JPH02210296A - Method and structure for repairing long-sized housing - Google Patents
Method and structure for repairing long-sized housingInfo
- Publication number
- JPH02210296A JPH02210296A JP1031920A JP3192089A JPH02210296A JP H02210296 A JPH02210296 A JP H02210296A JP 1031920 A JP1031920 A JP 1031920A JP 3192089 A JP3192089 A JP 3192089A JP H02210296 A JPH02210296 A JP H02210296A
- Authority
- JP
- Japan
- Prior art keywords
- housing
- repair
- sleeve
- neutron flux
- long
- 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
Links
- 238000000034 method Methods 0.000 title claims description 41
- 230000008439 repair process Effects 0.000 claims abstract description 112
- 230000004907 flux Effects 0.000 claims abstract description 106
- 230000007547 defect Effects 0.000 claims abstract description 29
- 230000002950 deficient Effects 0.000 claims abstract description 27
- 238000003466 welding Methods 0.000 claims abstract description 20
- 238000003780 insertion Methods 0.000 claims abstract description 8
- 230000037431 insertion Effects 0.000 claims abstract description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 36
- 238000007789 sealing Methods 0.000 abstract description 6
- 230000002093 peripheral effect Effects 0.000 abstract description 5
- 230000000903 blocking effect Effects 0.000 abstract description 2
- 230000000149 penetrating effect Effects 0.000 description 8
- 230000007797 corrosion Effects 0.000 description 7
- 238000005260 corrosion Methods 0.000 description 7
- 238000005336 cracking Methods 0.000 description 7
- 229910000679 solder Inorganic materials 0.000 description 7
- 238000010438 heat treatment Methods 0.000 description 6
- 238000009835 boiling Methods 0.000 description 5
- 238000010586 diagram Methods 0.000 description 5
- 239000010931 gold Substances 0.000 description 5
- 229910052737 gold Inorganic materials 0.000 description 5
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 230000007246 mechanism Effects 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 230000004927 fusion Effects 0.000 description 3
- 229910001026 inconel Inorganic materials 0.000 description 3
- 238000009434 installation Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 230000035515 penetration Effects 0.000 description 2
- 230000002265 prevention Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- 206010067482 No adverse event Diseases 0.000 description 1
- 206010070834 Sensitisation Diseases 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 1
- 238000005219 brazing Methods 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 150000002343 gold Chemical class 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000007935 neutral effect Effects 0.000 description 1
- 238000009659 non-destructive testing Methods 0.000 description 1
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000002250 progressing effect Effects 0.000 description 1
- 230000008313 sensitization Effects 0.000 description 1
- 238000005482 strain hardening Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
(産業上の利用分野)
本発明は原子炉容器に固定支持される中性子束モニタハ
ウジング等の長尺ハウジングの補修方法およびその補修
構造に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a repair method and a repair structure for a long housing such as a neutron flux monitor housing that is fixedly supported in a nuclear reactor vessel.
(従来の技術)
沸騰水型原子炉等の原子炉の出力は、中性子束に比例す
るので、原子炉の出力表示や燃焼度評価のために、原子
炉の中性子束を中性子束検出器(中性子束モニタ)にて
計測し、監視している。(Prior art) The output of a nuclear reactor such as a boiling water reactor is proportional to the neutron flux, so in order to display the reactor output and evaluate the burnup, the neutron flux of the reactor is measured using a neutron flux detector (neutron flux detector). It is measured and monitored using a bundle monitor.
中性子束検出器1は沸騰水型原子炉へ第9図に概略的に
示すように設けられる。原子炉圧力容器2内には炉心3
が破線で示すように収容される。A neutron flux detector 1 is installed in a boiling water nuclear reactor as schematically shown in FIG. There is a reactor core 3 inside the reactor pressure vessel 2.
is accommodated as shown by the broken line.
この炉心3に中性子検出器1が据付けられる。図示例で
は簡略化のために1本の中性子検出器1を据付けた例を
示す。A neutron detector 1 is installed in this core 3. In the illustrated example, one neutron detector 1 is installed for the sake of simplicity.
中性子検出器1の中性子束モニタ本体4は細長い長尺状
に形成され、その上端は炉心部の上部格子板5の下面支
持孔5aに弾力的に支持され、そ゛の下部は中性子束モ
ニタ案内管6および中性子束モニタハウジング(インコ
アモニタハウジング)7を介して下方に突出し1.その
下端は中性中性子束モニタランジ(インコアフランジ)
8に当接支持され、据付用の締付ナツト9により固定さ
れ丞。The neutron flux monitor main body 4 of the neutron detector 1 is formed into an elongated shape, and its upper end is elastically supported by the lower support hole 5a of the upper grid plate 5 of the reactor core, and its lower part is connected to the neutron flux monitor guide tube. 6 and protrudes downward through the neutron flux monitor housing (in-core monitor housing) 7.1. Its lower end is a neutral neutron flux monitor flange (in-core flange)
8 and is fixed by a tightening nut 9 for installation.
中性子束モニタハウジング7は上部が原子炉圧力容器2
の下鏡溶接部に溶接にて固定され、垂下状態に設けられ
る。中性子束モニタハウジング7は5LIS304等の
オーステナイト系ステンレス鋼管を使用しているので、
応力、腐食環境、材料(クロム欠乏層の生成)の3つの
条件が成立すると、原子炉圧力容器2との溶接部付近で
応力腐食割れ(以下、SCCという。)が発生するおそ
れがある。応力腐食割れは3条件のうち1つでも欠落す
れば発生しないので、この応力腐食割れ防止のために、
種々の対策が講じられている。The upper part of the neutron flux monitor housing 7 is the reactor pressure vessel 2
It is fixed by welding to the lower mirror welding part and is placed in a hanging state. Since the neutron flux monitor housing 7 uses an austenitic stainless steel tube such as 5LIS304,
If the three conditions of stress, corrosive environment, and material (creation of a chromium-deficient layer) are satisfied, stress corrosion cracking (hereinafter referred to as SCC) may occur near the weld to the reactor pressure vessel 2. Stress corrosion cracking will not occur if even one of the three conditions is missing, so to prevent stress corrosion cracking,
Various measures are being taken.
(発明が解決しようとする課題)
中性子束モニタハウジング7を固定支持する原子炉圧力
容器2の溶接部付近に例えば粒界応力腐食割れ(IGS
CC)が生じたり、あるいは溶接時の融合不良に伴う溶
接欠陥が生じたり、または中性子束モニタハウジング自
身の欠陥により、溶接部付近の中性子束モニタハウジン
グに割れが生じ、この割れがハウジング貫通性欠陥に進
展すると炉水リークに発展するおそれがある。(Problems to be Solved by the Invention) For example, intergranular stress corrosion cracking (IGS) occurs near the welded part of the reactor pressure vessel 2 that fixedly supports the neutron flux monitor housing 7.
