JPH09113666A - Method for installing core internal structure - Google Patents

Method for installing core internal structure

Info

Publication number
JPH09113666A
JPH09113666A JP7275610A JP27561095A JPH09113666A JP H09113666 A JPH09113666 A JP H09113666A JP 7275610 A JP7275610 A JP 7275610A JP 27561095 A JP27561095 A JP 27561095A JP H09113666 A JPH09113666 A JP H09113666A
Authority
JP
Japan
Prior art keywords
shroud
simulated
core support
upper lattice
plate
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
JP7275610A
Other languages
Japanese (ja)
Inventor
Akira Sato
亮 佐藤
Koichi Kurosawa
孝一 黒沢
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP7275610A priority Critical patent/JPH09113666A/en
Publication of JPH09113666A publication Critical patent/JPH09113666A/en
Pending legal-status Critical Current

Links

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
    • 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

PROBLEM TO BE SOLVED: To provide a method for installing structures which can reduce the radiation exposure for workers in the installation or replacement of structures in a nuclear reactor in service and shorten the processes for installing them. SOLUTION: A shroud 1, an upper grid plate 12 and a core support 13 are installed inside a reactor pressure vessel 6. In the replacement of these core internals with new ones during the operation of a reactor, a dummy upper grid plate 2, a dummy core support 13 and an automatic welder 4 for welding the shroud 1 are beforehand incorporated into the shroud 1, which is brought into the reactor pressure vessel 6. Subsequently, after the shroud 1 is installed on a shroud support 5, the dummy upper grid plate 2 and the dummy core support 13 incorporated into the shroud 1 are replaced with a regular upper grid plate 12 and a regular core support 13 to install these regular ones finally.

Description

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

【０００１】[0001]

【発明の属する技術分野】本発明は、原子力発電プラン
ト建設時において、原子炉内部構造物であるシュラウド
を据付ける原子炉内部構造物の据付け方法に関する。ま
た、供用期間中にシュラウド、上部格子板、炉心支持板
等の原子炉内部構造物を新規の物に取り替える場合の原
子炉内部構造物の据付け方法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor internal structure installation method for installing a shroud which is a nuclear reactor internal structure at the time of construction of a nuclear power plant. Further, the present invention relates to a method for installing a reactor internal structure when replacing a reactor internal structure such as a shroud, an upper lattice plate and a core support plate with a new one during the service period.

【０００２】[0002]

【従来の技術】従来一般に採用されているの原子力発電
プラント建設時の原子炉内部構造物の据付け方法は、原
子炉圧力容器（以下ＲＰＶという）内にシュラウドサポ
ートを溶接により固定し、その後ジェットポンプを前記
ＲＰＶおよびシュラウドサポートに溶接により固定す
る。次いで、シュラウドを上部格子板および炉心支持板
と一体で前記ＲＰＶ内に搬入し、所定位置に据付けた
後、前記炉心支持板を前記シュラウドに固定する。2. Description of the Related Art Generally, a method of installing a reactor internal structure at the time of constructing a nuclear power plant is generally used in which a shroud support is fixed in a reactor pressure vessel (hereinafter referred to as RPV) by welding, and then a jet pump is used. To the RPV and shroud support by welding. Next, the shroud is carried into the RPV integrally with the upper lattice plate and the core support plate and installed at a predetermined position, and then the core support plate is fixed to the shroud.

【０００３】次いでＣＲＤハウジングを前記ＲＰＶに接
続固定されたＣＲＤスタブチューブに溶接により固定
し、ＩＣＭハウジングを前記ＲＰＶに溶接により固定す
る。ＩＣＭ案内管を前記炉心支持板穴に挿入後、前記Ｉ
ＣＭハウジングに溶接により固定、ＩＣＭ案内管をＩＣ
Ｍ案内管スタビライザにより溶接固定する。また差圧検
出／ほう酸水注入管を前記ＲＰＶおよび前記シュラウド
に溶接により固定する。上部格子板を前記シュラウドに
溶接により固定、炉心スプレイおよび給水スパージャを
前記ＲＰＶに溶接により固定するようにしている。Then, the CRD housing is fixed to the CRD stub tube connected and fixed to the RPV by welding, and the ICM housing is fixed to the RPV by welding. After inserting the ICM guide tube into the core support plate hole,
Welded to CM housing by welding, ICM guide tube is IC
Welded and fixed with M guide tube stabilizer. Further, the differential pressure detection / boric acid water injection pipe is fixed to the RPV and the shroud by welding. The upper lattice plate is fixed to the shroud by welding, and the core spray and the water supply sparger are fixed to the RPV by welding.

【０００４】一方、供用期間中のシュラウド、上部格子
板、炉心支持板等の原子炉内部構造物を新規の物に取り
替える場合の据付け方法としては、例えば特開昭６３−
３６１６１号公報、特開昭６３−３６１９５号公報に開
示されているような原子炉内部構造物の取替え工法等が
ある。これら公報に開示されている原子炉内部構造物の
取替え工法においては、シュラウド、上部格子板および
炉心支持板の取替え工法は、据付け後の機器の信頼性お
よび作業者の被ばく低減の観点よりある程度有望な方法
といえる。On the other hand, as a method for installing the reactor internal structure such as the shroud, the upper lattice plate, the core support plate, etc. during the service period to a new one, for example, Japanese Patent Laid-Open No. 63-
There is a method for replacing the reactor internal structure as disclosed in Japanese Patent No. 36161 and Japanese Patent Laid-Open No. 63-36195. In the method of replacing the reactor internal structure disclosed in these publications, the method of replacing the shroud, the upper lattice plate and the core support plate is promising to some extent from the viewpoint of reliability of equipment after installation and reduction of worker exposure. Can be said to be a simple method.

【０００５】[0005]

【発明が解決しようとする課題】しかし、従来の原子力
発電プラント建設時の原子炉内部構造物の据付け方法で
は、シュラウドのシュラウドサポートへの溶接は、作業
員が接近して手動溶接にて行うことになり、この工法を
供用期間中の原子炉内部構造物を新規の物に取替える場
合の据付け方法に適用すると、作業員が原子炉の底部に
接近して作業を行うことから、まだ、かなりの被ばくが
予想される。However, in the conventional method of installing the reactor internal structure at the time of constructing a nuclear power plant, the shroud is welded to the shroud support by an operator approaching and performing manual welding. If this method is applied to the installation method when replacing the reactor internal structure with a new one during the service period, it will still be a considerable amount because the workers work near the bottom of the reactor. Expected to be exposed.

