JPH0527838B2 - - Google Patents

Info

Publication number
JPH0527838B2
JPH0527838B2 JP59142213A JP14221384A JPH0527838B2 JP H0527838 B2 JPH0527838 B2 JP H0527838B2 JP 59142213 A JP59142213 A JP 59142213A JP 14221384 A JP14221384 A JP 14221384A JP H0527838 B2 JPH0527838 B2 JP H0527838B2
Authority
JP
Japan
Prior art keywords
pump
pressure vessel
reactor pressure
motor
protrusion
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
Application number
JP59142213A
Other languages
Japanese (ja)
Other versions
JPS6122291A (en
Inventor
Kazuo Suga
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP59142213A priority Critical patent/JPS6122291A/en
Publication of JPS6122291A publication Critical patent/JPS6122291A/en
Publication of JPH0527838B2 publication Critical patent/JPH0527838B2/ja
Granted 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

  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Magnetic Resonance Imaging Apparatus (AREA)

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は、水冷却原子炉の原子炉圧力容器に係
り、特に原子炉内蔵形再循環ポンプの装着部の剛
性を増大し、振動特性や原子炉圧力容器の供用期
間中間検査(ISI)作業の低減を図つた原子炉圧
力容器のポンプ装着部に関するものである。
Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a reactor pressure vessel of a water-cooled nuclear reactor, and in particular increases the rigidity of a mounting part of a built-in reactor recirculation pump, improves vibration characteristics and This relates to a pump installation part of a reactor pressure vessel that aims to reduce the amount of work required for interim in-service inspection (ISI) of the reactor pressure vessel.

[発明の技術的背景とその問題点] 現在、原子炉再循環系外部ループをなくし、こ
れに代えてインターナル・ポンプ方式の再循環系
を採用し、原子炉格納容器のコンパクト化、原子
炉圧力容器の耐震性向上、外部再循環配管の削除
により供用期間中間検査(ISI)の対象となる溶
接線を減少して作業量の低減、ポンプ駆動動力の
減少等を図つた水冷却原子炉の開発が進められて
いる。
[Technical background of the invention and its problems] At present, the external loop of the reactor recirculation system has been eliminated and an internal pump type recirculation system has been adopted in its place. A water-cooled nuclear reactor that improves the earthquake resistance of the pressure vessel, eliminates external recirculation piping, reduces the number of weld lines subject to interim in-service inspection (ISI), reduces workload, and reduces pump drive power. Development is underway.

このインターナル・ポンプ方式において、ウエ
ツトモータを用いた原子炉内蔵形再循環ポンプ
は、第5図に示すように原子炉圧力容器1の下鏡
部1aの内側に突出した突出部2にスリーブ3a
を溶接したモータケーシング3を有するポンプモ
ータ4、原子炉圧力容器1の内部に配置され、ポ
ンプ吐出流を整流するデイフユーザ5、デイフユ
ーザ5を突出部2に装着するためにモータケーシ
ング3のスリーブ部3aに設けられるストレツチ
チユーブ6、ストレツチチユーブ6をスリーブ3
aに固定するストレツチチユーブナツト7、ポン
プモータ4の回転軸に連結され一体的に回転する
図示しないポンプシヤフト、デイフユーザ5の内
部に配置されポンプシヤフトの端部に装着される
図示しないインペラ、ポンプモータ4の保守時に
モータケーシング3内を原子炉圧力容器1側から
シールための二次シール8、原子炉水がモータケ
ーシング3内に侵入するのを防ぐために、ポンプ
モータ4の上部から原子炉圧力容器1側へ清浄水
を注入するパージ水注入系統(ただし同図にはパ
ージ水入口9のみを示す)、二次シール8へ加圧
水を充填する二次シール(ただし同図には二次シ
ール入口10のみを示す)、ポンプモータ4を冷
却するポンプモー冷却水系統(ただし同図にはポ
ンプモータ冷却水出口11のみを示す)等から構
成されている。
In this internal pump system, the reactor built-in recirculation pump using a wet motor has a sleeve 3a attached to a protruding part 2 protruding inside the lower mirror part 1a of the reactor pressure vessel 1, as shown in FIG.
A pump motor 4 having a motor casing 3 welded with The stretch tube 6 is attached to the sleeve 3.
a stretch tube nut 7 fixed to a, a pump shaft (not shown) connected to the rotating shaft of the pump motor 4 and rotated integrally therewith, an impeller (not shown) disposed inside the differential user 5 and attached to the end of the pump shaft, and a pump. A secondary seal 8 is used to seal the inside of the motor casing 3 from the reactor pressure vessel 1 side during maintenance of the motor 4, and a secondary seal 8 is used to seal the inside of the motor casing 3 from the reactor pressure vessel 1 side. A purge water injection system that injects clean water into the container 1 side (however, only the purge water inlet 9 is shown in the figure), a secondary seal that fills pressurized water into the secondary seal 8 (however, the figure shows only the purge water inlet 9) 10), a pump motor cooling water system for cooling the pump motor 4 (however, only the pump motor cooling water outlet 11 is shown in the figure), and the like.

