JPS6118157B2 - - Google Patents

Info

Publication number
JPS6118157B2
JPS6118157B2 JP54091891A JP9189179A JPS6118157B2 JP S6118157 B2 JPS6118157 B2 JP S6118157B2 JP 54091891 A JP54091891 A JP 54091891A JP 9189179 A JP9189179 A JP 9189179A JP S6118157 B2 JPS6118157 B2 JP S6118157B2
Authority
JP
Japan
Prior art keywords
nozzle
sleeve
intermediate sleeve
pressure vessel
flange
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
JP54091891A
Other languages
Japanese (ja)
Other versions
JPS5614998A (en
Inventor
Tooru Kawasaki
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 JP9189179A priority Critical patent/JPS5614998A/en
Publication of JPS5614998A publication Critical patent/JPS5614998A/en
Publication of JPS6118157B2 publication Critical patent/JPS6118157B2/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

  • Pressure Vessels And Lids Thereof (AREA)

Description

【発明の詳細な説明】 本発明は、原子炉圧力容器の給水等に用いられ
るノズルに係り、特にノズルコーナー部の熱応力
クラツクの発生を防止して、原子炉圧力容器等の
安全性を高め得るノズルに関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nozzle used for water supply to a nuclear reactor pressure vessel, etc., and in particular prevents the occurrence of thermal stress cracks at nozzle corners, thereby increasing the safety of the reactor pressure vessel, etc. Regarding the nozzle obtained.

従来の原子炉圧力容器の給水ノズルは、例えば
第1図に示すように、圧力容器の胴部1の外側に
一体に形成された筒状のノズル本体2と、このノ
ズル本体2に内側からすきま嵌めされたサーマル
スリーブ3とを有している。このサーマルスリー
ブ3の内端部は溶接部4を介して給水スパージヤ
5に接続されており、原子炉圧力容器の外側から
矢印a方向に沿つて流入する低温の冷却材が、こ
のノズルおよび給水スパージヤ5を経て、図示し
ない給水スパージヤノズルから圧力容器内に注入
されるようになつている。しかして、通常圧力容
器は高温(沸騰水型原子炉の場合約300℃)で冷
却材は低温(沸騰水型原子炉の給水温度は200
℃)であるから、ノズルはこのような温度差に対
処できるように、ノズル本体2とサーマルスリー
ブ3との間に隙間gを保つて後者を前者に緩挿す
るようにしている。そのため、給水スパージヤ5
の流体圧力と圧力容器内の圧力との差圧により、
上記隙間gを通つてサーマルスリーブ3の外側を
流れる漏流Lが生じ、この漏流Lは主にノズル本
体2の内側コーナ部Cを局部的に冷却することに
なる。この漏流Lは上記内側コーナ部に熱応力を
発生させ、この部分にクラツクを生じさせる恐れ
がある。
A conventional water supply nozzle for a reactor pressure vessel, as shown in FIG. It has a fitted thermal sleeve 3. The inner end of this thermal sleeve 3 is connected to a water supply spargeer 5 via a weld 4, and the low-temperature coolant flowing from the outside of the reactor pressure vessel in the direction of arrow a flows through this nozzle and water supply spargeer. 5, and is injected into the pressure vessel from a water supply sparge nozzle (not shown). Normally, the pressure vessel is at a high temperature (approximately 300°C in the case of a boiling water reactor) and the coolant is at a low temperature (the feed water temperature in a boiling water reactor is approximately 200°C).
C), so that the nozzle can cope with such a temperature difference by maintaining a gap g between the nozzle body 2 and the thermal sleeve 3 so that the latter is loosely inserted into the former. Therefore, the water supply spargeer 5
Due to the differential pressure between the fluid pressure of and the pressure inside the pressure vessel,
A leakage flow L flows outside the thermal sleeve 3 through the gap g, and this leakage flow L mainly locally cools the inner corner C of the nozzle body 2. This leakage flow L generates thermal stress in the inner corner portion, which may cause a crack in this portion.