【０００６】この場合、溶接作業を自動溶接機にて行う
考えもあるが、原子炉付近の溶接作業を自動溶接機にて
行うとしても、従来のこの据付け方法ではその溶接機の
取付けあるいは取外しの関係から、結局作業員が原子炉
の底部に接近して作業を行うことになり、その作業時に
は被ばくを負う恐れがある。In this case, it is considered that the welding work is carried out by an automatic welding machine, but even if the welding work near the nuclear reactor is carried out by the automatic welding machine, the conventional installation method does not require installation or removal of the welding machine. Due to the relationship, the worker will eventually approach the bottom of the reactor to perform the work, and there is a risk of exposure during the work.

【０００７】本発明はこれに鑑みなされたもので、その
目的とするところは、供用期間中の原子炉内部構造物の
据付け、あるいは取替え時における作業者の被ばく低減
を図るとともに、その据付け工程の短縮化を図ることが
可能なこの種原子炉内部構造物の据付け方法を提供する
にある。The present invention has been made in view of the above, and an object of the present invention is to reduce the exposure of workers during the installation or replacement of internal reactor internal structures during the service period, and An object of the present invention is to provide a method of installing the internal structure of this type of reactor, which can be shortened.

【０００８】[0008]

【課題を解決するための手段】すなわち本発明は、原子
炉圧力容器の内部にシュラウド、上部格子板、炉心支持
板を備え、供用期間中にこれらを新規の物に取り替える
に際し、予め前記シュラウド内に模擬の上部格子板およ
び模擬の炉心支持板さらにシュラウドを溶接する自動溶
接機を組み込んでおき、それを原子炉圧力容器内に搬入
し、次いでこの搬入したシュラウドを、原子炉圧力容器
およびシュラウドサポートに据え付けた後、このシュラ
ウド内に組み込まれている模擬の上部格子板および模擬
の炉心支持板を正規の上部格子板および炉心支持板と交
換し、前記正規の上部格子板および炉心支持板を据え付
けるようになし所期の目的を達成するようにしたもので
ある。That is, according to the present invention, a shroud, an upper lattice plate, and a core support plate are provided inside a reactor pressure vessel, and when these are replaced with new ones during the service period, the shroud A simulated upper lattice plate, a simulated core support plate, and an automatic welding machine for welding the shroud were installed in the reactor pressure vessel, which was then loaded into the reactor pressure vessel, and then the loaded shroud was coupled to the reactor pressure vessel and the shroud support. After installation, replace the simulated upper lattice plate and simulated core support plate incorporated in this shroud with the regular upper lattice plate and core support plate, and install the regular upper lattice plate and core support plate. As such, it is intended to achieve the intended purpose.

【０００９】すなわちこのような原子炉内部構造物の据
付け方法であると、予めシュラウド内に模擬の上部格子
板および模擬の炉心支持板およびシュラウドを溶接する
自動溶接機が組み込まれ、原子炉圧力容器内に搬入され
るので、溶接機の取付けあるいは取外しは、炉心から離
れた場所で行うことができ、作業員が原子炉の底部に接
近して作業を行う必要はなくなり、したがって、供用期
間中の原子炉内部構造物の据付け、あるいは取替えであ
っても、作業者の被ばく低減を図ることができ、また、
シュラウド内に組み込まれている模擬の上部格子板およ
び模擬の炉心支持板が、シュラウド据え付け時の芯出し
の役目をなし、シュラウド据え付け時の芯出しが容易と
なり、据付け工程短縮、作業ステップの低減が図れるの
である。That is, according to such a method for installing the internal structure of a nuclear reactor, an automatic welding machine for previously welding a simulated upper lattice plate, a simulated core support plate and a shroud is incorporated in a shroud, and a reactor pressure vessel is installed. Since the welding machine can be installed or removed from the reactor core, it is not necessary for the worker to approach the bottom of the reactor to carry out the work, so that the welding Even when installing or replacing the internal reactor structure, it is possible to reduce the exposure of workers, and
The simulated upper lattice plate and simulated core support plate incorporated in the shroud play a role of centering during shroud installation, which facilitates centering during shroud installation, shortening the installation process and reducing work steps. It can be achieved.

【００１０】[0010]

【発明の実施の形態】以下図示した実施例に基づいて本
発明を詳細に説明する。なお、以下の説明は新規建設プ
ラントよりも放射線環境下で種々制約条件があり作業が
困難な供用期間中におけるプラントの原子炉内部構造
物，すなわちシュラウド、上部格子板、炉心支持板など
を新規のものに取り替える場合について説明する。勿
論、新規建設プラントも同様な手法により原子炉内部構
造物の据付けが可能であることは云うまでもない。DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described below in detail with reference to the illustrated embodiments. In addition, the following explanation describes the reactor internal structure of the plant during the in-service period that is difficult to work under various radiation conditions than the new construction plant, that is, the shroud, the upper lattice plate, the core support plate, etc. The case of replacing with a new one will be described. Needless to say, the reactor internal structure can be installed in a new construction plant by the same method.

【００１１】図１５には据付け完了した圧力容器が断面
で示されている。図中６がＲＰＶ（原子炉圧力容器）で
あり、その内部にはシュラウド１、シュラウドサポート
５、上部格子板１２、炉心支持板１３、差圧検出／ほう
酸水注入管１４、ＩＣＭ案内管１５、ＩＣＭハウジング
１６、ＩＣＭ案内管スタビライザ１７、炉心スプレイ配
管１８などが配置されている。FIG. 15 shows a sectional view of the pressure vessel which has been installed. Reference numeral 6 in the figure is an RPV (reactor pressure vessel), and inside thereof is a shroud 1, a shroud support 5, an upper lattice plate 12, a core support plate 13, a differential pressure detection / boric acid water injection pipe 14, an ICM guide pipe 15, An ICM housing 16, an ICM guide tube stabilizer 17, a core spray pipe 18, and the like are arranged.