しかしながら、原子炉圧力容器1側からポンプ
モータ4への入熱を低減させるために、モータケ
ーシング3のスリーブ部3aと突出部2に図示し
ない空隙を設けて、空気による断熱効果を利用し
た構成としているから、突出部2の剛性が必ずし
も大きくなく、防振器の装着が必要となり機器配
置が複雑化していた。また、モータケーシング3
と突出部2の溶接接合部は、第6図に符号12で
示すように接近し難い位置にあるため、溶接作業
やその検査も容易ではない。
However, in order to reduce the heat input from the reactor pressure vessel 1 side to the pump motor 4, a gap (not shown) is provided in the sleeve portion 3a and the protruding portion 2 of the motor casing 3, and a configuration utilizing the heat insulation effect of air is adopted. Because of this, the rigidity of the protrusion 2 is not necessarily high, and a vibration isolator must be installed, which complicates the equipment arrangement. Also, motor casing 3
The welded joint of the protrusion 2 and the protrusion 2 is located in a difficult-to-reach position as indicated by reference numeral 12 in FIG. 6, and therefore welding work and inspection thereof are not easy.

[発明の目的] 本発明は、上記した事情に鑑みてなされたもの
で、ポンプ装着部の剛性を増大して振動特性を向
上し、また、溶接位置を接近容易な位置として溶
接作業やその検査を容易とした原子炉圧力容器の
ポンプ装着部を提供することを目的とする。
[Object of the Invention] The present invention was made in view of the above-mentioned circumstances, and it increases the rigidity of the pump mounting part to improve vibration characteristics, and also makes the welding position an easily accessible position to facilitate welding work and inspection. An object of the present invention is to provide a pump mounting part for a nuclear reactor pressure vessel that facilitates the installation of a pump.

[発明の概要] 本発明は、炉心へ冷却材を供給するポンプを一
体に装着する原子炉圧力容器のポンプ装着部にお
いて、原子炉圧力容器の下鏡部の外側に、ポンプ
駆動用のモータを装着する突出部を鍜造により一
体に形成し、この突出部の内部に断熱材を装着す
ることにより、ポンプ装着部の剛性を増大して振
動特性を向上し、かつ剛性の増大にともなう水平
断面積(入熱面積)の増加による入熱量の増加を
低減させることができ、また、溶接位置を接近容
易な位置として溶接作業やその検査を容易とした
ものである。
[Summary of the Invention] The present invention provides a pump-driving motor that is mounted on the outside of the lower head of the reactor pressure vessel in a pump mounting portion of a reactor pressure vessel that is integrally equipped with a pump that supplies coolant to the reactor core. By integrally forming the protruding part to be attached by forging and installing a heat insulating material inside this protruding part, the rigidity of the pump attaching part is increased and the vibration characteristics are improved. It is possible to reduce the increase in heat input due to an increase in area (heat input area), and the welding position can be easily accessed to facilitate welding work and inspection.

[発明の実施例] 以下、本発明の一実施例を図面を参照して説明
する。第5図および第6図と同一部分に同符号を
付した第1図において、原子炉圧力容器21の下
鏡部21aに例えば鍛造により突出部22を一体
に形成する。この突出部22は、円筒状をなし外
形は図示しないポンプモータのモータケーシング
23の外形に略等しい寸法とし、この下端部にモ
ータケーシング23(ただしスリーブは設けられ
ていない)の端部を溶接接合する。符号24はこ
の溶接接合部を示し、所定の耐圧性を保持するよ
うにする。また、下鏡部21aの内側には、突出
部22と同心に突出部25を溶接接合する。符号
26はこの溶接接合部を示す。しかして、突出部
22と25には、穴27を貫通して図示しないス
トレツチチユーブを挿入する。また、この穴27
の下部には、後部27aを設け原紙炉圧力容器2
1側からポンプモータへの剛性の増大にともなう
突出部22の水平断面積(入熱面積)の増加も含
めた入熱を低減する断熱材28を挿入し固定す
る。
[Embodiment of the Invention] An embodiment of the present invention will be described below with reference to the drawings. In FIG. 1, in which the same parts as in FIGS. 5 and 6 are given the same reference numerals, a protrusion 22 is integrally formed on the lower mirror portion 21a of the reactor pressure vessel 21 by, for example, forging. This protruding part 22 has a cylindrical shape and has an outer shape approximately equal to the outer diameter of a motor casing 23 of a pump motor (not shown), and the end of the motor casing 23 (however, no sleeve is provided) is welded to the lower end of the protruding part 22. do. Reference numeral 24 indicates this welded joint, which maintains a predetermined pressure resistance. Furthermore, a protrusion 25 is welded to the inside of the lower mirror portion 21a, concentrically with the protrusion 22. Reference numeral 26 indicates this welded joint. Stretch tubes (not shown) are then inserted into the protrusions 22 and 25 by passing through the holes 27. Also, this hole 27
A rear part 27a is provided at the bottom of the paper furnace pressure vessel 2.
A heat insulating material 28 is inserted and fixed to reduce heat input from the first side to the pump motor, including an increase in the horizontal cross-sectional area (heat input area) of the protrusion 22 due to an increase in rigidity.