CC) occurs, or a welding defect occurs due to poor fusion during welding, or a crack occurs in the neutron flux monitor housing near the weld due to a defect in the neutron flux monitor housing itself, and this crack is a housing penetrating defect. If this progresses, there is a risk that it will develop into a reactor water leak.
一方、炉心部の中性子束を計測し、監視する中性子束検
出器は、原子炉の出力l!1lIIlや炉運転停止を行
なうυ制御棒駆動機構と異なり、原子炉の安全系に属さ
ないため、中性子束モニタハウジングのシール支持構造
は原子炉安全系を前提としたものではなく、また、原子
炉圧力容器との溶接部付近に中性子束モニタハウジング
自身の貫通性欠陥が万−生じた場合、炉水漏洩に対する
恒久的な補修工法やシール支持構造は未確立であった。On the other hand, the neutron flux detector that measures and monitors the neutron flux in the reactor core measures the reactor's output l! Unlike the υ control rod drive mechanism that shuts down reactor operation, the seal support structure of the neutron flux monitor housing is not intended for the reactor safety system, as it does not belong to the reactor safety system. In the event that a penetration defect occurs in the neutron flux monitor housing itself near the weld to the pressure vessel, no permanent repair method or seal support structure has been established to prevent reactor water leakage.
本発明は上述した事情を考慮してなされたもので、中性
子束モニダハウジング等の長尺ハウジングの溶接部付近
の欠陥部からの炉水リークを確実かつ迅速に防止でき、
欠陥部の進展も抑制できる恒久的な長尺ハウジングの補
修方法およびその補修構造を提供することを目的とする
。The present invention has been made in consideration of the above-mentioned circumstances, and is capable of reliably and quickly preventing leakage of reactor water from defective parts near the welds of elongated housings such as neutron flux monitor housings.
It is an object of the present invention to provide a permanent method for repairing a long housing and a structure for repairing the same, which can also suppress the growth of defective parts.
〔発明の構成)
(課題を解決するための手段)
本発明に係る長尺ハウジングの補修方法は、上述した課
題を解決するために、原子炉容器の溶接部に固定された
中性子束モニタハウジング等の長尺ハウジングに補修ス
リーブを挿入し、挿入された補修スリーブで長尺ハウジ
ングの欠陥発生部を内側から覆うように塞ぎ、この閉塞
位置で前記補修スリーブを長尺ハウジングに固着する方
法である。[Structure of the Invention] (Means for Solving the Problems) In order to solve the above-mentioned problems, a method for repairing a long housing according to the present invention provides a method for repairing a neutron flux monitor housing, etc. fixed to a welded part of a reactor vessel. In this method, a repair sleeve is inserted into the elongated housing, the inserted repair sleeve covers and closes the defective part of the elongated housing from the inside, and the repair sleeve is fixed to the elongated housing at this closed position.
また、上述した課題を解決するために、本発明に係る長
尺ハウジングの補修方法は原子炉容器の下鏡溶接部に固
定された中性子束モニタハウジング等の長尺ハウジング
を、原子炉容器の貫通孔にその挿通位置で拡管させてシ
ール固着する一方、上記長尺ハウジング内に補修スリー
ブを挿入し、挿入された補修スリーブで長尺ハウジング
の欠陥発生部を内側から覆うように塞ぎ、この閉塞位置
で前記補修スリーブを長尺ハウジングに固着する方法で
ある。In addition, in order to solve the above-mentioned problems, the long housing repair method according to the present invention is a method for repairing a long housing such as a neutron flux monitor housing fixed to the lower mirror welding part of the reactor vessel. While the hole is expanded and sealed at the insertion position, a repair sleeve is inserted into the long housing, and the inserted repair sleeve covers and closes the defective part of the long housing from the inside, and the closed position In this method, the repair sleeve is fixed to the elongated housing.
さらに、本発明に係る長尺ハウジングの補修構造は、上
述した課題を解決するために、原子炉容器の溶接部に固
着された中性子束モニタハウジング等の長尺ハウジング
に、そのハウジング欠陥発生部を内側から塞ぐように補
修スリーブを内挿し、その閉塞位置で補修スリーブを長
尺ハウジングに固着したものである。Furthermore, in order to solve the above-mentioned problem, the elongated housing repair structure according to the present invention repairs the defective part of the elongated housing such as the neutron flux monitor housing fixed to the welded part of the reactor vessel. A repair sleeve is inserted so as to close it from the inside, and the repair sleeve is fixed to the elongated housing at the closed position.
さらにまた、本発明に係る長尺ハウジングの補修構造は
、上述した課題を解決するために、原子炉容器の貫通孔
内を通り、その下鏡溶接部に固定された中性子束モニタ
ハウジング等の長尺ハウジングを、前記貫通孔挿通位置
で拡管させてシール固着させる一方、前記長尺ハウジン
グに、そのハウジング欠陥発生部を内側から塞ぐように
補修スリーブを内挿し、その閉塞位置で補修スリーブを
長尺ハウジングに固着したものである。Furthermore, in order to solve the above-mentioned problems, the repair structure for a long housing according to the present invention provides a long housing such as a neutron flux monitor housing that passes through the through hole of the reactor vessel and is fixed to the welded portion of the lower mirror. The long housing is expanded and sealed at the through-hole insertion position, and a repair sleeve is inserted into the long housing so as to close the defective part of the housing from the inside, and the repair sleeve is inserted into the long housing at the closed position. It is fixed to the housing.
(作用)
この長尺ハウジングの補修方法およびその補修構造は、
原子炉の運転中に中性子束モニタハウジング等の長尺ハ
ウジング自身に貫通性の欠陥が生じた場合に、この欠陥
発生位置を、長尺ハウジング内に内挿される補修スリー
ブで内側、から塞ぎ、この閉塞位置で補修スリーブを長
尺ハウジングに固着させることにより、長尺ハウジング
の欠陥位置からの炉水リークを確実かつ迅速に防止でき
、炉水環境と隔離して欠陥部の進展も抑制できる。(Function) The repair method and structure of this long housing are as follows:
If a penetrating defect occurs in the elongated housing itself, such as the neutron flux monitor housing, during operation of the nuclear reactor, the defect location is sealed from the inside with a repair sleeve inserted into the elongated housing. By fixing the repair sleeve to the elongated housing at the closed position, leakage of reactor water from the defective position of the elongated housing can be reliably and quickly prevented, and the progress of the defective part can also be suppressed by isolating it from the reactor water environment.