【００１２】本発明の据付け方法は、予めシュラウド１
内に模擬の上部格子板および模擬の炉心支持板さらにシ
ュラウドを溶接する自動溶接機を組み込んでおき、それ
をＲＰＶ６内に搬入し、次いでこの搬入したシュラウド
を、原子炉圧力容器およびシュラウドサポートに据え付
けた後、このシュラウド内に組み込まれている模擬の上
部格子板および模擬の炉心支持板を正規の上部格子板１
２および炉心支持板１３と交換し、前記自動溶接機で溶
接固定するわけであるが、以下それぞれについて説明す
る。According to the installation method of the present invention, the shroud 1 is previously prepared.
A simulated upper grid plate, a simulated core support plate, and an automatic welding machine for welding the shroud were installed in the RPV6, and then the loaded shroud was installed in the reactor pressure vessel and the shroud support. After that, the simulated upper lattice plate and the simulated core support plate incorporated in this shroud are replaced with the regular upper lattice plate 1
2 and the core support plate 13 are replaced and welded and fixed by the automatic welding machine, which will be described below.

【００１３】図２には、そのシュラウド１内に模擬上部
格子板２および模擬炉心支持板３を組み込んだ状況が示
されている。すなわちシュラウド１に上部格子板および
炉心支持板を組み込みシュラウド１と一体で搬入するの
である。後述するが、これによりシュラウド１の芯出し
が容易になるのである。図３にはシュラウド１内に模擬
上部格子板２および模擬炉心支持板３を組み込み、さら
にシュラウド溶接機４を組み込んだ状況が示されてい
る。シュラウド溶接機４はシュラウド内面の下端に設定
される。FIG. 2 shows a state in which the simulated upper lattice plate 2 and the simulated core support plate 3 are incorporated in the shroud 1. That is, the upper lattice plate and the core support plate are incorporated in the shroud 1 and carried in integrally with the shroud 1. As will be described later, this facilitates the centering of the shroud 1. FIG. 3 shows a state in which the simulated upper lattice plate 2 and the simulated core support plate 3 are incorporated in the shroud 1, and further the shroud welder 4 is incorporated. The shroud welder 4 is set at the lower end of the inner surface of the shroud.

【００１４】図４、図５には、その模擬上部格子板２の
概念が示されている。模擬上部格子板２はボルト３８、
キーパ３９、クサビ４０にて固定される。一方、図６、
図７には模擬炉心支持板３が示されている。図からも明
らかなように、取付けおよび取外しが容易に行えるよう
にボルト３８にて固定されるようになっている。FIGS. 4 and 5 show the concept of the simulated upper lattice plate 2. The simulated upper lattice plate 2 has bolts 38,
It is fixed with a keeper 39 and a wedge 40. On the other hand, FIG.
FIG. 7 shows the simulated core support plate 3. As is clear from the figure, the bolts 38 are fixed so that they can be easily attached and detached.

【００１５】また、図８、図９にはシュラウド溶接機４
の概念が示されている。シュラウド溶接機４は、ヘッド
走行モータ２３、ワイヤーリール２４、左右位置決めセ
ンサ２５、アーク監視用カメラ２６、ＡＶＣモータ２
７、オシレートモータ２８、溶接トーチ２９、ワイヤ送
給モータ３０より構成され、ヘッド走行レール３１に設
置しケーブル３２により電源３３および制御盤３４に接
続される。Further, the shroud welding machine 4 is shown in FIGS.
The concept of is shown. The shroud welder 4 includes a head traveling motor 23, a wire reel 24, a horizontal positioning sensor 25, an arc monitoring camera 26, and an AVC motor 2.
7, an oscillating motor 28, a welding torch 29, and a wire feeding motor 30, which are installed on a head traveling rail 31 and connected to a power source 33 and a control panel 34 by a cable 32.

【００１６】ヘッド走行レール３１はシュラウド内面の
下端にボルト３５により固定され、ヘッド走行モータ２
３によりヘッド走行レール３１上を左右（周方向）に移
動できる構造としている。また溶接トーチ２９の上下、
前後の移動はオシレートモータ２８、およびＡＶＣモー
タ２７により行いアーク監視用カメラ２６にて溶接状況
を確認する。電源３３および制御盤３４はケーブル３２
によりシュラウド溶接機４に接続され、ＲＰＶ６外に設
置されることで作業者の被ばく低減が図れる。The head traveling rail 31 is fixed to the lower end of the inner surface of the shroud with bolts 35, and the head traveling motor 2
3, the head traveling rail 31 can be moved left and right (circumferential direction). Also, above and below the welding torch 29,
The forward and backward movement is performed by the oscillating motor 28 and the AVC motor 27, and the welding status is confirmed by the arc monitoring camera 26. The power supply 33 and the control panel 34 are cables 32
With this, it is connected to the shroud welder 4 and installed outside the RPV 6, so that the exposure of the worker can be reduced.

【００１７】この図に示されているようにシュラウド溶
接機４は、４セットで構成され４セット同時に溶接する
ことによりシュラウド１の溶接による倒れを少なくし、
また溶接作業時間の短縮も図られる。As shown in this figure, the shroud welder 4 is composed of 4 sets, and by simultaneously welding 4 sets, the fall of the shroud 1 due to welding is reduced,
Also, the welding work time can be shortened.

【００１８】シュラウド溶接機４のＲＰＶ６外への搬出
は、シュラウド１据付け完了後、シュラウド１内部に組
み込まれた模擬上部格子板２および模擬炉心支持板３を
取外した後、ゴンドラ３７により作業員がＲＰＶ６内に
接近し走行レール３１よりシュラウド溶接機４およびケ
ーブル３２を取外し、ボルト３５を緩め走行レール３１
を取外しＲＰＶ６外へ搬出される。上部格子板および炉
心支持板が模擬的なものであり取外しが容易に行えるた
め、シュラウド溶接機の設計が容易になる。The shroud welder 4 is carried out to the outside of the RPV 6 after the installation of the shroud 1 is completed, the simulated upper lattice plate 2 and the simulated core support plate 3 incorporated in the shroud 1 are removed, and then the operator uses the gondola 37. The shroud welder 4 and the cable 32 are removed from the traveling rail 31 by approaching the inside of the RPV 6, and the bolts 35 are loosened to the traveling rail 31.
Removed and carried out of RPV6. Since the upper lattice plate and the core support plate are simulated and can be easily removed, the design of the shroud welder becomes easy.

