JPS6122291A - Pump mounting section of pressure vessel for nuclear reactor - Google Patents

Pump mounting section of pressure vessel for nuclear reactor

Info

Publication number
JPS6122291A
JPS6122291A JP59142213A JP14221384A JPS6122291A JP S6122291 A JPS6122291 A JP S6122291A JP 59142213 A JP59142213 A JP 59142213A JP 14221384 A JP14221384 A JP 14221384A JP S6122291 A JPS6122291 A JP S6122291A
Authority
JP
Japan
Prior art keywords
pressure vessel
pump
reactor pressure
pump mounting
motor
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.)
Granted
Application number
JP59142213A
Other languages
Japanese (ja)
Other versions
JPH0527838B2 (en
Inventor
和夫 須賀
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 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

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

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

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(181)
作業の低減を図っ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 Mid-service inspection of reactor pressure vessel (181)
This invention relates to a pump mounting section for a nuclear reactor pressure vessel that aims to reduce work.

[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
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(13
+)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っ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 instead, making the nuclear containment vessel more compact and reducing the reactor pressure. Interim inspection during service period (13
Progress is being made in the development of water-cooled nuclear reactors that reduce the number of welding lines that are subject to +), thereby reducing the amount of work and pump drive power required.

このインターナル・ポンプ方式において、ウェットモー
タを用いだ原子炉内藏形再循環ポンプは、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
を有するボンプモータ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ィフューザ5、ディ
フューザ5を突出部2にH!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ッチチューブ
6、ストレッチチューブ6をスリーブ3aに固定するス
トレッチチューブナラ1〜7、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ャフト
、ディフューザ5の内部に配置されポンプシャフトの端
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
らシールだめの二次シール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 in-reactor cross-shaped recirculation pump using a wet motor has a sleeve attached to a protruding part 2 protruding inside the lower head part 1a of the reactor pressure vessel 1, as shown in FIG. Motor casing 3 with welded 3a
a pump motor 4 having an H! A stretch tube 6 provided in the sleeve portion 3a of the motor casing 3 to do this, stretch tube collars 1 to 7 that fix the stretch tube 6 to the sleeve 3a, and a pump (not shown) connected to the rotating shaft of the pump motor 4 and rotated integrally with the pump motor 4. A shaft, an impeller (not shown) disposed inside the diffuser 5 and attached to the end of the pump shaft, a secondary seal 8 of the sealing reservoir inside the motor casing 3 from the reactor pressure vessel 1 side during maintenance of the pump motor 4, and the reactor. A purge water injection system that injects clean water from the top of the pump motor 4 into the reactor pressure vessel 1 side in order to prevent water from entering the motor casing 3 (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, only the secondary seal inlet 10 is shown in the figure), a pump motor cooling water system that cools the pump motor 4 (however, the pump motor cooling water outlet is not shown in the figure). (only 11 are shown), etc.

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
示すように接近し勤い位置にあるため、溶接作業やその
検査も容易ではない。
However, the pump motor 4 is connected from the reactor pressure vessel 1 side.
In order to reduce heat input to the motor casing 3, a gap (not shown) is provided between the sleeve portion 3a of the motor casing 3 and the protruding portion 2, and the structure utilizes the heat insulating effect of air, so the rigidity of the protruding portion 2 is not necessarily large. This required the installation of a vibration isolator, complicating the equipment layout. Furthermore, since the welded joint between the motor casing 3 and the protrusion 2 is close to each other as shown by reference numeral 12 in FIG. 6, welding work and inspection thereof are not easy.

[発明の目的] 本発明は、−り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41位冒ど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
ことを目的とり−る。
[Object of the Invention] The present invention has been made in view of the above-mentioned circumstances, and improves the vibration characteristics by increasing the rigidity of the pump mounting part, and
It is an object of the present invention to provide a pump mounting part for a nuclear reactor pressure vessel in which the welding position can be easily accessed to facilitate welding work and inspection thereof.

[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
する突出部を鍛造により一体に形成することにより、ポ
ンプ装着部の剛性を増大して振動特性を向上し、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 mounting protrusion by forging, the rigidity of the pump mounting part is increased and vibration characteristics are improved.
The welding position is easily accessible to facilitate welding work and inspection.