そこで、本発明の目的は、上記した不都合を解
消し、ノズル本体の内側コーナ部におけるクラツ
クの発生を防止し得るノズルを提供するにある。
SUMMARY OF THE INVENTION Therefore, an object of the present invention is to provide a nozzle which can eliminate the above-mentioned disadvantages and prevent cracks from occurring at the inner corner portions of the nozzle body.

以下、本発明の実施例を第2図および第3図を
参照して説明する。
Embodiments of the present invention will be described below with reference to FIGS. 2 and 3.

第2図において符号6は中間スリーブを示し、
この中間スリーブ6はノズル本体2の内筒部に装
着されている。中間スリーブ6の外端は例えば隅
肉溶接等の結合手段により、ノズル本体2の内周
面開口端縁付近に一体的に接合されている。ま
た、中間スリーブの内端部は、圧力容器の胴部1
の内面より内側に突出している。
In FIG. 2, reference numeral 6 indicates an intermediate sleeve;
This intermediate sleeve 6 is attached to the inner cylindrical portion of the nozzle body 2. The outer end of the intermediate sleeve 6 is integrally joined to the inner peripheral surface of the nozzle body 2 near the opening edge by a joining means such as fillet welding. Moreover, the inner end of the intermediate sleeve is connected to the body 1 of the pressure vessel.
protrudes inward from the inner surface of

上記中間スリーブ6の内筒部には、所要の隙間
gを介して、前記サーマルスリーブ3が緩挿され
ている。
The thermal sleeve 3 is loosely inserted into the inner cylindrical portion of the intermediate sleeve 6 through a required gap g.

本発明によれば、このサーマルスリーブ3と上
記中間スリーブ6とを同種の材料例えばステンレ
ス鋼で製造することが重要であり、それによつ
て、金属電位差に基づく腐食の増進を防ぐことが
できる。
According to the invention, it is important that this thermal sleeve 3 and the intermediate sleeve 6 are made of the same type of material, for example stainless steel, so as to prevent increased corrosion due to metal potential differences.

なお、第2図において第1図と同符号を付した
部分は、第1図と均等な部分を示す。
In addition, in FIG. 2, parts given the same reference numerals as in FIG. 1 indicate the same parts as in FIG. 1.

上記のように構成された本発明の一実施例によ
るノズルは、中間スリーブ6の外端がノズル本体
2の内周面開口端縁付近に一体的に接合されてい
るため、本体ノズル2の内面側には冷却材が流入
しない。ただし、ノズル本体2の外端開口部から
冷却材が流入したとき、前記した理由によりサー
マルスリーブ3と中間スリーブ6との間に漏流L
が発生する。しかしながら、この漏流Lは、中間
スリーブ6の内筒部を樋にして圧力容器の胴部1
の内面より内方に導かれ、中間スリーブ6の内端
縁から落下するから、ノズル本体の内側コーナ部
Cに触れることはない。
In the nozzle according to the embodiment of the present invention configured as described above, the outer end of the intermediate sleeve 6 is integrally joined to the vicinity of the opening edge of the inner peripheral surface of the nozzle main body 2, so that the inner surface of the main nozzle 2 No coolant flows into the side. However, when the coolant flows in from the outer end opening of the nozzle body 2, there is a leakage L between the thermal sleeve 3 and the intermediate sleeve 6 due to the above-mentioned reason.
occurs. However, this leakage L flows through the body part 1 of the pressure vessel using the inner cylindrical part of the intermediate sleeve 6 as a gutter.
Since it is guided inward from the inner surface of the intermediate sleeve 6 and falls from the inner edge of the intermediate sleeve 6, it does not touch the inner corner C of the nozzle body.