また、原子炉容器の貫通孔に挿通される長尺ハウジング
を、その挿通位置で拡管させて貫通孔にシール固着させ
ると、長尺ハウジングは内挿される補修スリ−ブととも
もに二重のシール構造とすることができ、炉水リークを
確実に防止し、恒久的なシール対策を施すことができる
。In addition, when a long housing inserted into a through-hole in a reactor vessel is expanded at the insertion position and sealed and fixed in the through-hole, the long housing and the repair sleeve inserted into the through-hole are double-sided. It can have a sealing structure, reliably prevent reactor water leaks, and provide permanent sealing measures.
(実施例)
以下、本発明の一実施例について添付図面を参照して説
明する。(Example) Hereinafter, an example of the present invention will be described with reference to the accompanying drawings.
沸騰水型原子炉は、第2図に示すように原子炉容器とし
ての原子炉圧力容器10を備え、この原子炉圧力容器1
0はその支持ペデスタル11上に支持スカート12を介
して支持される。原子炉圧力容器10の下部(下鏡)に
は原子炉の炉心に制御棒(図示せず)の出し入れを行な
う制御棒駆動機構(CRD)13が多数本林立状態で垂
設される。制御棒駆動機構13のCRDハウジング14
は原子炉圧力容器10の下鏡に溶接にて固定される。こ
のCRDハウジング(長尺ハウジング)14には5US
304.5US3041等のステンレス鋼が用いられる
。As shown in FIG. 2, a boiling water reactor is equipped with a reactor pressure vessel 10 as a reactor vessel.
0 is supported on its support pedestal 11 via a support skirt 12. At the lower part (lower mirror) of the reactor pressure vessel 10, a large number of control rod drive mechanisms (CRD) 13 are installed vertically in a stand-alone manner for moving control rods (not shown) in and out of the reactor core. CRD housing 14 of control rod drive mechanism 13
is fixed to the lower mirror of the reactor pressure vessel 10 by welding. This CRD housing (long housing) 14 has 5US
Stainless steel such as 304.5 US 3041 is used.
また、原子炉の出力表示や燃焼度の評価のために、原子
炉炉心部で発生する中性子束は中性子束検出器15にて
測定され、監視される。中性子束検出器15は各CHD
13間の適宜空間に配置され、細長い長尺状の中性子束
モニタ本体16を第3図に示すように有する。Further, in order to display the output of the nuclear reactor and evaluate the burnup, the neutron flux generated in the core of the nuclear reactor is measured and monitored by the neutron flux detector 15. The neutron flux detector 15 is connected to each CHD.
As shown in FIG. 3, the main body 16 of the neutron flux monitor has an elongated shape and is disposed in an appropriate space between the monitors 13 and 13.
中性子束モニタ本体16はv8長い管状をなし、その下
部側は長尺ハウジングである中性子束七二タ案内管17
や中性子束モニタハウジング(インコアモニタハウジン
グ)18を通って下方に延びており、その下端部は中性
子束モニタ7ランジ19の内周肩部に当接支持される。The neutron flux monitor main body 16 has a V8 long tubular shape, and the lower side thereof has a neutron flux 72 guide tube 17 which is a long housing.
It extends downward through the neutron flux monitor housing (in-core monitor housing) 18, and its lower end portion is abutted and supported by the inner peripheral shoulder portion of the neutron flux monitor 7 flange 19.
この中性子束モニタフランジ19は中性子束モニタハウ
ジング18の下端外周7ランジ18aに締付ボルト20
により固定される。中性子束モニタフランジ19により
支持された中性子束モニタ本体16はインコアナツト(
据付用締付ナツトでもよい。)21により固定される。This neutron flux monitor flange 19 is attached to the lower end outer circumference 7 flange 18a of the neutron flux monitor housing 18 with a tightening bolt 20.
Fixed by The neutron flux monitor main body 16 supported by the neutron flux monitor flange 19 is an in-core nut (
An installation tightening nut may also be used. )21.
一方、中性子束モニタ本体16を挿通させた中性子束モ
ニタハウジング18は5LIS304.5LIS304
L、5US316L等のステンレス鋼が用いられ、こ
の中性子束モニタハウジング18の上部は第4図に示す
ように、炭素鋼を母材とする原子炉圧力容器10の貫通
孔23内を通されて原子炉圧力容器10の内側から溶接
により固定される。On the other hand, the neutron flux monitor housing 18 into which the neutron flux monitor main body 16 is inserted is 5LIS304.5LIS304.
As shown in FIG. 4, the upper part of the neutron flux monitor housing 18 is passed through the through hole 23 of the reactor pressure vessel 10 whose base material is carbon steel. It is fixed by welding from the inside of the furnace pressure vessel 10.
具体的には、原子炉圧力容器10の内側はステンレス肉
盛部24が溶接にて形成され、鏡面仕上げされる。貫通
孔部23の傾斜側には開先を取ってインコネル182等
で溶接し、管台25を形成する。この管台25の頂部に
開先部を形成し、この開先部をインコネル82やNbに
オブ)入りのインコネル182等で溶接し、この溶接部
26を介して中性子束モニタハウジング(長尺ハウジン
グ)18を管台25に固定させ、シールさせる。Specifically, a stainless steel overlay 24 is formed by welding on the inside of the reactor pressure vessel 10, and is mirror-finished. The inclined side of the through hole portion 23 is beveled and welded with Inconel 182 or the like to form the nozzle stub 25. A groove is formed at the top of this nozzle stub 25, and this groove is welded with Inconel 82, Inconel 182 containing Nb, etc., and the neutron flux monitor housing (long housing ) 18 is fixed to the nozzle stand 25 and sealed.
管台25の溶接部26により原子炉圧力容器10内を下
方のプレッシャバウンダリ27から区画し炉水環境から
隔離している。The welded portion 26 of the nozzle stub 25 separates the inside of the reactor pressure vessel 10 from the lower pressure boundary 27 and isolates it from the reactor water environment.
一方、長尺ハウジングである中性子束モニタハウジング
18やCRDハウジング14はステンレス鋼(StJS
鋼)で形成されているため、応力腐食割れの3条件が成
立すると、原子炉圧力容器10との溶接部分で応力腐食
割れが発生するおそれがある。この応力腐食割れ(SC
C)が生じたり、ハウジング自身の欠陥により長尺ハウ
ジングに貫通性の欠陥が生じたり、溶接時の融合不良に
伴う溶接欠陥などによりクラックが生じ、このクラック
が成長して大きくなると原子炉圧力容器10内の炉水が
長尺ハウジングの貫通性欠陥発生部を通って原子炉圧力
容器外にリークするおそれがある。On the other hand, the neutron flux monitor housing 18 and CRD housing 14, which are long housings, are made of stainless steel (StJS
If the three conditions for stress corrosion cracking are satisfied, stress corrosion cracking may occur at the welded portion with the reactor pressure vessel 10. This stress corrosion cracking (SC)
C) occurs, a penetrating defect occurs in the long housing due to a defect in the housing itself, a crack occurs due to a welding defect due to poor fusion during welding, and if this crack grows and becomes larger, it may damage the reactor pressure vessel. There is a risk that the reactor water in the reactor 10 may leak out of the reactor pressure vessel through the penetrating defect occurring portion of the elongated housing.