[発明の実施例コ 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ッチチューブを挿入する。また、こ
の穴27の下部には、後部27aを設は原子炉圧力容器
21側からポンプモータへの入熱を低減する断熱材28
を挿入し固定する。
[Embodiment of the Invention] Hereinafter, an embodiment of the present invention will be described 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 protrusion 22
has a cylindrical shape and has an outer shape approximately equal to the outer shape 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 motor casing 23. 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 inserted into the protrusions 22 and 25 through the holes 27. Further, a rear part 27a is provided at the bottom of this hole 27, and a heat insulating material 28 is provided at the bottom of the hole 27 to reduce heat input from the reactor pressure vessel 21 side to the pump motor.
Insert and secure.

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 prevents heat transfer due to convection of cooling water in the motor casing 23 at the lower part of the protrusion 22 where the temperature difference is large, and functionally corresponds to the conventional gap described above. As shown in FIGS. 2 and 3, the structure consists of an annular housing 29 and thin metal plates 30 laminated inside the housing, reducing heat transfer due to thermal resistance between the contact surfaces of each metal plate 30. It is fixed to the rear part 27a of the hole 27 with a screw 31.

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
にあったのに対し、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(Y6一 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 structure described above, the rigidity of the protrusion 22 to which the pump motor is mounted is greatly increased, which is different from the conventional protrusion 2.
In this case, 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. As shown by B in the figure, the amplitude is small, and its natural frequency (indicated by Y6) can be set outside the pump's motion range, making it possible to eliminate resonance with the system during pump operation.

[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。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 rigidity of the pump mounting portion is increased, vibration during pump operation and vibration response at the time of earthquake occurrence are reduced, and vibration characteristics are improved. 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・・・ディフューザ 6・・・ストレッチチコーブ 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 代理人 弁理士 則 近 憲 佑(ほか1名)第  1
  図 第  2  図 第 3 図 第  5  図 I 第  651!
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... Diffuser 6... Stretch cove 21... Reactor pressure vessel 21a... Lower mirror portion 22.25... Projection portion 23... Motor casing 24.26... Welded joint portion Agent: Patent Attorney Noriyuki Chika (and 1 other person) No. 1
Figure 2 Figure 3 Figure 5 Figure I 651!

Claims (4)

【特許請求の範囲】[Claims] (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たことを特徴
とする原子炉圧力容器のポンプ装着部。
(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 protruding portion on the outside of a lower mirror portion of the reactor pressure vessel is mounted with a motor for driving the pump. A pump attachment part for a nuclear reactor pressure vessel, characterized in that it is integrally formed by forging.
(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。
(2) A pump mounting portion for a reactor pressure vessel according to claim 1, characterized in that a motor casing is welded to the protruding portion.
(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。
(3) The pump mounting portion for a reactor pressure vessel according to claim 1, wherein a protruding portion is provided on the inside of the lower mirror portion by welding.
(4)突出部の内部に、断熱材を装着したことを特徴と
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。
(4) A pump mounting portion for a reactor pressure vessel according to claim 1, characterized in that a heat insulating material is mounted inside the protruding portion.
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 true JPS6122291A (en) 1986-01-30
JPH0527838B2 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)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108412783A (en) * 2017-02-10 2018-08-17 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
JPS5857000U (en) * 1981-10-14 1983-04-18 石川島播磨重工業株式会社 reactor pressure vessel

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5857000B2 (en) * 1976-02-18 1983-12-17 株式会社日立製作所 multilayer printed wiring board

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
JPS57157187A (en) * 1981-03-25 1982-09-28 Babcock Hitachi Kk Pressure vessel of bwr type reactor
JPS5857000U (en) * 1981-10-14 1983-04-18 石川島播磨重工業株式会社 reactor pressure vessel

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108412783A (en) * 2017-02-10 2018-08-17 国核电站运行服务技术有限公司 Nuclear power shielding main pump dismounting process test-bed

Also Published As

Publication number Publication date
JPH0527838B2 (en) 1993-04-22

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