JPH08122485A - Repairing method of shroud in nuclear reactor pressurized container - Google Patents

Repairing method of shroud in nuclear reactor pressurized container

Info

Publication number
JPH08122485A
JPH08122485A JP6263514A JP26351494A JPH08122485A JP H08122485 A JPH08122485 A JP H08122485A JP 6263514 A JP6263514 A JP 6263514A JP 26351494 A JP26351494 A JP 26351494A JP H08122485 A JPH08122485 A JP H08122485A
Authority
JP
Japan
Prior art keywords
shroud
reinforcing member
baffle plate
pressure vessel
fixing
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.)
Pending
Application number
JP6263514A
Other languages
Japanese (ja)
Inventor
Yusuke Watanabe
祐介 渡辺
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 JP6263514A priority Critical patent/JPH08122485A/en
Publication of JPH08122485A publication Critical patent/JPH08122485A/en
Pending 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)

Abstract

PURPOSE: To prevent the progress of a crack on a shroud in a nuclear reactor pressurized container. CONSTITUTION: In a nuclear reactor pressurized container 1, a baffle plate 7 is provided on the outer circumferential face of the lower part of a shroud 2 supported by a shroud support 11. the baffle plate 7 and a shroud head bolt- fixing lug 3 provided on the outer circumferential face of the upper part of the shroud 2 are connected to each other with a reinforcing member 5. Thereby, it is possible to prevent the progress of a crack when the crack is generated on the shroud 2.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は沸騰水型原子炉の原子炉
圧力容器内に設置されている原子炉圧力容器内シュラウ
ドの補修方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for repairing a shroud in a reactor pressure vessel installed in the reactor pressure vessel of a boiling water reactor.

【0002】[0002]

【従来の技術】沸騰水型原子炉の原子炉圧力容器内には
炉心支持板と上部格子板を保持し、燃料集合体全体を包
んで炉心を形成するシュラウドが設置されている。この
シュラウドの上部にはシュラウドヘッドボルトにより固
定されるシュラウドヘッドが設けられ、このシュラウド
ヘッドに気水分離器が取り付けられる。この気水分離器
は炉心から発生する蒸気と水に分離するものである。
2. Description of the Related Art In a reactor pressure vessel of a boiling water reactor, a shroud is installed which holds a core support plate and an upper lattice plate and encloses the entire fuel assembly to form a core. A shroud head fixed by a shroud head bolt is provided on an upper portion of the shroud, and a steam separator is attached to the shroud head. This steam separator separates steam and water generated from the core.

【0003】また、シュラウドの下部外面にはジェット
ポンプを固定するポンプデッキと称するバッフルプレー
トが取り付けられている。ジェットポンプは炉心外側に
配置され、冷却材を強制循環させるものである。
A baffle plate called a pump deck for fixing the jet pump is attached to the lower outer surface of the shroud. The jet pump is arranged outside the core and forcedly circulates the coolant.

【0004】[0004]

【発明が解決しようとする課題】原子炉圧力容器内のシ
ュラウド等の炉内構造物の多くは、ステンレス鋼の部材
の溶接構成からなるが、炭素含有量が高い場合、溶接部
あるいはその近くに応力腐食割れ等によりクラックを生
じる恐れがある。
Most of the reactor internals such as the shroud in the reactor pressure vessel are composed of welded stainless steel members. However, when the carbon content is high, the welded part or near the welded part is formed. Cracks may occur due to stress corrosion cracking.

【0005】特に、シュラウドは前述したように内部に
上部格子板と炉心支持板とを保持し、また、シュラウド
自身は下端で原子炉圧力容器と一体に作られたシュラウ
ドサポートリングに溶接して支持されている。そのた
め、交換することは極めて困難であり、交換できるもの
としても莫大なコストがかかるものと予測される。
In particular, the shroud holds the upper lattice plate and the core support plate inside, as described above, and the shroud itself is supported at the lower end by welding to the shroud support ring integrally formed with the reactor pressure vessel. Has been done. Therefore, it is extremely difficult to replace it, and even if it can be replaced, it is expected to be enormously expensive.