第3図は本発明の変形実施例を示し、この実施
例は、中間スリーブ6の内端にフランジ7を設け
ると共に、サーマルスリーブ3の内端部に、つば
部8を例えば溶接によつて一体的に着設し、これ
らフランジ7とつば部8とをOリング9を介して
相互に結合したもので、このようにすると、サー
マルスリーブ3と中間スリーブ6との間に漏出し
た冷却材が、つば部8、フランジ7およびOリン
グ9によつて封止され、冷却材がノズル本体の内
側コーナ部Cに触れないことは勿論のこと、圧力
容器内に漏流が流入しないという別の効果があ
る。
FIG. 3 shows a modified embodiment of the present invention, in which a flange 7 is provided at the inner end of the intermediate sleeve 6, and a collar 8 is integrated with the inner end of the thermal sleeve 3, for example by welding. The flange 7 and the collar 8 are connected to each other via an O-ring 9. In this way, the coolant leaking between the thermal sleeve 3 and the intermediate sleeve 6 is It is sealed by the collar 8, flange 7, and O-ring 9, which not only prevents the coolant from touching the inner corner C of the nozzle body, but also has another effect of preventing leakage from flowing into the pressure vessel. be.

以上の説明から明らかなように、本発明は、ノ
ズル本体のノズル孔内に中間スリーブを装着し、
中間スリーブの内端を圧力容器の胴部内面よ内側
に突出出させたので、中間スリーブとこれに緩挿
されたサーマルスリーブとの隙間から圧力容器内
に流入する漏流がノズル本体の内側コーナ部に触
れることは皆無となる。従つて、この部分におけ
る熱応力クラツクの発生は防止され、圧力容器の
安全性が向上する。
As is clear from the above description, the present invention includes installing an intermediate sleeve in the nozzle hole of the nozzle body,
Since the inner end of the intermediate sleeve protrudes inward from the inner surface of the body of the pressure vessel, leakage flowing into the pressure vessel through the gap between the intermediate sleeve and the thermal sleeve loosely inserted into the intermediate sleeve is caused to leak into the inner corner of the nozzle body. There will be no touching of the parts. Therefore, thermal stress cracks are prevented from occurring in this portion, improving the safety of the pressure vessel.

また、サーマルスリーブと中間スリーブとの間
にシール隙間を形成し、両者を同一の材料で構成
したから、金属電位差による腐食の増進を抑制す
ることができるし、また、中間スリーブの入口端
をノズルの孔壁に溶接結合したので溶接作業が容
易なことはもちろん、溶接部の放射線透視検査が
容易となる。
In addition, since a seal gap is formed between the thermal sleeve and the intermediate sleeve, and both are made of the same material, it is possible to suppress corrosion caused by metal potential difference. Since it is welded to the hole wall, not only the welding work is easy, but also radiographic inspection of the welded part is easy.

また、ノズル本体の内側コーナ部の補修等が不
要となるので、プラントの稼動率が向上する他、
補修作業員の放射線被ばく量の低減が期待でき
る、など種々の効果を奏する。
In addition, there is no need to repair the inner corner of the nozzle body, which improves the plant's operating rate.
It has various effects, including a reduction in radiation exposure for repair workers.

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

第1図は従来のノズルの構造の一例を示す断面
図、第2図は本発明の一実施例によるノズルの断
面図、第3図は本発明の変形実施例によるノズル
の断面図である。 1…胴部、2…ノズル本体、3…サーマルスリ
ーブ、5…給水スパージヤ、6…中間スリーブ、
7…フランジ、8…つば部、9…Oリング、C…
コーナ部、L…漏流。
FIG. 1 is a cross-sectional view showing an example of the structure of a conventional nozzle, FIG. 2 is a cross-sectional view of a nozzle according to an embodiment of the present invention, and FIG. 3 is a cross-sectional view of a nozzle according to a modified embodiment of the present invention. DESCRIPTION OF SYMBOLS 1...Body part, 2...Nozzle body, 3...Thermal sleeve, 5...Water supply spargeer, 6...Intermediate sleeve,
7...Flange, 8...Brim, 9...O-ring, C...
Corner part, L...Leakage.