この炉水リークは種々の検出器で監視され、また、定期
検査時に検査され、検出される。炉水リークが検出され
るとリーク防止対策が施され、次の補修方法により欠陥
部は修復され、炉水リークは確実かつ恒久的に防止され
る。This reactor water leak is monitored by various detectors, and is also inspected and detected during periodic inspections. When a reactor water leak is detected, leak prevention measures are taken, and the defective part is repaired using the following repair method, and reactor water leaks are reliably and permanently prevented.
第1図(A)ないしくD)は中性子束モニタハウジング
の補修方法およびその補修構造の一例を示すものである
。FIGS. 1A to 1D show an example of a method for repairing a neutron flux monitor housing and a structure for repairing the same.
この補修方法を行なう場合には、中性子束モニタハウジ
ング18から中性子検出器15を上方に引き抜いて取り
除く一方、中性子束モニタハウジング18の溶接部上方
〈中性子束モニタ案内管17でもよい。)をボアプラグ
等の水栓でシールする。When performing this repair method, the neutron detector 15 is pulled upward from the neutron flux monitor housing 18 and removed, while the neutron flux monitor guide tube 17 may be placed above the welded portion of the neutron flux monitor housing 18. ) with a water faucet such as a bore plug.
次に、中性子束モニタハウジング18を原子炉圧力容器
の貫通孔23挿通位置で図示しないハウジング拡管機で
遠隔操作により第1図(A)に示すように拡管し、貫通
孔23の内周壁面に圧着させ、シール固着させる。中性
子束モニタハウジング18の拡管状態は寸法測定機(図
示せず)により測定される。この中性子束モニタハウジ
ング18の拡管作業の後(拡管作業の開始前でもよい。Next, the neutron flux monitor housing 18 is expanded at a position where the through hole 23 of the reactor pressure vessel is inserted, as shown in FIG. Crimp and secure the seal. The expanded state of the neutron flux monitor housing 18 is measured by a dimension measuring machine (not shown). After the tube expansion operation of the neutron flux monitor housing 18 (or before the tube expansion operation is started).
)には、超音波探傷装置(UT装置)等の非破壊検査装
置をハウジング下方から挿入して貫通性欠陥発生位置を
調べ、特定する。), a non-destructive testing device such as an ultrasonic flaw detection device (UT device) is inserted from below the housing to investigate and identify the location where the penetrating defect occurs.
中性子束モニタハウジング18の拡管作業終了後に、遠
隔操作によるハウジング内面加工機やハウジング内面仕
上機(共に図示せず)を必要に応じ用いて、欠陥発生部
の周辺の内周面を所定の軸方向長さにわたってポーリン
グ加工し、第1図(B)に示すように内面研削する。After the tube expansion work of the neutron flux monitor housing 18 is completed, the inner circumferential surface around the defective area is polished in a predetermined axial direction using a remote-controlled housing inner surface processing machine or a housing inner surface finishing machine (both not shown) as necessary. Pauling is performed over the length, and the inner surface is ground as shown in FIG. 1(B).
中性子束モニタハウジング18の内面加工が終了した後
、薄肉の補修スリーブ30が内面被覆スリーブとして中
性子束モニタハウジング18内に挿入される。挿入され
た補修スリーブ30はハウジング欠陥部@31を内側か
ら覆うようにセットされる。補修スリーブ30には、S
CC対策を施した5tJS316L等のステンレス鋼が
用いられ、この補修スリーブ30は中性子束モニタハウ
ジング18の内径より小ざく、原子炉運転中の炉内圧に
充分に耐え得る肉厚、例えば2履程度、を有する。After the inner surface of the neutron flux monitor housing 18 is finished, the thin repair sleeve 30 is inserted into the neutron flux monitor housing 18 as an inner coating sleeve. The inserted repair sleeve 30 is set so as to cover the housing defect part @31 from the inside. The repair sleeve 30 has S
Stainless steel such as 5t JS316L with CC countermeasures is used, and the repair sleeve 30 has a wall thickness smaller than the inner diameter of the neutron flux monitor housing 18 and has a wall thickness of, for example, about 2 shoes, enough to withstand the pressure inside the reactor during reactor operation. has.
中性子束モニタハウジング18の欠陥位置31を覆うよ
うに内挿された補修スリーブ30は、エキスバンド装置
により冷間加工等で第1図(C)に示すように拡管され
てハウジング内周面に密着される。補修スリーブ30の
拡管率は、SCC対策を考慮し、残留応力が残らない程
度、例えば約10%程度以内に抑えられる。拡管された
補修スリーブ30は中性子検出器15の中性子束モニタ
本体16(例えば、外径34.1履φ)が挿通される内
径を有する。The repair sleeve 30 inserted so as to cover the defective position 31 of the neutron flux monitor housing 18 is expanded by cold working etc. using an expander as shown in FIG. be done. The expansion ratio of the repair sleeve 30 is suppressed to such an extent that residual stress does not remain, for example, within about 10%, taking SCC countermeasures into consideration. The expanded repair sleeve 30 has an inner diameter into which the neutron flux monitor main body 16 of the neutron detector 15 (for example, outer diameter 34.1 mm) is inserted.
中性子束モニタハウジング18の欠陥部31を覆う位置
で拡管され、ハウジング内周面にW!着された補修スリ
ーブ30は、続いてスリーブ溶接機により欠陥発生部の
上方および下方位置で周方向にアークシーム溶接(TI
Gフュージョン溶接)32され、ハウジング内周面に第
1図(D)に示すように固着される。中性子束モニタハ
ウジング18内に固着された補修スリーブ30はさらに
スリーブ上下端が全周にわたってシール溶接33され、
補修スリーブ30と中性子束モニタハウジング18の間
の隙間を炉水から隔離し、腐食環境を取り除いている。The tube is expanded at a position covering the defective part 31 of the neutron flux monitor housing 18, and the W! The applied repair sleeve 30 is then arc seam welded (TI) in the circumferential direction at positions above and below the defect occurrence area using a sleeve welding machine.
(G fusion welding) 32, and is fixed to the inner circumferential surface of the housing as shown in FIG. 1(D). The repair sleeve 30 fixed in the neutron flux monitor housing 18 is further sealed by welding 33 at the upper and lower ends of the sleeve over the entire circumference.
The gap between the repair sleeve 30 and the neutron flux monitor housing 18 is isolated from reactor water to eliminate a corrosive environment.
