JPH0139077B2 - - Google Patents

Info

Publication number
JPH0139077B2
JPH0139077B2 JP54131242A JP13124279A JPH0139077B2 JP H0139077 B2 JPH0139077 B2 JP H0139077B2 JP 54131242 A JP54131242 A JP 54131242A JP 13124279 A JP13124279 A JP 13124279A JP H0139077 B2 JPH0139077 B2 JP H0139077B2
Authority
JP
Japan
Prior art keywords
nozzle
water supply
thermal sleeve
safe end
spargeer
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
Application number
JP54131242A
Other languages
Japanese (ja)
Other versions
JPS5654391A (en
Inventor
Fumihiko Ko
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 JP13124279A priority Critical patent/JPS5654391A/en
Publication of JPS5654391A publication Critical patent/JPS5654391A/en
Publication of JPH0139077B2 publication Critical patent/JPH0139077B2/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

  • Protection Of Pipes Against Damage, Friction, And Corrosion (AREA)

Description

【発明の詳細な説明】 本発明は、原子炉圧力容器等に冷却水を注入す
る給水ノズルに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a water supply nozzle for injecting cooling water into a nuclear reactor pressure vessel or the like.

一般に、原子炉圧力容器に冷却水を注入する給
水ノズルには、原子炉圧力容器内の温度に比較し
て低温の流体が流れる。したがつて、このような
給水ノズルに対しては、従来から上記の温度差に
対処するための構造が採られている。すなわち、
第1図に示すように、圧力容器の壁部1に設けら
れたノズル1aにはその端部にセイフエンド部2
が固着されており、そのセイフエンド部の先端に
溶接等により固着されたサーマルスリーブ3が上
記ノズル1a内に同心的に配設され、そのサーマ
ルスリーブ3の先端が、圧力容器の内周に沿つて
配設された給水スパージヤ4に溶接等により固着
されている。
Generally, a fluid at a low temperature compared to the temperature inside the reactor pressure vessel flows through a water supply nozzle that injects cooling water into the reactor pressure vessel. Therefore, such water supply nozzles have conventionally been constructed to cope with the above-mentioned temperature difference. That is,
As shown in FIG. 1, a nozzle 1a provided on the wall 1 of the pressure vessel has a safe end portion 2 at its end.
is fixed, and a thermal sleeve 3 fixed by welding or the like to the tip of the safe end is concentrically disposed within the nozzle 1a, and the tip of the thermal sleeve 3 extends along the inner circumference of the pressure vessel. It is fixed to the provided water supply spargeer 4 by welding or the like.

しかし、セイフエンド部2とサーマルスリーブ
3の結合が単純な冷し嵌め構造の場合には、ノズ
ル1の内面とサーマルスリーブ3の外面との間隙
に炉水より低温の給水が漏洩侵入したり、この間
隙内の炉水がサーマルスリーブ3の熱伝導により
冷却され、これらの低温水と高温炉水との流れに
よつて、ノズル1a内面に熱応力が発生する。
However, when the safe end part 2 and the thermal sleeve 3 are connected by a simple cold fitting structure, feed water at a temperature lower than the reactor water may leak into the gap between the inner surface of the nozzle 1 and the outer surface of the thermal sleeve 3. The reactor water in the gap is cooled by heat conduction through the thermal sleeve 3, and the flow of these low-temperature water and high-temperature reactor water generates thermal stress on the inner surface of the nozzle 1a.

本発明はこのような点に鑑み、ノズルの熱応力
を低減し、より信頼性の高い給水ノズルを提供す
ることを目的とする。
In view of these points, an object of the present invention is to reduce the thermal stress of the nozzle and provide a more reliable water supply nozzle.

以下、第2図を参照して本発明の一実施例につ
いて説明する。なお、第1図と同一部分について
は同一符号を付する。
An embodiment of the present invention will be described below with reference to FIG. Note that the same parts as in FIG. 1 are given the same reference numerals.

第2図において、ノズル1aのセイフエンド部
2にはサーマルスリーブ3aが溶接により固着さ
れており、そのサーマルスリーブ3aはノズル1
aのコーナ部からさらに圧力容器内側に突出され
ている。セイフエンド部2の配管側寄り内面に
は、不銹鋼5が内張りされており、その内面に給
水スパージヤ4の後端部が固着されている。
In FIG. 2, a thermal sleeve 3a is fixed to the safe end portion 2 of the nozzle 1a by welding, and the thermal sleeve 3a is attached to the nozzle 1.
It further protrudes inside the pressure vessel from the corner part of a. The inner surface of the safe end portion 2 closer to the piping side is lined with stainless steel 5, and the rear end portion of the water supply spargeer 4 is fixed to the inner surface.

しかして、セイフエンド部2にサーマルスリー
ブ3aを溶接により固着しているため給水が直接
ノズル1aの内面に接することなく、またノズル
1aの内面付近の炉水と、給水との間には、サー
マルスリーブ3aと給水スパージヤ4の二重の円
筒が存在するため、ノズル1a内面の冷却が緩和
される。したがつて、ノズル1a内面の熱応力が
低減でき、また給水スパージヤ4がセイフエンド
部2の配管側に近い所で固着されているため、セ
イフエンド部2の熱応力も低減せしめることがで
きる。さらにセイフエンド部2の内面の給水スパ
ージヤ4の固着部に不銹鋼5を内張りすれば、腐
食がより防止され、給水がサーマルスリーブ3a
内面に漏洩侵入することも防止される。
Since the thermal sleeve 3a is fixed to the safe end part 2 by welding, the water supply does not come into direct contact with the inner surface of the nozzle 1a, and there is no thermal sleeve between the reactor water near the inner surface of the nozzle 1a and the water supply. 3a and the water supply spargeer 4 exist, cooling of the inner surface of the nozzle 1a is alleviated. Therefore, the thermal stress on the inner surface of the nozzle 1a can be reduced, and since the water supply spargeer 4 is fixed close to the piping side of the safe end section 2, the thermal stress on the safe end section 2 can also be reduced. Furthermore, if the fixed part of the water supply spargeer 4 on the inner surface of the safe end part 2 is lined with stainless steel 5, corrosion can be further prevented and the water supply can be prevented from entering the thermal sleeve 3a.
It is also prevented from leaking into the inner surface.

