 1 is a block diagram showing an embodiment of an internal pump of a nuclear reactor according to the present invention, and FIG. 2 shows a transition of an induced voltage of a drive motor of the internal pump when power is cut off in FIG. FIG. 3 is a diagram showing the operation of the internal pump of the nuclear reactor of the present invention, FIG. 4 is a perspective view of the nuclear reactor to which the internal pump of the nuclear reactor of the present invention is applied, and FIG. FIG. 4 is a partially broken longitudinal sectional view, and FIG. 6 is an enlarged detailed longitudinal sectional view showing a main part of FIG. 1 Reactor pressure vessel 2 Internal pump 7 Underwater motor 39 Pulse generator 40 Frequency-voltage converter 42 Pulse
───────────────────────────────────────────────────── フロントページの続き (72)発明者 須賀 和夫 神奈川県横浜市磯子区新杉田町８番地 株式会社東芝横浜事業所内 (72)発明者 薄 正司 神奈川県横浜市磯子区新杉田町８番地 株式会社東芝横浜事業所内 (56)参考文献 特開 昭63−208767（ＪＰ，Ａ) (58)調査した分野(Int.Cl.6，ＤＢ名) G21C 15/243 G01P 3/46 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Kazuo Suka 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Inside the Toshiba Yokohama Office (72) Inventor Seiji Hatsu 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Toshiba (56) References JP-A-63-208767 (JP, A) (58) Field surveyed (Int. Cl. 6 , DB name) G21C 15/243 G01P 3/46
Claims (1)
冷却流体を循環させるインターナルポンプにおいて、こ
のインターナルポンプの駆動電動機の電源側に、この電
源遮断直後の前記インターナルポンプの回転数の変化を
検出する残留電圧検出部を設けたことを特徴とする原子
炉のインターナルポンプ。1. An internal pump for circulating a cooling fluid in a reactor pressure vessel through a reactor pressure vessel, wherein a rotation of the internal pump immediately after the power is shut off is provided on a power supply side of a drive motor of the internal pump. An internal pump for a nuclear reactor, comprising a residual voltage detector for detecting a change in the number.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2241256A JP2883701B2 (en) | 1990-09-13 | 1990-09-13 | Reactor internal pump |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2241256A JP2883701B2 (en) | 1990-09-13 | 1990-09-13 | Reactor internal pump |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04121693A JPH04121693A (en) | 1992-04-22 |
| JP2883701B2 true JP2883701B2 (en) | 1999-04-19 |
Family
ID=17071538
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2241256A Expired - Lifetime JP2883701B2 (en) | 1990-09-13 | 1990-09-13 | Reactor internal pump |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2883701B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4820053B2 (en) * | 2003-12-25 | 2011-11-24 | 富士重工業株式会社 | Motor rotation stop detection device |
-
1990
- 1990-09-13 JP JP2241256A patent/JP2883701B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH04121693A (en) | 1992-04-22 |
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