これにより、炉水の漏洩は防止され、さらに中性子束モ
ニタハウジング18の欠陥部をか水より隔離することが
でき、欠陥の新たな進展を有効に防止することができる
。第1図(D)は炉水り一り対策が施された長尺ハウジ
ングの補修構造である。Thereby, leakage of reactor water is prevented, and furthermore, the defective portion of the neutron flux monitor housing 18 can be isolated from the water, and further development of the defect can be effectively prevented. FIG. 1(D) shows a repair structure for a long housing that takes measures against reactor water.
補修スリーブ30が中性子束モニタハウジング18内の
所定位置に固着された後、寸法測定機によりスリーブ内
径寸法が測定される一方、図示しない浸透探傷検査機(
PT装置)により補修スリーブ30の健全性などが確認
され、中性子束モニタハウジング18の補修作業が終了
する。After the repair sleeve 30 is fixed at a predetermined position within the neutron flux monitor housing 18, the inner diameter of the sleeve is measured by a dimension measuring machine, while a penetrant inspection machine (not shown) is used.
The soundness of the repair sleeve 30 is confirmed by the PT device), and the repair work of the neutron flux monitor housing 18 is completed.
この中性子束モニタハウジング18のM修作業を行なう
場合、次の点が炉水漏洩対策として考慮される。When carrying out the M repair work on the neutron flux monitor housing 18, the following points should be considered as measures against leakage of reactor water.
■原子炉圧力容器10の耐圧バウンダリに適用できる補
修工法であること。■It must be a repair method that can be applied to the pressure-resistant boundary of the reactor pressure vessel 10.
■中性子束モニタハウジングの欠陥指示部を除去するか
、欠陥の進展を防止すること。■Remove the defect indicator of the neutron flux monitor housing or prevent the defect from progressing.
■ハウジング欠陥部周辺からの漏洩を防止すること。■Prevent leakage from around housing defects.
■ハウジング欠陥部(中性子束モニタハウジング取付溶
接部)の鋭敏化領域の性状を悪化させないこと。■Do not worsen the properties of the sensitized area of the housing defect (neutron flux monitor housing attachment weld).
■技術基準に適合しないものでないこと。■It must not conform to technical standards.
これらの点を考慮して、中性子束モニタハウジング18
の補修作業が行なわれる。Considering these points, the neutron flux monitor housing 18
Repair work will be carried out.
この補修作業終了後に水栓を外し、中性子束モニタ本体
16を中性子束モニタハウジング18内に案内して、中
性子束モニタハウジング18に支持させ、固定させる。After this repair work is completed, the faucet is removed, and the neutron flux monitor main body 16 is guided into the neutron flux monitor housing 18, and is supported and fixed by the neutron flux monitor housing 18.
この場合、中性子束モニタハウジング18は、補修スリ
ーブ30により炉水リークが防止される一方、中性子束
モニタハウジング18は原子炉圧力容器貫通孔23に対
応する挿通位置で拡管されてシール固定されるので、二
重シール構造をとることができ、炉水リークを確実かつ
有効的に防止できる。In this case, the neutron flux monitor housing 18 is prevented from leaking reactor water by the repair sleeve 30, while the neutron flux monitor housing 18 is expanded and sealed at the insertion position corresponding to the reactor pressure vessel through hole 23. , a double seal structure can be adopted, and reactor water leakage can be reliably and effectively prevented.
次に、長尺ハウジングの補修方法において実施される中
性子束モニタハウジング18の拡管方法について、第5
図(A)および(B)を参照してより具体的に説明する
。Next, the fifth section describes the tube expansion method of the neutron flux monitor housing 18 carried out in the long housing repair method.
This will be explained more specifically with reference to FIGS. (A) and (B).
中性子束モニタハウジング18の拡管は、ハウジング拡
管機を用いて、段階的に行なわれ、初めに、第5図(A
)に示すようにハウジング上段34aが拡管され、次に
第5図(B)に示すようにハウジング下段34bが拡管
される。この場合、中性子束モニタハウジング18の拡
管によりこのハウジング18を原子炉圧力容器10の下
鏡貫通孔に圧着させ、シール固着させることができるが
、このシール固着をより良好にするために、貫通孔23
に予め図示しないラビリンス溝を穿設しておいてもよい
。The tube expansion of the neutron flux monitor housing 18 is carried out in stages using a housing tube expander.
), the upper housing 34a is expanded, and then the lower housing 34b is expanded, as shown in FIG. 5(B). In this case, by expanding the tube of the neutron flux monitor housing 18, the housing 18 can be crimped to the lower mirror through hole of the reactor pressure vessel 10, and a seal can be secured. 23
A labyrinth groove (not shown) may be bored in advance.
この中性子束モニタハウジング18の拡管方法の特徴は
、ハウジングだけでなく、ハウジング18と管台25の
溶接部26や管台25そのものにクラック等が発生して
も、このクラックにより炉水が原子炉圧力容器10外に
漏洩するのを防止でき、汎用性の大きな炉水リーク防止
対策となる。The feature of this tube expansion method for the neutron flux monitor housing 18 is that even if cracks occur not only in the housing, but also in the welded part 26 between the housing 18 and the nozzle stub 25, or the nozzle stub 25 itself, the cracks will cause the reactor water to flow into the reactor. It is possible to prevent leakage to the outside of the pressure vessel 10, providing a highly versatile reactor water leak prevention measure.
また、補修スリーブを中性子束モニタハウジング18内
に挿入して固着する補修方法は、第6図(A)ないしく
C)に示す施行手順で行なってもよい。Further, the repair method of inserting and fixing the repair sleeve into the neutron flux monitor housing 18 may be carried out by the procedure shown in FIGS. 6(A) to 6(C).
この補修方法は、中性子束モニタハウジング18を拡管
させて原子炉圧力容器10の下Mmm郡部密着固定させ
るハウジング拡管工程を省略したものである。This repair method omits the housing tube expansion step of expanding the neutron flux monitor housing 18 and tightly fixing it under the reactor pressure vessel 10 by Mmm.
他の補修手順は、第1図(A)に示される工程が省略さ
れるだけで、第6図<A)ないしく’C)は第1図(B
)ないしくD)にそれぞれ対応するので、同一符号を付
して説明を省略する。In other repair procedures, the process shown in Figure 1 (A) is simply omitted, and Figure 6<A) or 'C) is shown in Figure 1 (B).
) to D), respectively, so the same reference numerals are given and the explanation will be omitted.