この断熱材28は、温度差の大きい突出部22
の下部で、モータケーシング23内の冷却水の対
流による熱伝達を妨げるもので、上記した従来の
空隙に機能的に対応するものである。構成は、第
2図および第3図に示すように、環状のハウジン
グ29と、この内部に積層された薄い金属板30
から成り、各金属板30の接触面間の熱抵抗によ
り熱伝達を低下させるもので、ねじ31により穴
27の後部27aに固定される。
This heat insulating material 28 has a large temperature difference between the protrusions 22 and 28.
This prevents heat transfer by convection of the cooling water within the motor casing 23, and corresponds functionally to the conventional gap described above. As shown in FIGS. 2 and 3, the structure includes an annular housing 29 and a thin metal plate 30 laminated inside the annular housing 29.
The metal plate 30 is fixed to the rear part 27a of the hole 27 with a screw 31 to reduce heat transfer due to the thermal resistance between the contact surfaces of each metal plate 30.

以上のように構成されているから、ポンプモー
タを装着する突出部22の剛性が大幅に増大し、
従来の突出部2ではポンプモータの下端が第4図
のAで示すように振動し、その固有振動数(Xで
示す)がポンプの運転範囲内にあつたのに対し、
突出部22ではポンプモータの下端が同図のBで
示すように振幅も小さく、しかもその固有振動数
(Yで示す)をポンプの運動範囲外とすることが
可能となり、ポンプ運転時の系との共振をなくす
ることができる。
With the above configuration, the rigidity of the protruding portion 22 to which the pump motor is mounted is greatly increased.
In the conventional protrusion 2, the lower end of the pump motor vibrates as shown by A in FIG. 4, and its natural frequency (indicated by X) is within the operating range of the pump.
In the protruding portion 22, the lower end of the pump motor has a small amplitude as shown by B in the same figure, and its natural frequency (indicated by Y) can be set outside the pump's motion range, making it difficult for the system to operate the pump. resonance can be eliminated.

さらに、突出部22の剛性の増大にともなう水
平断面積(入熱面積)の増加による入熱量の増加
を断熱材によつて低減できるので、ポンプモータ
の温度上昇を抑制でき、さらに信頼性の向上を図
ることができる。
Furthermore, the heat insulating material can reduce the increase in heat input due to an increase in the horizontal cross-sectional area (heat input area) due to an increase in the rigidity of the protrusion 22, so it is possible to suppress the temperature rise of the pump motor and further improve reliability. can be achieved.

