JPH0651089A - Recirculation pump installed in nuclear reactor - Google Patents

Recirculation pump installed in nuclear reactor

Info

Publication number
JPH0651089A
JPH0651089A JP4206711A JP20671192A JPH0651089A JP H0651089 A JPH0651089 A JP H0651089A JP 4206711 A JP4206711 A JP 4206711A JP 20671192 A JP20671192 A JP 20671192A JP H0651089 A JPH0651089 A JP H0651089A
Authority
JP
Japan
Prior art keywords
pump
bearing
shaft
thrust
force
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
JP4206711A
Other languages
Japanese (ja)
Inventor
Akira Okada
明 岡田
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 JP4206711A priority Critical patent/JPH0651089A/en
Publication of JPH0651089A publication Critical patent/JPH0651089A/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
    • 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

Abstract

PURPOSE:To keep resolutions even in case a pump loses its driving force and relieve the core stability and the transient characteristics by using a rolling bearing to a bearing means which supports a shaft in the thrust direction. CONSTITUTION:A rolling bearing A consisting of rolling elements 24, inner and outer rings 25, 26, and a retainer 27 is furnished on the undersurface of a thrust disc 20 at the bottom of a shaft 10. The inner ring 25 rotates together with the disc 20, while the outer ring 26 fixed to the upper part of a motor cover 8 is at a standstill even while a pump is in opeeation. A raceway 28, 28 where the rolling elements 24 are in contact is formed in the circumferential direction on the mating surface of each ring 25, 26, and the rolling elements 24 are held by the retainer 27 on the outer ring 26 so that they can rotate freely while their positions remain unchanged. Thereby the thrust force applied to the shaft 10 is received by the bearing A, so that the rotational resistance is reduced to a great extent, and revolutions of the pump are kept with the voluntary circulation force as the drive motive. Accordingly the flow resistance of the impeller part is reduced to lead to enhancement of the rate of flow in natural circulation, which permits relieving of the core safety and transient characteristics when the pump loses its driving force.

Description

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

【0001】[0001]

【産業上の利用分野】この発明は、沸騰水型原子炉に用
いられる原子炉内蔵型再循環ポンプ(インターナルポン
プとも称す)に係り、特にポンプ部とモータ部とを繋ぐ
シャフトのスラスト方向の軸受部抵抗の低減を図った原
子炉内蔵型再循環ポンプに関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor built-in recirculation pump (also referred to as an internal pump) used in a boiling water reactor, and more particularly to a thrust direction of a shaft connecting a pump part and a motor part. The present invention relates to a recirculation pump with a built-in reactor for reducing bearing resistance.

【0002】[0002]

【従来の技術】原子炉内蔵型再循環ポンプは、原子炉圧
力容器内の冷却材を強制的に循環させるためのもので、
図7に示すように原子炉圧力容器1の下部鏡板1a周辺
部に複数台組み込まれるものである。
2. Description of the Related Art Reactor built-in recirculation pumps are used to forcibly circulate coolant in a reactor pressure vessel.
As shown in FIG. 7, a plurality of reactor pressure vessels 1 are installed around the lower end plate 1a.

【0003】この原子炉内蔵型再循環ポンプは、水浸モ
ータ部2とポンプ部3とで構成されており、ポンプ部3
は原子炉圧力容器1の下部鏡板1aに固着された取付ノ
ズル4より上方に設けられている。そしてこの取付ノズ
ル4内にはモータケーシング5の上部が挿入されて溶接
5aにより固定されている。
This reactor built-in type recirculation pump is composed of a water immersion motor section 2 and a pump section 3.
Is provided above the attachment nozzle 4 fixed to the lower end plate 1a of the reactor pressure vessel 1. The upper portion of the motor casing 5 is inserted into the mounting nozzle 4 and fixed by welding 5a.