【0006】長時間使用された原子炉圧力容器内のシュ
ラウド等の炉内構造物や機器は中性子照射のため脆化し
ており、溶接した場合には溶着金属の周辺にさらに細か
い割れが生ずることもあるため、溶接による補修を難し
くしている課題がある。
[0006] Reactor internal structures and equipment such as shrouds in a reactor pressure vessel that have been used for a long time are fragile due to neutron irradiation, and when welded, finer cracks may occur around the weld metal. Therefore, there is a problem that repairing by welding is difficult.

【0007】本発明は上記課題を解決するためになされ
たもので、原子炉圧力容器内のシュラウドにクラック等
の欠陥が生じた場合、元の構造材料と同等の強度を保証
し、かつシュラウドヘッドボルト用ラグの機能を損うこ
とがない効果的な原子炉圧力容器内シュラウドの補修方
法を提供するものである。
The present invention has been made to solve the above problems, and when defects such as cracks occur in the shroud in the reactor pressure vessel, the shroud head guarantees the same strength as the original structural material. (EN) An effective method for repairing a shroud in a reactor pressure vessel that does not impair the function of a bolt lug.

【0008】[0008]

【課題を解決するための手段】本発明は原子炉圧力容器
内においてシュラウドサポートに支持されたシュラウド
の下部外側面にバッフルプレートを付設し、このバッフ
ルプレートと前記シュラウドの上部外側面に付設したシ
ュラウドヘッドボルト固定用ラグとを補強部材で連結す
ることを特徴とする。
According to the present invention, a baffle plate is attached to a lower outer surface of a shroud supported by a shroud support in a reactor pressure vessel, and the shroud attached to the baffle plate and the upper outer surface of the shroud. The head bolt fixing lug is connected by a reinforcing member.

【0009】[0009]

【作用】シュラウドの上部に取り付けられるシュラウド
ヘッドを固定するためのシュラウドヘッドボルト固定用
ラグとバッフルプレートとの間を補強部材で連結する。
これにより、シュラウドヘッドボルトの固定機能を損う
ことなく、シュラウドに割れが発生した場合の割れの進
行を防止できる。
The reinforcing member connects between the shroud head bolt fixing lug for fixing the shroud head attached to the upper part of the shroud and the baffle plate.
As a result, it is possible to prevent the crack from proceeding when the shroud cracks, without impairing the fixing function of the shroud head bolt.

【0010】また、補強部材の材質にオーステナイト系
ステンレス鋼の熱膨張係数より小さい熱膨張係数の材料
を使用することにより、補強部材取付時に付加する締結
荷重が僅かな荷重ですむため、取付作業が容易となる。
Further, by using a material having a coefficient of thermal expansion smaller than that of austenitic stainless steel for the material of the reinforcing member, a slight additional fastening load is required at the time of mounting the reinforcing member. It will be easy.

【0011】[0011]

【実施例】図面を参照しながら本発明に係る原子炉圧力
容器内シュラウドの補修方法の一実施例を説明する。な
お、図1は本発明方法を説明するための原子炉圧力容器
内を切欠して一部を縦断面で示す斜視図、図2は図1の
A部を拡大して示す斜視図、図3は図2の他の例を示す
斜視図、図4は図1のB部を説明するための一部断面図
で拡大して示す斜視図、図5は図4の他の例を一部断面
で示す斜視図、図6は図1におけるターンバックル部位
を一部側面で示す縦断面図である。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a method for repairing a shroud in a reactor pressure vessel according to the present invention will be described with reference to the drawings. 1 is a perspective view showing a part of the reactor pressure vessel in a vertical cross section by notching the inside of the reactor pressure vessel for explaining the method of the present invention, and FIG. 2 is an enlarged perspective view of part A of FIG. 2 is a perspective view showing another example of FIG. 2, FIG. 4 is an enlarged perspective view of a partial cross-sectional view for explaining a portion B of FIG. 1, and FIG. 5 is a partial cross-section of another example of FIG. 6 is a perspective view showing a part of the turnbuckle portion in FIG. 1 in a side view.