【００１９】図１０、図１１には図２に示すシュラウド
１内に模擬上部格子板２および模擬炉心支持板３を組み
込んだ原子炉内部構造物を原子炉建屋内のＲＰＶ６内に
搬入する搬入手順が示されている。上記原子炉内部構造
物を組み込んだシュラウド１を原子炉建屋内の大物搬入
口１０より天井クレーン（図示せず）により原子炉ウェ
ル７に設置する。10 and 11, the carrying-in procedure for carrying in the reactor internal structure in which the simulated upper lattice plate 2 and the simulated core support plate 3 are incorporated into the shroud 1 shown in FIG. 2 into the RPV 6 in the reactor building. It is shown. The shroud 1 incorporating the reactor internal structure is installed in the reactor well 7 from the large-scale inlet 10 in the reactor building by an overhead crane (not shown).

【００２０】原子炉ウェル７には予め遮蔽兼架台８を設
置し、シュラウド１を仮置する。遮蔽兼架台８に仮置き
したシュラウド１にシュラウド溶接機４を設定しシュラ
ウド遮蔽体９を設定する。炉内構造物吊り具１１をシュ
ラウド１の上面に取付けシュラウド１のＲＰＶ６内への
搬入準備が完了となる。なお、図１０、図１１ではシュ
ラウド１内にシュラウド遮蔽体９を組み込んだ状況を示
したが、新規建設プラントではシュラウド遮蔽体９は不
要である。A shield and gantry 8 is installed in advance in the reactor well 7 and the shroud 1 is temporarily placed. The shroud welder 4 and the shroud shield 9 are set on the shroud 1 which is temporarily placed on the shield and gantry 8. The in-core structure hanging tool 11 is attached to the upper surface of the shroud 1, and the preparation for carrying the shroud 1 into the RPV 6 is completed. 10 and 11 show the situation in which the shroud shield 9 is incorporated in the shroud 1, the shroud shield 9 is not necessary in the new construction plant.

【００２１】図１にシュラウド１の据付け概念が示され
ている。シュラウド１を炉内構造物吊り具１１によりＲ
ＰＶ６内に吊りこみシュラウドサポート５に設定する。
なお、芯測定要領については公知の方法，例えば特開昭
６３−３６１９５号公報に記載の方法で行われる。シュ
ラウド１を芯測定の規定公差内に設定した後、シュラウ
ド１上部とＲＰＶ６間にシュラウド倒れ防止治具（図示
せず）を設置し、シュラウド１の倒れ防止を図る。The installation concept of the shroud 1 is shown in FIG. R for the shroud 1 by means of the in-core structure hanging tool 11
Suspend in PV6 and set to shroud support 5.
The core measuring procedure is carried out by a known method, for example, the method described in JP-A-63-36195. After setting the shroud 1 within the specified tolerance of the core measurement, a shroud fall prevention jig (not shown) is installed between the upper part of the shroud 1 and the RPV 6 to prevent the shroud 1 from falling.

【００２２】シュラウド１をシュラウドサポート５に設
定後、シュラウド溶接機４によりシュラウド１をシュラ
ウドサポート５に溶接する。その後、シュラウド倒れ防
止治具をＲＰＶ６外へ搬出し、炉内構造物吊り具１１に
より模擬上部格子板２および模擬炉心支持板３をシュラ
ウド１内から取外し、ＲＰＶ６外へ搬出する。そしてシ
ュラウド溶接機４をＲＰＶ６外へ搬出する。シュラウド
溶接機４搬出後、正規炉心支持板１３の据付けを行うが
炉内構造物吊り具１１により搬入、芯測定を行いシュラ
ウド１に据え付ける。After setting the shroud 1 on the shroud support 5, the shroud welder 4 welds the shroud 1 to the shroud support 5. After that, the shroud fall prevention jig is carried out to the outside of the RPV 6, the simulated upper lattice plate 2 and the simulated core support plate 3 are removed from the inside of the shroud 1 by the reactor internal structure hanging tool 11, and carried out to the outside of the RPV 6. Then, the shroud welder 4 is carried out of the RPV 6. After unloading the shroud welder 4, the regular core support plate 13 is installed, but it is loaded by the in-core structure suspending tool 11, the core is measured, and the shroud 1 is installed.

【００２３】そしてその後、差圧検出／ほう酸水注入管
１４をＲＰＶ６内に搬入し溶接により固定する。そして
ＩＣＭ案内管１５を正規炉心支持板１３穴に挿入後、Ｉ
ＣＭハウジング１６に溶接により固定、ＩＣＭ案内管１
５をＩＣＭ案内管スタビライザ１７により溶接、固定す
る。正規上部格子板１２をシュラウド１に据え付ける
が、供用期間中にシュラウド１等の原子炉内部構造物を
新規の物と取り替える場合は、正規上部格子板１２据付
け前にシュラウド遮蔽体９をＲＰＶ６外に搬出、その後
正規上部格子板１２を炉内構造物吊り具１１により搬
入、芯測定を行いシュラウド１に据え付ける。Then, the differential pressure detection / boric acid water injection pipe 14 is carried into the RPV 6 and fixed by welding. Then, after inserting the ICM guide tube 15 into the hole of the regular core support plate 13,
Fixed to CM housing 16 by welding, ICM guide tube 1
5 is welded and fixed by the ICM guide tube stabilizer 17. Although the regular upper lattice plate 12 is installed on the shroud 1, if the reactor internal structure such as the shroud 1 is replaced with a new one during the service period, the shroud shield 9 is placed outside the RPV 6 before the regular upper lattice plate 12 is installed. After carrying out, the regular upper lattice plate 12 is carried in by the furnace internal structure hanging tool 11, the core is measured, and the shroud 1 is installed.