【0004】前記モータケーシング5内の水浸モータ部
2は、ステータ6およびロータ7とから成っており、水
浸モータ部2の下部はモータカバー8により密閉されて
いる。このモータケーシング5には、モータ部2で暖め
られた冷却水がモータ部冷却出口配管9aから外部へ導
出され、熱交換により低温となった後、モータ部冷却入
口配管9bより再びモータ部2に導入されるようになっ
ている。
The water immersion motor section 2 in the motor casing 5 comprises a stator 6 and a rotor 7. The lower portion of the water immersion motor section 2 is sealed by a motor cover 8. In the motor casing 5, the cooling water warmed in the motor unit 2 is led out to the outside from the motor unit cooling outlet pipe 9a and becomes a low temperature by heat exchange, and then is returned to the motor unit 2 again from the motor unit cooling inlet pipe 9b. It is being introduced.

【0005】前記ロータ7内にはシャフト10が挿通さ
れて一体化されており、このシャフト10の上端にはポ
ンプインペラ11が着脱自在に取り付けられ、シャフト
10の回転に伴ってポンプインペラ11が回転される。
このポンプインペラ11は原子炉圧力容器1の内壁とシ
ュラウド12との隙間(ダウンカマ部)に取り付けられ
たディフューザ13内に挿入されており、このディフュ
ーザ13はストレッチチューブ14とストレッチチュー
ブナット15とで取付ノズル4の先端部に固定されてい
る。したがって、保守点検時にはポンプインペラ11と
シャフト10とを一体として原子炉圧力容器1外へ取り
出すことができる。
A shaft 10 is inserted into and integrated with the rotor 7, a pump impeller 11 is detachably attached to the upper end of the shaft 10, and the pump impeller 11 rotates as the shaft 10 rotates. To be done.
The pump impeller 11 is inserted into a diffuser 13 attached to a gap (downcomer portion) between the inner wall of the reactor pressure vessel 1 and the shroud 12, and the diffuser 13 is attached by a stretch tube 14 and a stretch tube nut 15. It is fixed to the tip of the nozzle 4. Therefore, at the time of maintenance and inspection, the pump impeller 11 and the shaft 10 can be integrally taken out of the reactor pressure vessel 1.

【0006】前記モータ部2と原子炉圧力容器1の内部
とは空間的に連通されており、モータケーシング5の上
部に取り付けられたパージ水配管16からCRDポンプ
17によって駆動されるパージ水が常時流入していてこ
のパージ水がシャフト10の表面を上方へ向けて流れ、
原子炉圧力容器1内の炉水が漏出しないように水質的に
は完全に分離している。
The motor unit 2 and the interior of the reactor pressure vessel 1 are spatially communicated with each other, and purge water driven by a CRD pump 17 is constantly supplied from a purge water pipe 16 attached to an upper portion of the motor casing 5. Inflowing, this purge water flows upward on the surface of the shaft 10,
Water quality is completely separated so that the reactor water in the reactor pressure vessel 1 does not leak out.

【0007】またモータケーシング5の上部には二次シ
ール18が設けられており、モータ部2を取り外す場合
には圧力水供給管19を介してこの二次シール18に圧
力水を供給し、この二次シール8を膨脹させてシャフト
10の外周面と密着させることにより炉水が洩れ出すの
を防いでいる。
A secondary seal 18 is provided on the upper portion of the motor casing 5. When the motor unit 2 is removed, pressurized water is supplied to the secondary seal 18 via a pressurized water supply pipe 19. By expanding the secondary seal 8 and bringing it into close contact with the outer peripheral surface of the shaft 10, the reactor water is prevented from leaking out.

【0008】前記シャフト10の下方にはスラストディ
スク20が設けられ、ポンプインペラ11、シャフト1
0、ロータ7、およびスラストディスク20は一体とな
って回転するもので、スラストディスク20の上側には
上部スラスト軸受21が、また下側には下部スラスト軸
受22がそれぞれ設置されている。この上部スラスト軸
受21および下部スラスト軸受22は共にスラスト軸受
とされている。
A thrust disc 20 is provided below the shaft 10, and the pump impeller 11 and the shaft 1 are provided.
0, the rotor 7, and the thrust disk 20 rotate together, and an upper thrust bearing 21 is installed on the upper side of the thrust disk 20 and a lower thrust bearing 22 is installed on the lower side thereof. The upper thrust bearing 21 and the lower thrust bearing 22 are both thrust bearings.