Claims (1)

【特許請求の範囲】 1 原子炉圧力容器の胴部に一体に形成された筒
状のノズル本体と、このノズル本体のノズル孔内
に挿入された入口端をノズル孔壁に溶接結合され
た中間スリーブと、この中間スリーブの孔内に緩
挿され、内端が給水スパージヤに接続されたサー
マルスリーブとからなり、上記中間スリーブとサ
ーマルスリーブとを同一の材料で構成すると共
に、上記中間スリーブの孔壁とサーマルスリーブ
の入口端の外周面との間にシール間隙を形成し、
さらに中間スリーブの内端部を原子炉圧力容器の
胴部内面より内方へ突出させたことを特徴とする
ノズル。 2 中間スリーブの内端にフランジを形成すると
共に、サーマルスリーブの内端部につば部を一体
的に形成し、これらのフランジとつば部とをOリ
ングを介して相互に結合したことを特徴とする特
許請求の範囲第1項に記載のノズル。
[Scope of Claims] 1. A cylindrical nozzle body integrally formed in the body of the reactor pressure vessel, and an intermediate part in which the inlet end inserted into the nozzle hole of this nozzle body is welded to the nozzle hole wall. It consists of a sleeve and a thermal sleeve that is loosely inserted into the hole of the intermediate sleeve and whose inner end is connected to the water supply spargeer. forming a sealing gap between the wall and the outer peripheral surface of the inlet end of the thermal sleeve;
Furthermore, the nozzle is characterized in that the inner end of the intermediate sleeve projects inward from the inner surface of the trunk of the reactor pressure vessel. 2. A flange is formed at the inner end of the intermediate sleeve, a flange is integrally formed at the inner end of the thermal sleeve, and the flange and the flange are connected to each other via an O-ring. A nozzle according to claim 1.
JP9189179A 1979-07-19 1979-07-19 Nozzle Granted JPS5614998A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9189179A JPS5614998A (en) 1979-07-19 1979-07-19 Nozzle

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9189179A JPS5614998A (en) 1979-07-19 1979-07-19 Nozzle

Publications (2)

Publication Number Publication Date
JPS5614998A JPS5614998A (en) 1981-02-13
JPS6118157B2 true JPS6118157B2 (en) 1986-05-10

Family

ID=14039173

Family Applications (1)

Application Number Title Priority Date Filing Date
JP9189179A Granted JPS5614998A (en) 1979-07-19 1979-07-19 Nozzle

Country Status (1)

Country Link
JP (1) JPS5614998A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0771796B2 (en) * 1988-06-25 1995-08-02 レンゴー株式会社 Tool positioning method
US6345084B1 (en) * 1999-11-19 2002-02-05 General Electric Company Apparatus and methods for replacing a core spray T-box/thermal sleeve in a nuclear reactor
JP5859344B2 (en) * 2012-03-05 2016-02-10 三菱重工業株式会社 Thermal sleeve repair method

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5430198B2 (en) * 1972-11-15 1979-09-28

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 (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5430198B2 (en) * 1972-11-15 1979-09-28

Also Published As

Publication number Publication date
JPS5614998A (en) 1981-02-13

Similar Documents

Publication Publication Date Title
US5345484A (en) Feedwater nozzle and method of repair
JPS6118157B2 (en)
JPH1010270A (en) Thermal sleeve of water feed nozzle
GB2156463A (en) Pipe junction-internal insulation
US2450173A (en) Seal for tank openings
JPS589867B2 (en) pressure vessel
US4062726A (en) Nozzle seal
JPH0139077B2 (en)
JP2774166B2 (en) Cooling device
US2849389A (en) Corrosion resistant jacketed metal body
CN217900607U (en) Heat exchanger structure with pipe pass without welding
JPS6148790A (en) Leakage countermeasure treater for housing section
CN217784371U (en) Corrugated pipe stop valve with corrugated pipe protection
JPH018792Y2 (en)
JPS6039994U (en) Pressure tube lower sealing device for pressure tube reactor
JP2008089487A (en) Radioactive substance containing cask and repair method therefor
JPS58156Y2 (en) Shielding structure of reactor shielding wall opening
JPS6180094A (en) Wedling thermal sleeve
JPS628000B2 (en)
JPH066983U (en) Structure of diaphragm part of pressure vessel
JPS59100895A (en) Nozzle
JPS60228995A (en) Nozzle for pressure vessel of nuclear reactor
JPS6025541Y2 (en) electromagnetic flowmeter detector
JPH0285696A (en) Connecting construction for double heat exchanger tube and tube plate
JP2804787B2 (en) Method of assembling reactor pressure vessel with main steam flow nozzle