【００２４】正規上部格子板１２および前術の正規炉心
支持板１３の芯測定要領の詳細も特開昭６３−３６１９
５号公報に記載の方法に準ずる。また、作業員の正規上
部格子板１２および前述の正規炉心支持板１３の復旧箇
所へのアクセスは、ゴンドラ３７により行う。正規上部
格子板１２据付け後炉心スプレイ１８および給水スパー
ジャ１９をＲＰＶ６に溶接固定される。Details of core measuring procedures for the regular upper lattice plate 12 and the conventional regular core support plate 13 are also disclosed in Japanese Patent Laid-Open No. 63-3619.
The method described in Japanese Patent No. 5 is applied. Further, the gondola 37 is used by the worker to access the restoration locations of the regular upper lattice plate 12 and the regular core support plate 13 described above. After installation of the regular upper lattice plate 12, the core spray 18 and the water supply sparger 19 are welded and fixed to the RPV 6.

【００２５】図１２〜図１５には、その据付け方法が順
に示されている。図１６には従来の原子炉内部構造物の
据付け手順、図１７には従来の原子炉内部構造物の据付
けにシュラウド溶接機を採用した据付け手順が示されて
いる。従来の手順の図１６では、ＲＰＶ６炉底部に接近
するケースが、シュラウド１溶接、差圧検出／ほう酸水
注入管１４溶接、ＩＣＭ案内管１５溶接、ＩＣＭ案内管
スタビライザ１７設定、ＩＣＭ案内管スタビライザ１７
溶接と５回になる。12 to 15 show the installation method in order. FIG. 16 shows a conventional reactor internal structure installation procedure, and FIG. 17 shows a conventional reactor internal structure installation procedure using a shroud welder. In FIG. 16 of the conventional procedure, cases where the RPV6 furnace bottom is approached include shroud 1 welding, differential pressure detection / boric acid water injection pipe 14 welding, ICM guide pipe 15 welding, ICM guide pipe stabilizer 17 setting, ICM guide pipe stabilizer 17
It will be 5 times with welding.

【００２６】また、図１７ではシュラウド溶接機４設
定、シュラウド１溶接、シュラウド溶接機４取外し、差
圧検出／ほう酸水注入管１４溶接、ＩＣＭ案内管１５溶
接、ＩＣＭ案内管スタビライザ１７設定、ＩＣＭ案内管
スタビライザ１７溶接と７回となる。そこで、本発明と
比較してみると、原子炉内部構造物をシュラウド１内に
組み込み、シュラウド１と一体でＲＰＶ６内に搬入、そ
してシュラウド１溶接に自動溶接機を用いることによ
り、ＲＰＶ６炉底部への接近回数が５回となり、供用期
間中のシュラウド１、上部格子板１２、炉心支持板１３
等の原子炉内部構造物を新規の物に取り替える場合、放
射線環境下の作業となり、作業者の被ばく低減の観点よ
り図１７に示す従来の据付け手順に比し有利といえる。Further, in FIG. 17, shroud welder 4 setting, shroud 1 welding, shroud welder 4 removal, differential pressure detection / boric acid water injection pipe 14 welding, ICM guide pipe 15 welding, ICM guide pipe stabilizer 17 setting, ICM guide Pipe stabilizer 17 welding and 7 times. Therefore, in comparison with the present invention, by incorporating the reactor internal structure into the shroud 1, carrying it into the RPV 6 integrally with the shroud 1, and using an automatic welding machine for the shroud 1 welding, to the RPV 6 furnace bottom part. Has been approached 5 times, and the shroud 1, the upper lattice plate 12, the core support plate 13 during the service period
When replacing the reactor internal structure with a new one, etc., it becomes a work under a radiation environment, and it can be said that it is advantageous as compared with the conventional installation procedure shown in FIG. 17 from the viewpoint of reducing the exposure of the worker.

【００２７】また、シュラウド溶接に自動溶接機を採用
することにより、作業者の被ばく低減の観点より図１６
に示す従来の据付け手順に比し有利と言える。なお、図
１８には本発明による原子炉内部構造物の据え付け手順
が示されている。Further, by adopting an automatic welding machine for the shroud welding, from the viewpoint of reducing the exposure of the worker, FIG.
It can be said to be advantageous as compared with the conventional installation procedure shown in. It should be noted that FIG. 18 shows a procedure for installing the reactor internal structure according to the present invention.

【００２８】以上説明してきたように、本発明の原子炉
内部構造物の据え付け方法であると、シュラウド据え付
け時の芯出し用として、上部格子板および炉心支持板を
模擬的なものにすることにより取外しを容易にすること
ができる。供用期間中に原子炉内部構造物を新規の物と
取り替える場合のシュラウドの溶接に自動溶接機を採用
することにより、作業員がＲＰＶ内の炉底部へ接近する
必要がなくなり作業者の被ばく低減が図れる。また、シ
ュラウド溶接機をシュラウドと一体でＲＰＶ内に搬入す
ることにより、作業員が溶接機の設定をするためにＲＰ
Ｖ内の炉底部に接近する必要がなくなり、原子炉内部構
造物の据付け工程短縮、作業ステップの低減および作業
者の被ばく低減が図れる。As described above, according to the method for installing the reactor internal structure of the present invention, the upper lattice plate and the core support plate are simulated for centering when installing the shroud. It can be easily removed. By adopting an automatic welding machine for welding the shroud when replacing the reactor internal structure with a new one during the service period, it is not necessary for the worker to approach the bottom of the RPV and the worker's exposure is reduced. Can be achieved. In addition, by bringing the shroud welder together with the shroud into the RPV, the RP can be set so that the worker can set the welder.
Since it is not necessary to approach the bottom of the reactor in V, the installation process of the reactor internals can be shortened, the work steps can be reduced, and the worker's exposure can be reduced.