【0009】したがって、ポンプインペラ11、シャフ
ト10、ロータ7、およびスラストディスク20から成
る回転体が停止しているとき、および低速回転時にスラ
ストディスク20を介して下部スラスト軸受22により
支持される。また高速回転時にはポンプインペラ11部
での流体の反力により回転体が浮き上がるため、上部ス
ラスト軸受21により支持されることになる。そして回
転体の横方向は上部ラジアル軸受23a、下部ラジアル
軸受23bにより支持される。
Therefore, the lower thrust bearing 22 is supported by the lower thrust bearing 22 via the thrust disk 20 when the rotating body composed of the pump impeller 11, the shaft 10, the rotor 7, and the thrust disk 20 is stopped and at low speed rotation. Further, at the time of high speed rotation, the rotating body floats up due to the reaction force of the fluid in the pump impeller 11 section, so that the upper thrust bearing 21 supports it. The lateral direction of the rotating body is supported by the upper radial bearing 23a and the lower radial bearing 23b.

【0010】[0010]

【発明が解決しようとする課題】しかして通常運転時に
原子炉内蔵型再循環ポンプが何らかの要因により電源を
喪失した場合、原子炉内蔵型再循環ポンプは駆動力を失
うため次第に回転数が低下し、これに伴って下部スラス
ト軸受22とスラストディスク20との接触抵抗が増大
する。
However, in the case where the internal reactor recirculation pump loses power due to some factor during normal operation, the internal reactor recirculation pump loses its driving force and its rotational speed gradually decreases. As a result, the contact resistance between the lower thrust bearing 22 and the thrust disk 20 increases.

【0011】一方、炉心部では依然として発熱されてお
り、この発熱によりシュラウド12の内側の冷却材が熱
せられ、シュラウド12の外側(ダウンカマ部)の冷却
材と密度差が生じる。この密度差を駆動力としてシュラ
ウド12の内側の冷却材は上方へ、またシュラウド12
の外側の冷却材は下方へ流動するように自然循環を行な
う。すなわち原子炉内蔵型再循環ポンプが停止した場合
にも冷却材の自然循環により一定量の炉心流量が得られ
る。この自然循環により得られる炉心流量は、前記の密
度差による駆動力と、原子炉内を循環する際の流動抵抗
との釣合で定まる。
On the other hand, heat is still generated in the core portion, and this heat generation heats the coolant inside the shroud 12, which causes a difference in density with the coolant outside the shroud 12 (downcomer portion). With this density difference as a driving force, the coolant inside the shroud 12 moves upward, and the shroud 12
The coolant on the outer side of the is naturally circulated so as to flow downward. That is, even when the internal reactor recirculation pump is stopped, a certain amount of core flow can be obtained by natural circulation of the coolant. The core flow rate obtained by this natural circulation is determined by the balance between the driving force due to the density difference and the flow resistance when circulating in the reactor.

【0012】この自然循環流によりポンプインペラ11
は回転方向に駆動力が得られ、この自然循環流による駆
動力と、スラストディスク20と下部スラスト軸受22
との抵抗の釣合で自然循環時におけるポンプの回転数が
決まるが、従来の下部スラスト軸受22によると低回転
数領域で抵抗が急激に大きくなり、自然循環力による駆
動力を上廻ってしまうため原子炉内蔵型再循環ポンプは
回転を停止してしまう。このようにポンプの回転が停止
すると、ポンプ部2の流動抵抗がポンプが回転を維持し
ている場合に較べて約14倍程度に大きくなり、その結
果自然循環流量が少なくなるためポンプが回転を維持し
ている場合と較べて炉心安定性および過度特性が悪くな
る。
With this natural circulation flow, the pump impeller 11
Drive force is obtained in the rotation direction, and the drive force by this natural circulation flow and the thrust disk 20 and the lower thrust bearing 22
The rotational speed of the pump during natural circulation is determined by the balance of the resistance with the. However, according to the conventional lower thrust bearing 22, the resistance rapidly increases in the low rotational speed region and exceeds the driving force due to the natural circulation force. Therefore, the recirculation pump with built-in reactor stops rotating. When the rotation of the pump is stopped in this manner, the flow resistance of the pump unit 2 is increased by about 14 times as compared with the case where the pump is kept rotating, and as a result, the natural circulation flow rate is reduced, so that the pump is rotated. The core stability and transient characteristics are worse than when maintained.