第6図(A)〜(C)に示される長尺ハウジングの補修
方法におい一〇も、中性子束モニタハウジング18の貫
通性欠陥発生部位31に、ハウジング内径より小さく、
原子炉運転中の炉内圧に耐え得る厚さの補修スリーブ3
0を挿入し、ハウジング欠陥部31を塞ぐように内側か
ら補修スリーブ30を拡管させて中性子束モニタハウジ
ング18の内周面に密着させ、ハウジング欠陥部31を
塞ぐとともに、この閉塞により炉水環境と隔離させるよ
うになっている。さらに、補修スリーブ30のスリーブ
上下部をアークシーム溶接32により中性子束モニタハ
ウジング18に固着することで、欠陥部を炉水環境から
隔離でき、欠陥の進展を防止できる。In the method for repairing a long housing shown in FIGS. 6(A) to 6(C), the method for repairing a long housing is as follows:
Repair sleeve 3 thick enough to withstand reactor pressure during reactor operation
0 is inserted, and the repair sleeve 30 is expanded from the inside so as to close the housing defect 31, and is brought into close contact with the inner circumferential surface of the neutron flux monitor housing 18, thereby blocking the housing defect 31 and, due to this blockage, removing the reactor water environment. It is designed to be isolated. Furthermore, by fixing the upper and lower parts of the repair sleeve 30 to the neutron flux monitor housing 18 by arc seam welding 32, the defective part can be isolated from the reactor water environment, and the progress of the defect can be prevented.
次に、長尺ハウジングの補修方法の他の実施例を第7図
(A)ないしくC)を参照して説明する。Next, another embodiment of a method for repairing a long housing will be described with reference to FIGS. 7(A) to 7(C).
この実施例に示される長尺ハウジングの補修方法は、中
性子束モニタハウジング18内への補修スリーブ35の
取付けを余ろう36によって行なう補修方法である。The repair method for a long housing shown in this embodiment is a repair method in which a repair sleeve 35 is attached to the inside of the neutron flux monitor housing 18 using a surplus solder 36.
°この補修方法を行なう場合にも、中性子束モニタハウ
ジング18から中性子検出器15を上方に取り除き、ハ
ウジング上方をボアプラグ等の水栓で水止めした後、ハ
ウジング内面加工機やハウジング内面仕上機にて中性子
束モニタハウジング19の貫通性欠陥部周辺をポーリン
グ加工し、第7図(A>に示すように、内面仕上げする
。この内面仕上後に、ハウジング寸法測定機により、ハ
ウジング内寸法が計測される。°When performing this repair method, the neutron detector 15 is removed upward from the neutron flux monitor housing 18, and the upper part of the housing is sealed off with a water faucet such as a bore plug. The area around the penetrating defect in the neutron flux monitor housing 19 is polled, and the inner surface is finished as shown in FIG.
その後、中性子束モニタハウジング18内に薄肉形状の
補修スリーブ35を挿入する。補修スリーブ35の上下
端部にはろう材として金ろう36が周方向に塗布されて
いる。この金ろう36は補修スリーブ35に塗布する代
りに、ポーリング加工により内面仕上げされた貫通性欠
陥部の上方および下方に予め塗布しておいてもよい。Thereafter, the thin-walled repair sleeve 35 is inserted into the neutron flux monitor housing 18. Gold solder 36 is applied as a brazing material to the upper and lower ends of the repair sleeve 35 in the circumferential direction. Instead of applying this gold solder 36 to the repair sleeve 35, it may be applied in advance above and below the penetrating defect whose inner surface has been finished by poling.
しかして、中性子束モニタハウジング18内に挿入され
た補修スリーブ35はハウジング欠陥部を内側から塞ぐ
位置に位置決めされ、この位置決め後に、エキスバンド
装置により補修スリーブ35を第7図(B)に示すよう
に拡管させて中性子束モニタハウジング18の内周面に
圧着させ、密着させる。このとき、補修スリーブ35の
拡管率は、約10%程度以内であり、スリー7に残留応
力が残らない程度である。拡管された補修スリーブ35
の拡管状態は、スリーブ寸法測定機により測定される。Thus, the repair sleeve 35 inserted into the neutron flux monitor housing 18 is positioned at a position that closes the defective part of the housing from the inside, and after this positioning, the repair sleeve 35 is moved by the expander as shown in FIG. 7(B). The tube is expanded and crimped onto the inner circumferential surface of the neutron flux monitor housing 18 so as to be brought into close contact. At this time, the expansion ratio of the repair sleeve 35 is within about 10%, which is such that no residual stress remains in the sleeve 7. Expanded repair sleeve 35
The expanded state of the tube is measured using a sleeve dimension measuring machine.
中性子束モニタハウジング18内で拡管された補修スリ
ーブ35は、続いて、第7図(C)に示すように加熱コ
イル37にて加熱され、金ろう36を溶融させる。この
金ろう36の溶融により補修スリーブ35は中性子束モ
ニタハウジング18に固着される。この固着後に、加熱
コイル37を補修スリーブ35から取り除くことで、長
尺ハウジングの補修構造が構成され、補修作業が終了す
る。The repair sleeve 35 expanded within the neutron flux monitor housing 18 is then heated by a heating coil 37 to melt the solder metal 36 as shown in FIG. 7(C). The repair sleeve 35 is fixed to the neutron flux monitor housing 18 by melting the gold solder 36. After this fixation, the heating coil 37 is removed from the repair sleeve 35 to construct a repair structure for the elongated housing, and the repair work is completed.
この場合、金ろう36は化学的、物理的に安定な物質で
あるので、悪影響が生じることがないが、補修スリーブ
35を加熱することにより中性子束モニタハウジング1
8に固着させているため、加熱による材料の鋭敏化等を
充分に検討する必要がある。このように、補修スリーブ
35の取付けに加熱作用を必要とするため、この補修ス
リーブ35のスリーブ長は、第1図に示す補修スリーブ
30より長くなる。In this case, since the gold solder 36 is a chemically and physically stable substance, no adverse effects will occur, but by heating the repair sleeve 35, the neutron flux monitor housing 1
8, it is necessary to fully consider the sensitization of the material due to heating. As described above, since a heating action is required to attach the repair sleeve 35, the sleeve length of the repair sleeve 35 is longer than that of the repair sleeve 30 shown in FIG.
第8図(A)ないしくC)は長尺ハウジングの補修方法
のさらに他の実施例を示すものである。FIGS. 8(A) to 8(C) show still another embodiment of a method for repairing a long housing.
この実施例に示された補修方法は、中性子束モニタハウ
ジング18内に挿入された補修スリーブ30を遠隔レー
ザ溶接機にハウジング内周面に固着させたものである。In the repair method shown in this embodiment, a repair sleeve 30 inserted into the neutron flux monitor housing 18 is fixed to the inner peripheral surface of the housing using a remote laser welding machine.
この補修方法のうち、第8図(A)、(B)に示される
ものは、第7図(A)、(B)に示される補修方法と異
ならないので説明を省略プる。Among these repair methods, those shown in FIGS. 8(A) and (B) are the same as the repair methods shown in FIGS. 7(A) and (B), so the explanation thereof will be omitted.