【００２９】また、シュラウド据付け時の芯出し用とし
て前記シュラウド内に組み込まれた模擬上部格子板およ
び模擬炉心支持板を取外すことによりシュラウド溶接機
をＲＰＶ外へ搬出することができる。シュラウド溶接機
のＲＰＶ外への搬出においてシュラウド内に組み込まれ
た上部格子板および炉心支持板を取外すことは困難なた
め、代りに模擬上部格子板および模擬炉心支持板を前記
シュラウド内に組み込み、前記シュラウド溶接機搬出時
の上部格子板および炉心支持板の取外しを容易にするこ
とができる。The shroud welder can be carried out of the RPV by removing the simulated upper lattice plate and the simulated core support plate incorporated in the shroud for centering during shroud installation. Since it is difficult to remove the upper lattice plate and the core support plate incorporated in the shroud when the shroud welder is carried out to the outside of the RPV, the simulated upper lattice plate and the simulated core support plate are incorporated in the shroud instead. It is possible to easily remove the upper lattice plate and the core support plate when carrying out the shroud welder.

【００３０】[0030]

【発明の効果】以上説明してきたように本発明によれ
ば、供用期間中の原子炉内部構造物の据付け、あるいは
取替え時における作業者の被ばく低減を図るとともに、
その据付け工程の短縮化を図ることが可能な原子炉内部
構造物の据付け方法を得ることができる。As described above, according to the present invention, while reducing the exposure of workers during the installation or replacement of the internal structure of the reactor during the service period,
It is possible to obtain a method of installing a reactor internal structure capable of shortening the installation process.

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

【図１】本発明の原子炉内部構造物の据付け方法を説明
するためのシュラウドの据付概念図である。FIG. 1 is a conceptual diagram of installation of a shroud for explaining a method of installing a reactor internal structure according to the present invention.

【図２】シュラウド内に炉内構造物を組み込んだ図であ
る。FIG. 2 is a diagram in which a core internal structure is incorporated in a shroud.

【図３】シュラウド内にシュラウド溶接機を組み込んだ
図である。FIG. 3 is a view showing a shroud welder incorporated in the shroud.

【図４】模擬上部格子板を示す斜視図である。FIG. 4 is a perspective view showing a simulated upper lattice plate.

【図５】図４のＱ枠内を拡大して示す断面図である。5 is a cross-sectional view showing the inside of a Q frame of FIG. 4 in an enlarged manner.

【図６】模擬炉心支持板を示す斜視図である。FIG. 6 is a perspective view showing a simulated core support plate.

【図７】図６のＰ枠内を拡大して示す断面図である。7 is a cross-sectional view showing the inside of a P frame in FIG. 6 in an enlarged manner.

【図８】シュラウド自動溶接機の概念図である。FIG. 8 is a conceptual diagram of an automatic shroud welder.

【図９】シュラウド自動溶接機およびその周辺を示す斜
視図である。FIG. 9 is a perspective view showing an automatic shroud welding machine and its surroundings.

【図１０】シュラウドの原子炉圧力容器内への搬入手順
図である。FIG. 10 is a diagram showing a procedure for loading the shroud into the reactor pressure vessel.

【図１１】シュラウドの原子炉圧力容器内への搬入状態
図である。FIG. 11 is a diagram showing how the shroud is loaded into the reactor pressure vessel.

【図１２】シュラウド据付完了状況図である。FIG. 12 is a diagram showing the completion status of shroud installation.

【図１３】炉心支持板据付完了状況図である。FIG. 13 is a diagram showing the completion of installation of the core support plate.

【図１４】上部格子板据付完了状況図である。FIG. 14 is a diagram showing the completion of installation of the upper grid plate.

【図１５】炉内構造物据付完了状況図である。FIG. 15 is a diagram showing the completion of installation of the internal structure of the reactor.

【図１６】従来の原子力発電プラント建設時の据付手順
図（手動溶接）である。FIG. 16 is an installation procedure diagram (manual welding) at the time of constructing a conventional nuclear power plant.

【図１７】従来の原子力発電プラント建設時の手順で自
動溶接機を採用した据付け手順図である。FIG. 17 is an installation procedure diagram in which an automatic welding machine is adopted in the conventional procedure for constructing a nuclear power plant.

【図１８】本発明による原子炉内部構造物据付手順図で
ある。FIG. 18 is a reactor internal structure installation procedure diagram according to the present invention.

【符号の説明】[Explanation of symbols]

１…シュラウド、２…模擬上部格子板、３…模擬炉心支
持板、４…シュラウド溶接機、５…シュラウドサポー
ト、６…原子炉圧力容器、７…原子炉ウェル、８…遮蔽
兼架台、９…シュラウド遮蔽体、１０…大物搬入口、１
１…炉内構造物吊り具、１２…正規上部格子板、１３…
正規炉心支持板、１４…差圧検出／ほう酸水注入管、１
５…ＩＣＭ案内管、１６…ＩＣＭハウジング、１７…Ｉ
ＣＭ案内管スタビライザ、１８…炉心スプレイ配管、１
９…給水スパージャ、２０…再循環水出口ノズル、２１
…ＣＲＤハウジング、２２…ＣＲＤスタブチューブ、２
３…ジェットポンプ、２４…ワイヤーリール、２５…左
右位置決めセンサ、２６…アーク監視用カメラ、２７…
ＡＶＣモータ、２８…オシレートモータ、２９…溶接ト
ーチ、３０…ワイヤ送給モータ、３１…ヘッド走行レー
ル、３２…ケーブル、３３…電源、３４…制御盤、３５
…ボルト、３６…ヘッド走行モータ、３７…ゴンドラ、
３８…ボルト、３９…キーパ、４０…クサビ。1 ... Shroud, 2 ... Simulated upper lattice plate, 3 ... Simulated core support plate, 4 ... Shroud welder, 5 ... Shroud support, 6 ... Reactor pressure vessel, 7 ... Reactor well, 8 ... Shield and mount, 9 ... Shroud shield, 10 ... Large object carry-in port, 1
1 ... In-furnace structure hanging device, 12 ... Regular upper lattice plate, 13 ...
Regular core support plate, 14 ... Differential pressure detection / boric acid water injection pipe, 1
5 ... ICM guide tube, 16 ... ICM housing, 17 ... I
CM guide tube stabilizer, 18 ... Core spray piping, 1
9 ... Water supply sparger, 20 ... Recirculation water outlet nozzle, 21
… CRD housing, 22… CRD stub tube, 2
3 ... Jet pump, 24 ... Wire reel, 25 ... Left / right positioning sensor, 26 ... Arc monitoring camera, 27 ...
AVC motor, 28 ... Oscillating motor, 29 ... Welding torch, 30 ... Wire feeding motor, 31 ... Head traveling rail, 32 ... Cable, 33 ... Power supply, 34 ... Control panel, 35
... Bolts, 36 ... Head running motors, 37 ... Gondolas,
38 ... Bolt, 39 ... Keeper, 40 ... Wedge.