【0013】この発明は上記の点に鑑みてなされたもの
で、原子炉内蔵型再循環ポンプが駆動力を失った場合で
あっても回転を維持し得る構造とし、自然循環流量を増
加させることにより炉心安定性、および過度特性の緩和
を図ることができる原子炉内蔵型再循環ポンプを提供す
ることを目的とする。
The present invention has been made in view of the above points, and has a structure capable of maintaining rotation even when the internal reactor recirculation pump loses the driving force, and increasing the natural circulation flow rate. Therefore, it is an object of the present invention to provide a reactor built-in type recirculation pump capable of achieving core stability and mitigation of transient characteristics.

【0014】[0014]

【課題を解決するための手段】上記課題を解決するた
め、この発明に係る原子炉内蔵型再循環ポンプは、原子
炉圧力容器の底面に設置されるポンプと、このポンプを
駆動するモータ部と、前記ポンプとモータ部とを繋ぐシ
ャフトと、このシャフトをスラスト方向に支持する軸受
手段とを有する原子炉内蔵型再循環ポンプにおいて、前
記軸受手段として転がりまたは非接触軸受を用いたもの
である。
In order to solve the above problems, a reactor built-in type recirculation pump according to the present invention comprises a pump installed on the bottom surface of a reactor pressure vessel, and a motor unit for driving the pump. In a nuclear reactor built-in recirculation pump having a shaft connecting the pump and a motor part and a bearing means for supporting the shaft in a thrust direction, a rolling or non-contact bearing is used as the bearing means.

【0015】[0015]

【作用】原子炉内蔵型再循環ポンプが何らかの要因によ
り電源を喪失した場合であってもシャフトのスラスト方
向を支持する軸受手段の抵抗が極小となるため自然循環
力を駆動力としてポンプが回転を持続し、インペラ部の
流動抵抗が大幅に削減されるため自然循環流量を向上さ
せることができ、これにより原子炉内蔵型再循環ポンプ
の駆動力喪失時における炉心安定性、過度特性が緩和さ
れる。
[Effect] Even if the recirculation pump with built-in reactor loses power due to some cause, the resistance of the bearing means that supports the thrust direction of the shaft is minimized, and the pump is rotated using the natural circulation force as the driving force. Sustained and the flow resistance of the impeller is greatly reduced, so that the natural circulation flow rate can be improved, which alleviates the core stability and transient characteristics when the driving force of the internal reactor recirculation pump is lost. .

【0016】[0016]

【実施例】以下この発明の実施例を図1ないし図6によ
り図7と共通する部材には同一符号を付して援用して説
明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS.

【0017】図1はこの発明の第1実施例の全体縦断面
を、図2はスラスト軸受手段の拡大断面を示している。
この実施例においては、シャフト10の下端のスラスト
ディスク20の下面に転動体24と内輪25、外輪2
6、および保持器27とから成る転がり軸受Aが設置さ
れている。上記内輪25はスラストディスク20に取り
漬けられており、スラストディスク20と共に回転され
る。また外輪26はモータカバー8の上部に取り漬けら
れており、ポンプの運転時であっても静止した状態にお
かれる。これら内輪25および外輪26の各対向面には
前記の転動体24が接触する軌道28が周方向に形成さ
れており、この転動体24は図3に示すように保持器2
7によりその位置は変らずに自由に回転できるように外
輪26に保持されている。
FIG. 1 shows an entire longitudinal section of a first embodiment of the present invention, and FIG. 2 shows an enlarged section of thrust bearing means.
In this embodiment, the rolling element 24, the inner ring 25, and the outer ring 2 are provided on the lower surface of the thrust disk 20 at the lower end of the shaft 10.
A rolling bearing A composed of 6 and a cage 27 is installed. The inner ring 25 is immersed in the thrust disc 20 and is rotated together with the thrust disc 20. Further, the outer ring 26 is submerged in the upper portion of the motor cover 8 so that the outer ring 26 remains stationary even when the pump is in operation. On the respective facing surfaces of the inner ring 25 and the outer ring 26, raceways 28 with which the rolling elements 24 come into contact are formed in the circumferential direction, and the rolling elements 24, as shown in FIG.
It is held by the outer ring 26 so that its position can be freely rotated by 7.