【0012】図1に示したように原子炉圧力容器1内に
はシュラウド2がシュラウドサポートリング11に支持さ
れて設置されている。シュラウド2の下部外側面にはバ
ッフルプレート7が付設し、前記シュラウド2の上部外
側面にはシュラウドヘッドボルト固定用ラグ3が付設し
ている。このバッフルプレート7とシュラウドヘッドボ
ルト固定ラグ3とを補強部材5で連結固定して原子炉圧
力容器1内のシュラウド2を補修する。
As shown in FIG. 1, a shroud 2 is installed in a reactor pressure vessel 1 while being supported by a shroud support ring 11. A baffle plate 7 is attached to the lower outer surface of the shroud 2, and a shroud head bolt fixing lug 3 is attached to the upper outer surface of the shroud 2. The baffle plate 7 and the shroud head bolt fixing lug 3 are connected and fixed by the reinforcing member 5 to repair the shroud 2 in the reactor pressure vessel 1.

【0013】この連結固定方法は図2に示したように、
シュラウドヘッドボルト固定用ラグ3に穴4を形成し、
この穴4と同様の位置に補強部材5にも穴を形成してお
く。補強部材5をラグ3の外側から押し込み、穴からピ
ンまたはボルト等の固定部品6を挿し込んでラグ3に設
けた穴4に固定する。この固定方法によりシュラウドヘ
ッドボルトの固定機能を失うことなく、補強部材5をシ
ュラウドヘッドボルト固定用ラグ3に接触固定できる。
This connecting and fixing method is as shown in FIG.
Form a hole 4 in the lug 3 for fixing the shroud head bolt,
A hole is also formed in the reinforcing member 5 at the same position as the hole 4. The reinforcing member 5 is pushed in from the outside of the lug 3 and a fixing component 6 such as a pin or a bolt is inserted through the hole and fixed in the hole 4 provided in the lug 3. By this fixing method, the reinforcing member 5 can be fixed by contact with the shroud head bolt fixing lug 3 without losing the fixing function of the shroud head bolt.

【0014】補強部材5のバッフルプレート7への固定
方法は、図4に示したようにバッフルプレート7および
補強部材5にネジ穴8加工を行い直接ねじ込み固定す
る。固定時、バッフルプレート7面と補強部材5の当た
り面に漏洩防止部品9を設ける。これによりポンプデッ
キつまり、バッフルプレート7の下部からの原子炉冷却
水漏洩を防止することが可能になる。
As a method of fixing the reinforcing member 5 to the baffle plate 7, screw holes 8 are formed in the baffle plate 7 and the reinforcing member 5 as shown in FIG. At the time of fixing, the leakage prevention component 9 is provided on the surface of the baffle plate 7 and the contact surface of the reinforcing member 5. This makes it possible to prevent leakage of the reactor cooling water from the pump deck, that is, the lower part of the baffle plate 7.

【0015】また、バッフルプレート7に穴加工を行い
この穴に補強部材を挿入し、挿入後補強部材5の先端爪
10を設け、この爪10が開くことによりバッフルプレート
7の下面に接触固定される。この場合、漏洩防止部品
は、バッフルプレートの穴加工面と補強部材との空隙に
設ける。
Further, a hole is formed in the baffle plate 7, a reinforcing member is inserted into this hole, and the tip claw of the reinforcing member 5 after the insertion.
10 is provided, and when the claw 10 is opened, it is fixed in contact with the lower surface of the baffle plate 7. In this case, the leakage prevention component is provided in the gap between the hole processing surface of the baffle plate and the reinforcing member.