以上説明したように本発明によれば、ノズルの
内面付近の炉水と給水との間に、サーマルスリー
ブと給水スパージヤ4との二重の円筒が存在する
ため、ノズル内面の熱応力を低減することがで
き、給水スパージヤをセイフエンド部の配管側寄
りで固着したことにより、セイフエンド部の熱応
力も低減し、健全性を向上せしめことができる等
の効果を奏する。
As explained above, according to the present invention, there is a double cylinder of the thermal sleeve and the water supply spargeer 4 between the reactor water and the feed water near the inner surface of the nozzle, so that thermal stress on the inner surface of the nozzle is reduced. By fixing the water supply spargeer near the piping side of the safe end part, the thermal stress of the safe end part can be reduced and the soundness of the safe end part can be improved.

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

第1図は従来の給水ノズルの断面図、第2図は
本発明による一実施例の給水ノズルの断面図であ
る。 1a……ノズル、2……セイフエンド部、3a
……サーマルスリーブ、4……給水スパージヤ、
5……不銹鋼。
FIG. 1 is a sectional view of a conventional water supply nozzle, and FIG. 2 is a sectional view of an embodiment of a water supply nozzle according to the present invention. 1a... Nozzle, 2... Safe end part, 3a
...Thermal sleeve, 4...Water supply spargear,
5... Rustless steel.

Claims (1)

【特許請求の範囲】[Claims] 1 ノズル、サーマルスリーブおよび給水スパー
ジヤを有する給水ノズルにおいて、ノズルのセイ
フエンド部に、ノズルの先端コーナ部から炉容器
内方に突出形成するサーマルスリーブを固着する
とともに、セイフエンド部の内面、配管側寄りに
給水スパージヤの後端部を固着したことを特徴と
する給水ノズル。
1. In a water supply nozzle having a nozzle, a thermal sleeve, and a water supply spargeer, a thermal sleeve that protrudes from the tip corner of the nozzle toward the inside of the reactor vessel is fixed to the safe end of the nozzle, and a thermal sleeve is attached to the inner surface of the safe end, closer to the piping side. A water supply nozzle characterized in that the rear end of a water supply spargeer is fixed.
JP13124279A 1979-10-11 1979-10-11 Feedwater nozzle Granted JPS5654391A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13124279A JPS5654391A (en) 1979-10-11 1979-10-11 Feedwater nozzle

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13124279A JPS5654391A (en) 1979-10-11 1979-10-11 Feedwater nozzle

Publications (2)

Publication Number Publication Date
JPS5654391A JPS5654391A (en) 1981-05-14
JPH0139077B2 true JPH0139077B2 (en) 1989-08-17

Family

ID=15053320

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13124279A Granted JPS5654391A (en) 1979-10-11 1979-10-11 Feedwater nozzle

Country Status (1)

Country Link
JP (1) JPS5654391A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60215754A (en) * 1984-04-11 1985-10-29 Nippon Kokan Kk <Nkk> Manufacture of thermally sprayed layer having high hardness
EP0681301A1 (en) * 1994-05-04 1995-11-08 General Electric Company Feedwater nozzle and method of repair

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4168071A (en) * 1978-03-17 1979-09-18 General Electric Company Thermal isolator
JPS5430198B2 (en) * 1972-11-15 1979-09-28
JPS5583892A (en) * 1978-12-20 1980-06-24 Hitachi Ltd Feedwater nozzle for reactor pressure vessel

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5430198U (en) * 1977-08-01 1979-02-27

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5430198B2 (en) * 1972-11-15 1979-09-28
US4168071A (en) * 1978-03-17 1979-09-18 General Electric Company Thermal isolator
JPS5583892A (en) * 1978-12-20 1980-06-24 Hitachi Ltd Feedwater nozzle for reactor pressure vessel

Also Published As

Publication number Publication date
JPS5654391A (en) 1981-05-14

Similar Documents

Publication Publication Date Title
US4834935A (en) Feedwater sparger assembly
US5785361A (en) Feedwater nozzle thermal sleeve
GB1003714A (en) Improvements in or relating to pressure vessels and to pressurisers using such vessel
JPH0139077B2 (en)
GB2156463A (en) Pipe junction-internal insulation
US4356147A (en) Fluid tight and thermally insulated coupling assembly
US2471475A (en) Hot-water tank connection
JPS6118157B2 (en)
JP4301604B2 (en) Pressurized water reactor
US2849389A (en) Corrosion resistant jacketed metal body
JPH031633B2 (en)
JPS5941557B2 (en) nuclear fuel assembly
JPS6038240Y2 (en) Reactor
JPH018792Y2 (en)
JPS59100895A (en) Nozzle
JPS6180094A (en) Wedling thermal sleeve
JPS63631Y2 (en)
JPS60238788A (en) Liquid metal cooling type nuclear reactor
Grigor'yants et al. Tests on zirconium superheating channels in the first unit at the Kurchatov Beloyarsk nuclear power station
JPS60165594A (en) Nozzle for pressure vessel of reactor
CN117226357A (en) Novel welded structure temperature regulator
Walling Nozzle seal
GB1041042A (en) Improvements in concrete walls
JPS60171487A (en) Pressure vessel for nuclear reactor
JPS6349754Y2 (en)