【0018】なお、原子炉内蔵型再循環ポンプはそのモ
ータ部2が水漬けとなるため、軸受部の潤滑材として一
般的に用いられるオイルやグリースを使用するとこれら
が水中に漏出するおそれがある。そのためこれらの潤滑
材を使用できず、水を潤滑材とせざるを得ない。したが
って、前記内輪25、外輪26、転動体24として金属
系の素材を使用すると摩耗が大きく、耐久性が低くなる
ため、一部をセラミックス製とすることが好ましい。
Since the motor part 2 of the recirculation pump with built-in reactor is submerged, if oil or grease generally used as a lubricant for the bearing part is used, these may leak into water. . Therefore, these lubricants cannot be used, and water cannot help being used as a lubricant. Therefore, if a metal-based material is used for the inner ring 25, the outer ring 26, and the rolling elements 24, the wear becomes large and the durability becomes low.

【0019】この実施例によれば、シャフト10に掛る
スラスト力は転がり軸受Aによって受けるので、回転抵
抗が著しく低減され、自然循環力を駆動力としてポンプ
の回転が充分に維持される。
According to this embodiment, since the thrust force applied to the shaft 10 is received by the rolling bearing A, the rotational resistance is remarkably reduced, and the rotation of the pump is sufficiently maintained by using the natural circulation force as a driving force.

【0020】図4はこの発明の第2実施例の全体縦断面
を、図5はスラスト軸受手段の拡大断面を示している。
この実施例においては、スラストディスク20の下面に
ポケット29を有した下部スラスト軸受22と、このポ
ケット29にパージ水を流入させたるめのパージ水配管
16とからなる静圧軸受Bが設置されている。
FIG. 4 shows the entire longitudinal section of the second embodiment of the present invention, and FIG. 5 shows the enlarged section of the thrust bearing means.
In this embodiment, a hydrostatic bearing B including a lower thrust bearing 22 having a pocket 29 on the lower surface of the thrust disk 20 and a purge water pipe 16 for allowing purge water to flow into the pocket 29 is installed. There is.

【0021】パージ水配管16は、モータケーシング5
の下部に取り付けられており、パージ水はモータカバー
8を貫通する流路を通り、下部スラスト軸受22のポケ
ット29へ導かれる。したがって、このポケット29に
高圧のパージ水が常時流入することによってポケット2
9内が高圧となり、スラストディスク20に鉛直向きの
力が作用し、スラストディスク20と下部スラスト軸受
22との接触抵抗が低く抑えられる。
The purge water pipe 16 is connected to the motor casing 5
Is attached to the lower portion of the lower thrust bearing 22, and the purge water is guided to the pocket 29 of the lower thrust bearing 22 through the flow path passing through the motor cover 8. Therefore, the high pressure purge water constantly flows into the pocket 29 so that the pocket 2
The pressure inside 9 becomes high, a vertical force acts on the thrust disk 20, and the contact resistance between the thrust disk 20 and the lower thrust bearing 22 is suppressed low.

【0022】停電時を考慮して、図4のように無停電電
源30と、この電源30を駆動源とする補助パージ水ポ
ンプ31と、パージ水水源32とから成る補助パージ水
系を設けることができる。パージ水配管中には逆止弁3
3a,33bが介装され、パージ水の逆流を防止してい
る。またパージ水配管16には締切弁34a,34bが
介装されており、通常運転時には締切弁34aが閉、締
切弁34bが開の状態とされ、パージ水はモータケーシ
ング5の下部から流入するが、保守点検時等にモータ部
2を取り外すときは締切弁34aを開、締切弁34bを
閉の状態にし、二次シール18の上部からパージ水を注
入する。
In consideration of a power failure, as shown in FIG. 4, an auxiliary purge water system including an uninterruptible power supply 30, an auxiliary purge water pump 31 using the power supply 30 as a drive source, and a purge water water source 32 is provided. it can. Check valve 3 in the purge water pipe
3a and 33b are interposed to prevent backflow of purge water. The purge water pipe 16 is provided with shutoff valves 34a and 34b. During normal operation, the shutoff valve 34a is closed and the shutoff valve 34b is opened, so that the purge water flows from the lower portion of the motor casing 5. When the motor unit 2 is removed for maintenance or the like, the shutoff valve 34a is opened and the shutoff valve 34b is closed, and purge water is injected from the upper portion of the secondary seal 18.