【0016】さらに、図1に示したようにシュラウドヘ
ッドボルト固定用ラグ3の接触固定部とバッフルプレー
ト7の接触固定部との間にターンバックル10を設けるこ
とにより原子炉圧力容器1内に設置されたシュラウド2
を確実に補強することが可能になる。また、ターンバッ
クル10を補強部材とシュラウドヘッドボルト固定用ラグ
3の接触固定部の上部に設けることも可能である。この
とき、この補強部材5の接触固定部のシュラウドヘッド
ボルトの固定機能は失われるが、他のシュラウドヘッド
ボルトによりシュラウドヘッドは固定される。
Further, as shown in FIG. 1, a turnbuckle 10 is provided between the contact fixing portion of the lug 3 for fixing the shroud head bolt and the contact fixing portion of the baffle plate 7, and the turnbuckle 10 is installed in the reactor pressure vessel 1. Shroud 2
It is possible to reliably reinforce. It is also possible to provide the turnbuckle 10 above the contact fixing portion of the reinforcing member and the shroud head bolt fixing lug 3. At this time, the function of fixing the shroud head bolt of the contact fixing portion of the reinforcing member 5 is lost, but the shroud head is fixed by another shroud head bolt.

【0017】さらに、補強部材の材質として、シュラウ
ドの材料であるオーステナイト系ステンレス鋼の熱膨張
係数より小さい熱膨張係数を有する材料、たとえば耐食
耐熱超合金(NCF材)を選定する。
Further, as the material of the reinforcing member, a material having a coefficient of thermal expansion smaller than that of austenitic stainless steel which is a material of the shroud, for example, a corrosion resistant heat resistant superalloy (NCF material) is selected.

【0018】これにより多大な保持力を必要とする高
温,高圧運転のもとで被締結部材であるシュラウドと締
結部材である補強部材に熱膨張の伸びの差が生じ、これ
により得られる補強部材の軸力がシュラウドの保持のた
め効果的に作用する。この方法によれば補強部材取付時
に付加する締付加重もわずかな荷重ですむため、補強部
材の取付作業は容易となる。
As a result, a difference in thermal expansion between the shroud, which is the member to be fastened, and the reinforcing member, which is the fastening member, occurs under the high-temperature and high-pressure operation that requires a great holding force, and the resulting reinforcing member is obtained. The axial force of the shaft effectively acts to hold the shroud. According to this method, the tightening load added when mounting the reinforcing member requires only a small load, so that the mounting work of the reinforcing member becomes easy.

【0019】図1はシュラウドヘッドボルト固定用ラグ
3とバッフルプレート3をターンバックル10を具備した
補強部材5で連結固定し、シュラウド2を補強した状態
を示したものである。
FIG. 1 shows a state in which the shroud 2 is reinforced by connecting and fixing the shroud head bolt fixing lug 3 and the baffle plate 3 with a reinforcing member 5 having a turnbuckle 10.

【0020】図2はシュラウドヘッドボルト固定用ラグ
3と補強部材5を固定部品6で接触固定した状態の詳細
を示したものである。固定部品6は、シュラウドヘッド
ボルト固定用ラグ3の左右各々に取り付けるため、シュ
ラウドヘッド設置の際、挿入されるシュラウドヘッドボ
ルトとは干渉することなく、従ってシュラウドヘッドボ
ルトの締結機能を失うことがない。
FIG. 2 shows details of a state in which the lug 3 for fixing the shroud head bolt and the reinforcing member 5 are fixed in contact with each other by the fixing component 6. Since the fixing parts 6 are attached to each of the right and left sides of the shroud head bolt fixing lug 3, they do not interfere with the inserted shroud head bolt when the shroud head is installed, and thus the fastening function of the shroud head bolt is not lost. .

【0021】図3はシュラウドヘッドボルト固定用ラグ
3と補強部材5を固定部品6で別の方法により接触固定
した状態の詳細を示したものである。本固定方法により
図1に示すターンバックル10の機能を固定部品6で行う
ことが可能となるためターンバックル10を削除できる。
FIG. 3 shows details of a state in which the lug 3 for fixing the shroud head bolt and the reinforcing member 5 are contact-fixed by the fixing component 6 by another method. By this fixing method, the function of the turnbuckle 10 shown in FIG. 1 can be performed by the fixing component 6, so that the turnbuckle 10 can be deleted.