[発明の効果] 本発明は、以上のように構成されているから、
ポンプ装着部の剛性が増大して、ポンプ運転中の
振動や地震発生時の振動応答を小さくし振動特性
を改善することができ、さらに剛性の増大にとも
なう突出部の水平断面積の増加による入熱量の増
加を抑制できポンプモータの信頼性の向上を図る
ことができる。また、防振器の装着を不要として
スペースの有効利用を図ることができる。さら
に、溶接接合部を接近の容易な位置として、溶接
作業の容易性と信頼性を向上し、溶接接合部の検
査の作業性を向上しかつ作業時の被ばくの低減を
図ることができる。
[Effects of the Invention] Since the present invention is configured as described above,
The increased rigidity of the pump mounting part reduces vibrations during pump operation and vibration response during earthquakes, improving vibration characteristics.Furthermore, the increase in rigidity also reduces the impact due to the increased horizontal cross-sectional area of the protruding part. It is possible to suppress an increase in the amount of heat and improve the reliability of the pump motor. Furthermore, it is not necessary to install a vibration isolator, and space can be used effectively. Furthermore, by setting the welded joint at an easily accessible position, it is possible to improve the ease and reliability of welding work, improve the workability of inspecting the welded joint, and reduce radiation exposure during work.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明の原子炉圧力容器のポンプ装着
部の一実施例を示す断面図、第2図は本発明の原
子炉圧力容器のポンプ装着部の一実施例の断熱材
の断面図、第3図は第2図の平面図、第4図は本
発明の実施例および従来のポンプモータのモータ
ケーシングの振幅と固有振動数の関係を示す線
図、第5図は従来の原子炉圧力容器のポンプ装着
構成を示す断面図、第6図は従来の原子炉圧力容
器のポンプ装着部を示す断面図である。 5……デイフユーザ、6……ストレツチチユー
ブ、21……原子炉圧力容器、21a……下鏡
部、22,25……突出部、23……モータケー
シング、24,26……溶接接合部。
FIG. 1 is a sectional view showing an embodiment of the pump mounting part of the reactor pressure vessel of the present invention, and FIG. 2 is a sectional view of the heat insulating material of the pump mounting part of the reactor pressure vessel of the present invention. Fig. 3 is a plan view of Fig. 2, Fig. 4 is a diagram showing the relationship between the amplitude and natural frequency of the motor casing of the embodiment of the present invention and a conventional pump motor, and Fig. 5 is a diagram showing the relationship between the amplitude and natural frequency of the motor casing of the embodiment of the present invention and the conventional pump motor. FIG. 6 is a sectional view showing a pump mounting structure of a conventional nuclear reactor pressure vessel. 5...Diff user, 6...Stretch tube, 21...Reactor pressure vessel, 21a...Lower mirror part, 22, 25...Protrusion part, 23...Motor casing, 24, 26...Weld joint part.

Claims (1)

【特許請求の範囲】 1 炉心へ冷却材を供給するポンプを一体に装着
する原子炉圧力容器のポンプ装着部において、前
記原子炉圧力容器の下鏡部の外側に、前記ポンプ
駆動用のモータを装着する突出部を鍛造により一
体に形成し、この突出部の内部に断熱材を装着し
たことを特徴とする原子炉圧力容器のポンプ装着
部。 2 突出部に、モータケーシングを溶接接合した
ことを特徴とする特許請求の範囲第1項記載の原
子炉圧力容器のポンプ装着部。 3 下鏡部の内側に、突出部を溶接接合で設けた
ことを特徴とする特許請求の範囲第1項記載の原
子炉圧力容器のポンプ装着部。
[Scope of Claims] 1. In a pump mounting portion of a reactor pressure vessel in which a pump for supplying coolant to the reactor core is integrally mounted, a motor for driving the pump is mounted outside a lower mirror portion of the reactor pressure vessel. A pump attachment part for a nuclear reactor pressure vessel, characterized in that a protrusion to be attached is integrally formed by forging, and a heat insulating material is attached inside the protrusion. 2. A pump mounting portion for a nuclear reactor pressure vessel according to claim 1, wherein a motor casing is welded to the protruding portion. 3. A pump mounting portion for a reactor pressure vessel according to claim 1, characterized in that a protruding portion is provided on the inside of the lower mirror portion by welding.
JP59142213A 1984-07-11 1984-07-11 Pump mounting section of pressure vessel for nuclear reactor Granted JPS6122291A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59142213A JPS6122291A (en) 1984-07-11 1984-07-11 Pump mounting section of pressure vessel for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59142213A JPS6122291A (en) 1984-07-11 1984-07-11 Pump mounting section of pressure vessel for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS6122291A JPS6122291A (en) 1986-01-30
JPH0527838B2 true JPH0527838B2 (en) 1993-04-22

Family

ID=15310028

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59142213A Granted JPS6122291A (en) 1984-07-11 1984-07-11 Pump mounting section of pressure vessel for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS6122291A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108412783B (en) * 2017-02-10 2019-07-26 国核电站运行服务技术有限公司 Nuclear power shielding main pump dismounting process test-bed

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS4947239A (en) * 1972-09-01 1974-05-07
JPS5234418A (en) * 1975-07-08 1977-03-16 Cockerill Metallic containers
JPS57157187A (en) * 1981-03-25 1982-09-28 Babcock Hitachi Kk Pressure vessel of bwr type reactor
JPS5857000B2 (en) * 1976-02-18 1983-12-17 株式会社日立製作所 multilayer printed wiring board

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5857000U (en) * 1981-10-14 1983-04-18 石川島播磨重工業株式会社 reactor pressure vessel

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS4947239A (en) * 1972-09-01 1974-05-07
JPS5234418A (en) * 1975-07-08 1977-03-16 Cockerill Metallic containers
JPS5857000B2 (en) * 1976-02-18 1983-12-17 株式会社日立製作所 multilayer printed wiring board
JPS57157187A (en) * 1981-03-25 1982-09-28 Babcock Hitachi Kk Pressure vessel of bwr type reactor

Also Published As

Publication number Publication date
JPS6122291A (en) 1986-01-30

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