一方、遠隔レープ溶接機により第8図(C)に示すよう
に、中性子束モニタハウジング18内で溶着された補修
スリーブ3oは、その固着後、8丁装置等の非破壊検査
装置により、取付状態が確認され、チエツクされて補修
作業が終了する。第8図(C)は、長尺ハウジングの補
修構造を示すものである。On the other hand, as shown in FIG. 8(C) using a remote rape welder, the repair sleeve 3o is welded inside the neutron flux monitor housing 18. is confirmed and checked, and the repair work is completed. FIG. 8(C) shows a repair structure for a long housing.
この場合にも、第6図に示したものと同様の作用効果を
奏する。In this case as well, the same effects as shown in FIG. 6 can be achieved.
なお、本発明の一実施例では、中性子束モニタハウジン
グの補修方法およびその補修構造につい説明したが、C
RDハウジングの場合も同様にして適用できる。さらに
、本発明は加圧水型原子炉(DWR)の蒸気発生器の一
次および二次冷却材仕切部に設けられる配管にも適用す
ることができる。In addition, in one embodiment of the present invention, the repair method and the repair structure of the neutron flux monitor housing have been explained.
The same can be applied to the case of RD housing. Furthermore, the present invention can also be applied to piping provided in the primary and secondary coolant partitions of a steam generator of a pressurized water reactor (DWR).
また、中性子束モニタハウジング等の長尺ハウジングの
支持構造は、原子炉建設当初から上記長尺ハウジングを
原子炉路容器の貫通部に拡管により圧着支持させ、溶接
部における支持とともに、二重シール構造で支持させて
もよい。In addition, the support structure for long housings such as neutron flux monitor housings is such that from the beginning of reactor construction, the long housings are crimped and supported at the penetration part of the reactor vessel by expanding pipes, and are supported at welded parts and have a double seal structure. It may be supported by
〔発明の効果〕
以上に述べたように本発明に係る中性子束モニタハウジ
ング等の長尺ハウジングの補修方法およびその補修構造
においては、原子炉の運転中に中性子束モニタハウジン
グ等の長尺ハウジング自身に貫通性の欠陥が万−生じて
も、この欠陥発生位置を、長尺ハウジング内に内挿され
る補修スリーブで内側から塞ぎ、この閉塞位置で補修ス
リーブを長尺ハウジングに固着させることにより、長尺
ハウジングの欠陥位置からの炉水リークを確実かつ迅速
に防止でき、欠陥部の進展も抑制できる。[Effects of the Invention] As described above, in the method for repairing a long housing such as a neutron flux monitor housing and its repair structure according to the present invention, the long housing itself such as a neutron flux monitor housing can be damaged during operation of a nuclear reactor. Even if a penetrating defect occurs in the long housing, the defect location can be closed from the inside with a repair sleeve inserted into the long housing, and the repair sleeve can be fixed to the long housing at this closed position. Reactor water leakage from defective positions in the housing can be reliably and quickly prevented, and the growth of the defective parts can also be suppressed.
さらに、比較的短時間の簡単な補修作業で確実な修理を
行なうことができ、被曝量を軽減させ、信頼性を向上さ
せることができる。Furthermore, reliable repair can be performed with simple repair work in a relatively short time, reducing radiation exposure and improving reliability.
また、原子炉容器の貫通孔に挿通される長尺ハウジング
を、その挿通位置で拡管させて、t1通孔にシール固着
させると、長尺ハウジングは内挿される補修スリーブと
とももに二重のシール構造とすることができ、炉水リー
クを確実に防止し、恒久的なシール対策を施すことがで
きる。In addition, when the long housing inserted into the through hole of the reactor vessel is expanded at the insertion position and sealed and fixed to the T1 through hole, the long housing and the repair sleeve inserted therein will double up. It can have a sealing structure, reliably prevent reactor water leaks, and provide permanent sealing measures.
第1図(A>ないしくD)は本発明に係る長尺ハウジン
グの補修方法およびその補修構造の一実施例を示す図、
第2図は沸騰水型原子炉の下部構造を示す図、第3図は
第2図の原子炉圧力容器に固定支持される中性子束検出
器を示す図、第4図は上記中性子束検出器の中性子束モ
ニタハウジングを原子炉圧力容器に固定支持させる取付
MIt造を示す図、第5図(A)および(B)は第1図
の長尺ハウジングの補修方法に用いられるハウジング拡
管工程の一例を示す図、第6図(A)ないしくC)は本
発明に係る長尺ハウジングの補修方法およびその補修構
造の他の実施例を示す図、第7図(A)ないしくC)お
よび第8図(A)ないしくC)は本発明のさらに他の実
施例をそれぞれ示す図、第9図は従来の沸騰水型原子炉
に取付けられる中性子束検出器の設置例を概略的に示す
図である。
3・・・炉心、5・・・上部格子板、10・・・原子炉
圧力容器、13・・・tlJ 11棒駆動機構、14・
・・CRDハウジング、15・・・中性子束検出器、1
6・・・中性子束モニタ本体、17・・・中性子束モニ
タ案内管、18・・・中性子束モニタハウジング、23
・・・貫通孔、25・・・管台(溶接部)、26・・・
溶接部、30.35・・・補修スリーブ、31・・・欠
陥部、32・・・アームシーム溶接、33・・・シール
溶接、36・・・金ろう、37・・・加熱コイル。
出願人代理人 波 多 野 久2J
(A)
第5
ゐ
(B)
図FIG. 1 (A> to D) is a diagram showing an embodiment of a long housing repair method and its repair structure according to the present invention;
Figure 2 is a diagram showing the lower structure of a boiling water reactor, Figure 3 is a diagram showing a neutron flux detector fixedly supported on the reactor pressure vessel in Figure 2, and Figure 4 is a diagram showing the neutron flux detector mentioned above. Figures 5 (A) and (B) are an example of the housing tube expansion process used in the repair method for the elongated housing shown in Figure 1. Figures 6(A) to C) are diagrams showing other embodiments of the long housing repair method and its repair structure according to the present invention, and Figures 7(A) to C) and Figures 8 (A) to C) are views showing still other embodiments of the present invention, and Figure 9 is a view schematically showing an installation example of a neutron flux detector installed in a conventional boiling water reactor. It is. 3... Reactor core, 5... Upper grid plate, 10... Reactor pressure vessel, 13... tlJ 11 rod drive mechanism, 14...
...CRD housing, 15...Neutron flux detector, 1
6... Neutron flux monitor main body, 17... Neutron flux monitor guide tube, 18... Neutron flux monitor housing, 23
...Through hole, 25...Nozzle holder (welded part), 26...