【0023】この実施例においても、シャフト10に掛
るスラスト力は静圧軸受Bにより受けるので、回転抵抗
が著しく軽減され、自然循環力を駆動力としてポンプの
回転を維持し、また静圧軸受Bは停電時であってもその
機能を失うことがない。
Also in this embodiment, since the thrust force applied to the shaft 10 is received by the hydrostatic bearing B, the rotational resistance is remarkably reduced, the natural circulation force is used as the driving force to maintain the rotation of the pump, and the hydrostatic bearing B is also used. Does not lose its function even during a power outage.

【0024】図6はこの発明の第3実施例の全体縦断面
を示すもので、ロータ7の上部に永久磁石35が、また
上部ラジアル軸受23aの下部に電磁石36がそれぞれ
設置されている。この電磁石36は無停電電源37を駆
動源とし、原子炉内蔵型再循環ポンプの駆動源が喪失し
たことを感知して瞬時に起動し、永久磁石35との間に
吸引力が作用するように成っている。このときの吸引力
は、シャフト10、インペラ11、スラストディスク2
0、ロータ7、および永久磁石35から成る回転体を上
方に引き上げる程ではないが、下部スラスト軸受22と
スラストディスク20との接触抵抗を充分低減させるだ
けの力とされている。
FIG. 6 shows an overall longitudinal section of a third embodiment of the present invention, in which a permanent magnet 35 is installed above the rotor 7 and an electromagnet 36 is installed below the upper radial bearing 23a. The electromagnet 36 uses the uninterruptible power supply 37 as a drive source, senses that the drive source of the recirculation pump with built-in reactor has been lost, and instantly starts up so that an attractive force acts between the electromagnet 36 and the permanent magnet 35. Made of The suction force at this time is the shaft 10, the impeller 11, and the thrust disc 2.
0, the rotor 7, and the permanent magnet 35 are not enough to pull up the rotor, but the force is sufficient to sufficiently reduce the contact resistance between the lower thrust bearing 22 and the thrust disk 20.

【0025】したがってこの実施例によっても、回転抵
抗が減少され、自然循環力を利用しての回転を継続させ
ることができる。
Therefore, also in this embodiment, the rotation resistance is reduced, and the rotation using the natural circulation force can be continued.

【0026】[0026]

【発明の効果】以上のようにこの発明によれば、原子炉
内蔵型再循環ポンプが何らかの要因により電源を喪失し
た場合であっても、シャフトのスラスト力を受ける軸受
手段の回転抵抗が小さくなるので自然循環力を駆動力と
してのポンプの回転を持続させることができ、その結
果、インペラ部の流動抵抗を大幅に削減できるため自然
循環流量を向上させ、これにより原子炉内蔵型再循環ポ
ンプの駆動力喪失時における炉心安定性の確保および過
度特性の緩和を図ることができる。
As described above, according to the present invention, the rotational resistance of the bearing means that receives the thrust force of the shaft becomes small even if the power supply to the recirculation pump with built-in nuclear reactor is lost due to some factor. Therefore, it is possible to continue the rotation of the pump using the natural circulation force as the driving force, and as a result, the flow resistance of the impeller can be greatly reduced, which improves the natural circulation flow rate. It is possible to secure core stability and alleviate transient characteristics when the driving force is lost.

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

【図1】この発明の第1実施例を示す全体縦断面図。FIG. 1 is an overall vertical sectional view showing a first embodiment of the present invention.

【図2】図1の要部拡大断面図。FIG. 2 is an enlarged cross-sectional view of a main part of FIG.