【0022】図4は補強部材5とバッフルプレート7を
接触固定した状態の詳細を示したものである。本補強部
材5とバッフルプレート7の接触部には、漏洩防止部品
9が設置されており、原子炉冷却漏洩の防止を行う。ま
た爪10は、ポンプデッキつまり、バッフルプレート7に
挿入された後、バッフルプレート7の下面で確実に爪10
が引っ掛かるように左右非対称の形となっている。
FIG. 4 shows details of the state where the reinforcing member 5 and the baffle plate 7 are fixed in contact with each other. A leak prevention component 9 is installed at the contact portion between the main reinforcing member 5 and the baffle plate 7 to prevent the reactor cooling leak. Further, the pawl 10 is securely inserted on the lower surface of the baffle plate 7 after being inserted into the pump deck, that is, the baffle plate 7.
The shape is asymmetrical so that it will be caught.

【0023】図5は補強部材5とバッフルプレート7を
別の方法により接触固定した状態の詳細を示したもので
ある。本補強部材5とバッフルプレート7の接触部に
は、図4の方法と同様に漏洩防止部品が設置されてお
り、原子炉冷却水漏洩の防止を行う。
FIG. 5 shows details of a state in which the reinforcing member 5 and the baffle plate 7 are contact-fixed by another method. At the contact portion between the main reinforcing member 5 and the baffle plate 7, a leak prevention component is installed as in the method shown in FIG. 4 to prevent leakage of the reactor cooling water.

【0024】図6はターンバックル10を設置した状態の
詳細を示したもので、上下一対の補強部材5にはネジ5
aが形成され、ターンバックル10に形成したネジ10aに
ねじ込み、図6に示し矢印の方向にターンバックル10を
回転させることによりシュラウド2の補強力を調節する
ことが可能である。
FIG. 6 shows details of the state in which the turnbuckle 10 is installed. The pair of upper and lower reinforcing members 5 are provided with screws 5
It is possible to adjust the reinforcing force of the shroud 2 by forming a and screwing it into the screw 10a formed on the turnbuckle 10 and rotating the turnbuckle 10 in the direction of the arrow shown in FIG.

【0025】[0025]

【発明の効果】本発明のよれば、沸騰水型軽水冷却原子
炉の原子炉圧力容器内に設置されるシュラウドにクラッ
ク等の欠陥が生じた場合、補強部材によりシュラウドヘ
ッドボルト用ラグとバッフルプレートを連結固定するこ
とにより、元の構造材料と同等の強度を保証し、かつシ
ュラウドヘッドボルトの機能を損うことがない効果的な
補修方法を提供することができる。
According to the present invention, when a defect such as a crack occurs in a shroud installed in a reactor pressure vessel of a boiling water type light water cooled reactor, a shroud head bolt lug and a baffle plate are reinforced by a reinforcing member. It is possible to provide an effective repairing method that guarantees strength equivalent to that of the original structural material and does not impair the function of the shroud head bolt by connecting and fixing.

【0026】また、補強部材をバッフルプレートとシュ
ラウドヘッドボルト固定用ラグと連結固定するにあた
り、水中、および遠隔操作で行うことができるため、原
子炉内の工事において放射線被曝を低減できる効果があ
る。
In addition, since the reinforcing member can be connected and fixed to the baffle plate and the shroud head bolt fixing lug in water or by remote control, there is an effect that radiation exposure can be reduced during construction in the nuclear reactor.

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

【図1】本発明に係る原子炉圧力容器内シュラウドの補
修方法の一実施例を説明するための一部断面で示す斜視
図。
FIG. 1 is a perspective view showing a partial cross-section for explaining an embodiment of a method for repairing a shroud in a reactor pressure vessel according to the present invention.

【図2】図1におけるA部を拡大して示す斜視図。FIG. 2 is an enlarged perspective view showing a portion A in FIG.

【図3】図2における他の例を示す斜視図。FIG. 3 is a perspective view showing another example in FIG.

【図4】図1におけるB部の挿入方法を説明するための
斜視図。
FIG. 4 is a perspective view for explaining a method of inserting a B portion in FIG.

【図5】図4における他の例を説明するための斜視図。FIG. 5 is a perspective view for explaining another example in FIG.

【図6】図1におけるターンバックル部を一部断面で拡
大して示す斜視図。
FIG. 6 is a perspective view showing the turnbuckle portion in FIG.