Claims (7)

【特許請求の範囲】[Claims] 【請求項１】 原子炉圧力容器の内部にシュラウド、上
部格子板、炉心支持板を備え、供用期間中にこれらを新
規の物に取り替えるに際し、予め前記シュラウド内に模
擬の上部格子板および模擬の炉心支持板さらにシュラウ
ドを溶接する自動溶接機を組み込んでおき、この組み込
まれたシュラウドを原子炉圧力容器内に搬入し、次いで
この搬入したシュラウドをシュラウドサポートに据え付
けた後、このシュラウド内に組み込まれている模擬の上
部格子板および模擬の炉心支持板を正規の上部格子板お
よび炉心支持板と交換し、正規の上部格子板および炉心
支持板を取替え据え付けるようにしたことを特徴とする
原子炉内部構造物の据付け方法。1. A reactor pressure vessel is provided with a shroud, an upper lattice plate, and a core support plate, and when these are replaced with new ones during a service period, a simulated upper lattice plate and a simulated upper lattice plate are previously provided in the shroud. The core support plate and an automatic welding machine for welding the shroud are installed.The assembled shroud is loaded into the reactor pressure vessel, and then the loaded shroud is installed on the shroud support and then installed in the shroud. The inside of the reactor characterized in that the simulated upper lattice plate and the simulated core support plate are replaced with the regular upper lattice plate and the core support plate, and the regular upper lattice plate and the core support plate are replaced and installed. How to install a structure. 【請求項２】 原子炉圧力容器の内部にシュラウド、上
部格子板、炉心支持板を備え、供用期間中にこれらを新
規の物に取り替えるに際し、予め前記シュラウド内に模
擬の上部格子板および模擬の炉心支持板さらにシュラウ
ドを溶接する自動溶接機を組み込んでおき、それを原子
炉圧力容器内に搬入し、次いでこの搬入したシュラウド
を、原子炉圧力容器およびシュラウドサポートに据え付
け溶接した後、このシュラウド内に組み込まれている模
擬の上部格子板および模擬の炉心支持板を取外し、この
取り外した部分に正規の上部格子板および炉心支持板を
据付けるようにしたことを特徴とする原子炉内部構造物
の据付け方法。2. A shroud, an upper lattice plate, and a core support plate are provided inside the reactor pressure vessel, and when these are replaced with new ones during the service period, a simulated upper lattice plate and a simulated upper lattice plate are previously provided in the shroud. The core support plate and an automatic welding machine for welding the shroud are installed.Then, they are loaded into the reactor pressure vessel, and then the loaded shroud is installed and welded to the reactor pressure vessel and the shroud support. The simulated upper lattice plate and the simulated core support plate incorporated in the reactor were removed, and the regular upper lattice plate and core support plate were installed on the removed parts. Installation method. 【請求項３】 原子炉圧力容器の内部にシュラウド、上
部格子板、炉心支持板を備え、供用期間中にこれらを新
規の物に取り替えるに際し、予め前記シュラウド内に模
擬上部格子板および模擬炉心支持板さらにシュラウドを
溶接する自動溶接機を組み込んでおき、それを原子炉圧
力容器内に搬入し、次いでこの搬入したシュラウドを、
原子炉圧力容器およびシュラウドサポートに据え付けた
後、このシュラウド内に組み込まれている模擬上部格子
板、模擬炉心支持板および自動溶接機を一緒に原子炉圧
力容器の外部に搬出し、その後、正規の上部格子板およ
び炉心支持板を搬入据え付けるようにしたことを特徴と
する原子炉内部構造物の据付け方法。3. A reactor pressure vessel is provided with a shroud, an upper lattice plate and a core support plate, and when these are replaced with new ones during the service period, a simulated upper lattice plate and a simulated core support are previously provided in the shroud. An automatic welding machine for welding plates and shrouds was installed, and it was loaded into the reactor pressure vessel, and then this loaded shroud was
After installation in the reactor pressure vessel and shroud support, the simulated upper lattice plate, simulated core support plate and automatic welder incorporated in this shroud were carried out together with the A method for installing a nuclear reactor internal structure, characterized in that an upper lattice plate and a core support plate are loaded and installed. 【請求項４】 原子炉圧力容器の内部にシュラウド、上
部格子板、炉心支持板を備えた原子炉設備で、このシュ
ラウド、上部格子板および炉心支持板を据え付けるに際
し、予め前記シュラウド内に着脱自在な模擬の上部格子
板および模擬の炉心支持板さらにシュラウドを溶接する
自動溶接機を組み込んでおき、この組み込まれたシュラ
ウドを原子炉圧力容器内に搬入し、次いでこの搬入した
シュラウドをシュラウドサポートに溶接して取り付けた
後、このシュラウド内に組み込まれている模擬上部格子
板および模擬炉心支持板を取外し、この取り外した模擬
上部格子板および模擬炉心支持板それに前記自動溶接機
を原子炉圧力容器の外部に搬出し、次いで正規の上部格
子板および炉心支持板を搬入し、前記模擬上部格子板お
よび模擬炉心支持板を取り外した部分に正規の上部格子
板および炉心支持板を据付けるようにしたことを特徴と
する原子炉内部構造物の据付け方法。4. A nuclear reactor facility having a shroud, an upper lattice plate and a core support plate inside a reactor pressure vessel, which can be detachably attached in advance to the shroud when the shroud, the upper lattice plate and the core support plate are installed. A simulated upper lattice plate, a simulated core support plate, and an automatic welding machine for welding the shroud are installed, the built-in shroud is carried into the reactor pressure vessel, and then the carried shroud is welded to the shroud support. , The simulated upper lattice plate and the simulated core support plate assembled in the shroud are removed, and the removed simulated upper lattice plate and simulated core support plate and the automatic welding machine are attached to the outside of the reactor pressure vessel. To the simulated upper grid plate and the simulated core support plate. A method for installing a nuclear reactor internal structure, characterized in that a regular upper lattice plate and a core support plate are installed on the removed portion. 【請求項５】 前記自動溶接機は少なくとも複数セット
備え、周方向に所定の間隔をおいて同時に溶接するよう
にした請求項１、２、３あるいは４記載の原子炉内部構
造物の据付け方法。5. The method for installing a reactor internal structure according to claim 1, wherein the automatic welding machine is provided with at least a plurality of sets and is welded simultaneously at a predetermined interval in the circumferential direction. 【請求項６】 前記模擬上部格子板および模擬炉心支持
板の固定は、ボルトあるいはくさびにて行なわれてなる
請求項１、２、３、４あるいは５記載の原子炉内部構造
物の据付け方法。6. The method of installing a reactor internal structure according to claim 1, wherein the simulated upper lattice plate and the simulated core support plate are fixed by bolts or wedges. 【請求項７】 原子炉圧力容器の内部にシュラウド、上
部格子板、炉心支持板を備え、供用期間中にこれらを新
規の物に取り替えるに際し、予め前記シュラウド内に着
脱自在に模擬の上部格子板および模擬の炉心支持板さら
にシュラウドを溶接する自動溶接機を組み込んでおき、
それを原子炉圧力容器内に搬入し、次いでこの搬入した
シュラウドを原子炉圧力容器およびシュラウドサポート
に溶接して据え付けた後、このシュラウド内に組み込ま
れている模擬の上部格子板および模擬の炉心支持板を原
子炉圧力容器の外部に搬出し、次いで前記自動溶接機を
搬出し、その後正規の上部格子板および炉心支持板を原
子炉圧力容器内に順次搬入し、前記模擬の上部格子板お
よび炉心支持板を取り外した部分に正規の上部格子板お
よび炉心支持板を据え付けるようにしたことを特徴とす
る原子炉内部構造物の据付け方法。7. A reactor pressure vessel is provided with a shroud, an upper lattice plate, and a core support plate inside, and when these are replaced with new ones during a service period, a simulated upper lattice plate is detachably attached in advance in the shroud. And a simulated core support plate and an automatic welder for welding shrouds,
After loading it into the reactor pressure vessel and then installing the loaded shroud by welding to the reactor pressure vessel and shroud support, the simulated upper lattice plate and simulated core support installed in the shroud were installed. The plate is carried out of the reactor pressure vessel, then the automatic welding machine is carried out, and then the regular upper lattice plate and core support plate are sequentially carried into the reactor pressure vessel, and the simulated upper lattice plate and core are carried out. A method for installing a nuclear reactor internal structure, characterized in that a regular upper lattice plate and a core support plate are installed on a portion where the support plate is removed.
JP7275610A 1995-10-24 1995-10-24 Method for installing core internal structure Pending JPH09113666A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7275610A JPH09113666A (en) 1995-10-24 1995-10-24 Method for installing core internal structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7275610A JPH09113666A (en) 1995-10-24 1995-10-24 Method for installing core internal structure