【図3】図1の転がり軸受の半部断面斜視図。3 is a perspective view of a half portion of the rolling bearing of FIG.

【図4】この発明の第2実施例を示す全体縦断面図。FIG. 4 is an overall vertical sectional view showing a second embodiment of the present invention.

【図5】図4の要部の拡大断面図。5 is an enlarged cross-sectional view of the main part of FIG.

【図6】この発明の第3実施例を示す全体縦断面図。FIG. 6 is an overall vertical sectional view showing a third embodiment of the present invention.

【図7】従来の原子炉内蔵型再循環ポンプの全体縦断面
図。
FIG. 7 is an overall vertical cross-sectional view of a conventional nuclear reactor built-in recirculation pump.

【図8】従来のスラスト軸受の拡大断面図。FIG. 8 is an enlarged sectional view of a conventional thrust bearing.

【符号の説明】[Explanation of symbols]

1 原子炉圧力容器 2 水浸モータ部 3 ポンプ部 5 モータケーシング 6 ステータ 7 ロータ 8 モータカバー 10 シャフト 11 インペラ 12 シュラウド 13 ディフューザ 14 ストレッチチューブ 16 パージ水配管 17 CRDポンプ 18 二次シール 10 圧力水供給管 20 スラストディスク 21 上部スラスト軸受 22 下部スラスト軸受 24 転動体 25 内輪 26 外輪 27 保持器 29 ポケット 30 無停電電源 31 補助パージ水ポンプ 32 パージ水水源 35 永久磁石 36 電磁石 37 無停電電源 A 転がり軸受 B 静翼圧軸受 1 Reactor Pressure Vessel 2 Water Immersion Motor Section 3 Pump Section 5 Motor Casing 6 Stator 7 Rotor 8 Motor Cover 10 Shaft 11 Impeller 12 Shroud 13 Diffuser 14 Stretch Tube 16 Purge Water Piping 17 CRD Pump 18 Secondary Seal 10 Pressure Water Supply Pipe 20 Thrust Disc 21 Upper Thrust Bearing 22 Lower Thrust Bearing 24 Rolling Element 25 Inner Ring 26 Outer Ring 27 Cage 29 Pocket 30 Uninterruptible Power Supply 31 Auxiliary Purge Water Pump 32 Purge Water Source 35 Permanent Magnet 36 Electromagnet 37 Uninterruptible Power Supply A Rolling Bearing B B Blade pressure bearing

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 原子炉圧力容器の底面に設置されるポン
プと、このポンプを駆動するモータ部と、前記ポンプと
モータ部とを繋ぐシャフトと、このシャフトをスラスト
方向に支持する軸受手段とを有する原子炉内蔵型再循環
ポンプにおいて、前記軸受手段として転がりまたは非接
触軸受を用いたことを特徴とする原子炉内蔵型再循環ポ
ンプ。
1. A pump installed on the bottom surface of a reactor pressure vessel, a motor section for driving the pump, a shaft connecting the pump and the motor section, and bearing means for supporting the shaft in the thrust direction. A built-in-reactor recirculation pump, wherein a rolling or non-contact bearing is used as the bearing means.
JP4206711A 1992-08-03 1992-08-03 Recirculation pump installed in nuclear reactor Pending JPH0651089A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4206711A JPH0651089A (en) 1992-08-03 1992-08-03 Recirculation pump installed in nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4206711A JPH0651089A (en) 1992-08-03 1992-08-03 Recirculation pump installed in nuclear reactor

Publications (1)

Publication Number Publication Date
JPH0651089A true JPH0651089A (en) 1994-02-25

Family

ID=16527848

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4206711A Pending JPH0651089A (en) 1992-08-03 1992-08-03 Recirculation pump installed in nuclear reactor

Country Status (1)

Country Link
JP (1) JPH0651089A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112963854A (en) * 2020-07-30 2021-06-15 山东大学 Flue distributor with uniform temperature effect

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112963854A (en) * 2020-07-30 2021-06-15 山东大学 Flue distributor with uniform temperature effect
CN112963854B (en) * 2020-07-30 2021-12-21 山东大学 Flue distributor with uniform temperature effect

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