Welded part, 30. 35... Repair sleeve, 31... Defect part, 32... Arm seam welding, 33... Seal welding, 36... Gold solder, 37... Heating coil. Applicant's agent Hisashi Hatano 2J (A) Figure 5 (B)
Claims (1)
ウジング等の長尺ハウジングに補修スリーブを挿入し、
挿入された補修スリーブで長尺ハウジングの欠陥発生部
を内側から覆うように塞ぎ、この閉塞位置で前記補修ス
リーブを長尺ハウジングに固着することを特徴とする長
尺ハウジングの補修方法。 2、長尺ハウジングの欠陥発生部位を内側から覆う閉塞
位置で補修スリーブを拡管させて長尺ハウジング内面に
密着させ、密着された補修スリーブをアークシーム溶接
により固着する請求項1記載の長尺ハウジングの補修方
法。 3、原子炉容器の下鏡溶接部に固定された中性子束モニ
タハウジング等の長尺ハウジングを、原子炉容器の貫通
孔にその挿通位置で拡管させてシール固着する一方、上
記長尺ハウジング内に補修スリーブを挿入し、挿入され
た補修スリーブで長尺ハウジングの欠陥発生部を内側か
ら覆うように塞ぎ、この閉塞位置で前記補修スリーブを
長尺ハウジングに固着することを特徴とする長尺ハウジ
ングの補修方法。 4、原子炉容器の溶接部に固着された中性子束モニタハ
ウジング等の長尺ハウジングに、そのハウジング欠陥発
生部を内側から塞ぐように補修スリーブを内挿し、その
閉塞位置で補修スリーブを長尺ハウジングに固着したこ
とを特徴とする長尺ハウジングの補修構造。 5、長尺ハウジングに挿入される補修スリーブはハウジ
ング欠陥発生部の閉塞位置で拡管させて長尺ハウジング
内面に密着させて固着した請求項4記載の長尺ハウジン
グの補修構造。 6、原子炉容器の貫通孔内を通り、その下鏡溶接部に固
定された中性子束モニタハウジング等の長尺ハウジング
を、前記貫通孔挿通位置で拡管させてシール固着させる
一方、前記長尺ハウジングに、そのハウジング欠陥発生
部を内側から塞ぐように補修スリーブを内挿し、その閉
塞位置で補修スリーブを長尺ハウジングに固着したこと
を特徴とする長尺ハウジングの補修構造。[Claims] 1. Inserting a repair sleeve into a long housing such as a neutron flux monitor housing fixed to a welded part of a reactor vessel,
A method for repairing an elongated housing, comprising: closing a defective part of the elongated housing so as to cover it from the inside with the inserted repair sleeve, and fixing the repair sleeve to the elongated housing at this closed position. 2. The elongated housing according to claim 1, wherein the repair sleeve is expanded at a closed position to cover the defect occurrence site of the elongated housing from the inside, and the repair sleeve is brought into close contact with the inner surface of the elongated housing, and the adhered repair sleeve is fixed by arc seam welding. How to repair. 3. A long housing such as a neutron flux monitor housing fixed to the lower mirror welding part of the reactor vessel is expanded into the through hole of the reactor vessel at the insertion position and sealed and fixed, while the long housing is fixed inside the long housing. A long housing characterized in that a repair sleeve is inserted, the inserted repair sleeve covers and closes a defect occurring part of the elongated housing from the inside, and the repair sleeve is fixed to the elongated housing in this closed position. Repair method. 4. Insert the repair sleeve into a long housing such as a neutron flux monitor housing fixed to the welded part of the reactor vessel so as to close the defective part of the housing from the inside, and insert the repair sleeve into the long housing at the closed position. A repair structure for a long housing, which is characterized by being firmly fixed to the housing. 5. The repair structure for an elongated housing according to claim 4, wherein the repair sleeve inserted into the elongated housing is expanded at a closed position of the defective housing portion and tightly adhered to the inner surface of the elongated housing. 6. A long housing such as a neutron flux monitor housing that passes through the through hole of the reactor vessel and is fixed to the welded portion of the lower mirror is expanded at the through hole insertion position and fixed with a seal, while the long housing A repair structure for a long housing, characterized in that a repair sleeve is inserted so as to close the defective part of the housing from the inside, and the repair sleeve is fixed to the long housing at the closed position.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1031920A JP2519316B2 (en) | 1989-02-10 | 1989-02-10 | Repair method for long housing and repair structure |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1031920A JP2519316B2 (en) | 1989-02-10 | 1989-02-10 | Repair method for long housing and repair structure |
Related Child Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2118611A Division JPH03135794A (en) | 1990-05-10 | 1990-05-10 | Processing method for long-sized housing |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH02210296A true JPH02210296A (en) | 1990-08-21 |
JP2519316B2 JP2519316B2 (en) | 1996-07-31 |
Family
ID=12344414
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1031920A Expired - Lifetime JP2519316B2 (en) | 1989-02-10 | 1989-02-10 | Repair method for long housing and repair structure |
Country Status (1)
Country | Link |
---|---|
JP (1) | JP2519316B2 (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH03170093A (en) * | 1989-08-04 | 1991-07-23 | Hitachi Ltd | Preventive maintenance method for neutron flux monitor housing |
JP2011145271A (en) * | 2010-01-18 | 2011-07-28 | Mitsubishi Heavy Ind Ltd | Nozzle stub mounting structure |
CN106624405A (en) * | 2016-11-07 | 2017-05-10 | 中广核工程有限公司 | Damage repairing method and system for pipe plate and pipe hole of nuclear power plant steam generator |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111085819B (en) * | 2018-10-24 | 2021-11-12 | 中核核电运行管理有限公司 | Method for preparing neutron flux measuring tube power station on site |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0298695A (en) * | 1988-10-05 | 1990-04-11 | Hitachi Ltd | Method for repairing neutron flux monitor housing |
-
1989
- 1989-02-10 JP JP1031920A patent/JP2519316B2/en not_active Expired - Lifetime
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0298695A (en) * | 1988-10-05 | 1990-04-11 | Hitachi Ltd | Method for repairing neutron flux monitor housing |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH03170093A (en) * | 1989-08-04 | 1991-07-23 | Hitachi Ltd | Preventive maintenance method for neutron flux monitor housing |
JP2011145271A (en) * | 2010-01-18 | 2011-07-28 | Mitsubishi Heavy Ind Ltd | Nozzle stub mounting structure |
US8867688B2 (en) | 2010-01-18 | 2014-10-21 | Mitsubishi Heavy Industries, Ltd. | Nozzle mounting structure |
CN106624405A (en) * | 2016-11-07 | 2017-05-10 | 中广核工程有限公司 | Damage repairing method and system for pipe plate and pipe hole of nuclear power plant steam generator |
CN106624405B (en) * | 2016-11-07 | 2020-05-05 | 中广核工程有限公司 | Method and system for repairing damage of tube plate and tube hole of steam generator of nuclear power station |
Also Published As
Publication number | Publication date |
---|---|
JP2519316B2 (en) | 1996-07-31 |
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