【符号の説明】[Explanation of symbols]

1…原子炉圧力容器、2…シュラウド、3…シュラウド
ヘッドボルト固定用ラグ、4…穴、5…補強部材、6…
固定部品、7…バッフルプレート、8…ネジ穴、9…漏
洩防止部品、10…ターンバックル、11…シュラウドサポ
ート。
1 ... Reactor pressure vessel, 2 ... Shroud, 3 ... Shroud head bolt fixing lug, 4 ... Hole, 5 ... Reinforcing member, 6 ...
Fixed parts, 7 ... Baffle plate, 8 ... Screw holes, 9 ... Leakage prevention parts, 10 ... Turnbuckle, 11 ... Shroud support.

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】 原子炉圧力容器内においてシュラウドサ
ポートにより支持されたシュラウドの下部外側面にバッ
フルプレートを付設し、このバッフルプレートと前記シ
ュラウドヘッドボルト固定用ラグとを補強部材で連結す
ることを特徴とする原子炉圧力容器内シュラウドの補修
方法。
1. A baffle plate is attached to a lower outer surface of a shroud supported by a shroud support in a reactor pressure vessel, and the baffle plate and the lug for fixing the shroud head bolt are connected by a reinforcing member. Repair method for shroud in reactor pressure vessel.
【請求項2】 前記バッフルプレートに漏洩防止部品を
介して補強部材を接触固定することを特徴とする請求項
1記載の原子炉圧力容器内シュラウドの補修方法。
2. The method for repairing a shroud in a reactor pressure vessel according to claim 1, wherein a reinforcing member is contact-fixed to the baffle plate through a leakage prevention component.
【請求項3】 前記シュラウドヘッドボルト用ラグに補
強部材を外側面から包囲し固定部品により接触固定する
ことを特徴とする請求項1記載の原子炉圧力容器内シュ
ラウドの補修方法。
3. The method for repairing a shroud in a reactor pressure vessel according to claim 1, wherein a reinforcing member is surrounded from the outer surface of the lug for the shroud head bolt and fixed by contact with a fixing component.
【請求項4】 前記バッフルプレートと前記シュラウド
ヘッドボルト固定用ラグとをターンバックルを有する補
強部材により接触固定することを特徴とする請求項1記
載の原子炉圧力容器内シュラウドの補修方法。
4. The method for repairing a shroud in a reactor pressure vessel according to claim 1, wherein the baffle plate and the lug for fixing the shroud head bolt are contact-fixed with a reinforcing member having a turnbuckle.
【請求項5】 前記補強部材はオーステナイト系ステン
レス鋼の熱膨張係数より小さい熱膨張係数を有する材料
からなることを特徴とする請求項1記載の原子炉圧力容
器内シュラウドの補修方法。
5. The method for repairing a shroud in a reactor pressure vessel according to claim 1, wherein the reinforcing member is made of a material having a coefficient of thermal expansion smaller than that of austenitic stainless steel.
JP6263514A 1994-10-27 1994-10-27 Repairing method of shroud in nuclear reactor pressurized container Pending JPH08122485A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6263514A JPH08122485A (en) 1994-10-27 1994-10-27 Repairing method of shroud in nuclear reactor pressurized container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6263514A JPH08122485A (en) 1994-10-27 1994-10-27 Repairing method of shroud in nuclear reactor pressurized container

Publications (1)

Publication Number Publication Date
JPH08122485A true JPH08122485A (en) 1996-05-17

Family

ID=17390597

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6263514A Pending JPH08122485A (en) 1994-10-27 1994-10-27 Repairing method of shroud in nuclear reactor pressurized container

Country Status (1)

Country Link
JP (1) JPH08122485A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5781603A (en) * 1995-07-21 1998-07-14 Combustion Engineering, Inc. Method and apparatus for repair of nuclear reactor shroud
JP2010043995A (en) * 2008-08-15 2010-02-25 Toshiba Corp Method of repairing shroud head

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5781603A (en) * 1995-07-21 1998-07-14 Combustion Engineering, Inc. Method and apparatus for repair of nuclear reactor shroud
JP2010043995A (en) * 2008-08-15 2010-02-25 Toshiba Corp Method of repairing shroud head

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