Publications (1)

Publication Number Publication Date
JPH09113666A true JPH09113666A (en) 1997-05-02

Family

ID=17557854

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7275610A Pending JPH09113666A (en) 1995-10-24 1995-10-24 Method for installing core internal structure

Country Status (1)

Country Link
JP (1) JPH09113666A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008232678A (en) * 2007-03-16 2008-10-02 Toshiba Corp Core shroud replacement method
JP2010066216A (en) * 2008-09-12 2010-03-25 Hitachi-Ge Nuclear Energy Ltd Installation method of incore equipment of natural circulation type boiling water reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008232678A (en) * 2007-03-16 2008-10-02 Toshiba Corp Core shroud replacement method
JP2010066216A (en) * 2008-09-12 2010-03-25 Hitachi-Ge Nuclear Energy Ltd Installation method of incore equipment of natural circulation type boiling water reactor
JP4684324B2 (en) * 2008-09-12 2011-05-18 日立Ｇｅニュークリア・エナジー株式会社 How to install in-reactor equipment of natural circulation boiling water reactor

Similar Documents

Publication Publication Date Title
US8687758B2 (en) Method for managing internal equipment in reactor pressure vessel and apparatus thereof
JP2003337192A (en) Inspection and preventive maintenance apparatus for structure within reactor pressure vessel, and inspection method
JP3660770B2 (en) How to replace in-furnace structures
JP3679823B2 (en) How to replace the core shroud
JPH09113666A (en) Method for installing core internal structure
JPH08105990A (en) Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore
JP4276808B2 (en) Equipment for carrying out nuclear power plant equipment
JP3897928B2 (en) How to replace the core shroud
JPH0862368A (en) Carrying method at replacement of reactor pressure vessel and reactor internal structure, and reactor building
JP2766209B2 (en) Reactor internal structure replacement method
JP2766195B2 (en) Reactor internal structure replacement method
JP3786009B2 (en) Reactor vessel handling
JP4212175B2 (en) How to replace the core shroud
JP2000346993A (en) Method for handling large structure in reactor building
JP4393011B2 (en) Replacement method of core spray system equipment
JPH10260290A (en) Method and apparatus for replacing structure in reactor pressure vessel
JP3372236B2 (en) How to replace equipment
JP4316130B2 (en) Core spray system piping replacement method
JP3413752B2 (en) Jet pump repair method and work platform in boiling water reactor
JP2000304890A (en) Reactor internal structure replacing method
JP3757077B2 (en) Water jet peening method and apparatus
JP2766179B2 (en) Maintenance method for furnace internals
JPH1090479A (en) Control-rod drive mechanism exchanger and its inspection method
JP2000304892A (en) Reactor internal structure replacing method
JP2001099988A (en) Surface machining device for apparatus installed inside nuclear reactor