JPH08105990A - Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore - Google Patents
Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device thereforeInfo
- Publication number
- JPH08105990A JPH08105990A JP6241023A JP24102394A JPH08105990A JP H08105990 A JPH08105990 A JP H08105990A JP 6241023 A JP6241023 A JP 6241023A JP 24102394 A JP24102394 A JP 24102394A JP H08105990 A JPH08105990 A JP H08105990A
- Authority
- JP
- Japan
- Prior art keywords
- shroud
- reactor
- pressure vessel
- guide tube
- internal structure
- 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
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子力発電プラントの
建設時にシュラウド，炉心支持板，上部格子板，ＩＣＭ
案内管，ＩＣＭ案内管スタビライザ等の炉内構造物を短
期間で据付けることが出来る炉内構造物の据付け方法に
関する。The present invention relates to a shroud, a core support plate, an upper lattice plate, an ICM when constructing a nuclear power plant.
The present invention relates to a method of installing a reactor internal structure such as a guide pipe and an ICM guide pipe stabilizer that can be installed in a short period of time.
【０００２】また、供用期間中にシュラウド，炉心支持
板等の炉内構造物を新規製作の構造物と取替える場合、
短期間で取替作業後の信頼性が高くしかも作業員の被ば
く低減に好適な炉内構造物の据付け方法に関する。In the case where the in-core structures such as shrouds and core support plates are replaced with newly manufactured structures during the service period,
The present invention relates to a method of installing a reactor internal structure which has high reliability after replacement work in a short period of time and is suitable for reducing exposure of workers.
【０００３】更に、シュラウド据付けに好適なシュラウ
ド溶接機，シュラウド吊具兼芯測定装置に関する。Further, the present invention relates to a shroud welding machine suitable for shroud installation, a shroud suspension tool and a core measuring device.
【０００４】[0004]
【従来の技術】従来の原子力発電プラント建設時の炉内
構造物据付けは概略図２１に示すようにシュラウドサポ
ート２を原子炉圧力容器１に溶接後、前記シュラウドサ
ポート２および前記原子炉圧力容器１にジェットポンプ
３を取付け、その後前記シュラウドサポート２にシュラ
ウド４を作業員が接近し溶接、その後炉心支持板５を前
記シュラウド４に取付け、ＣＲＤハウジング６を前記原
子炉圧力容器１に溶接されたＣＲＤスタブチューブ７に
溶接し、ＩＣＭハウジング８を前記原子炉圧力容器１に
溶接する。その後差圧検出／ほう酸水注入管１７を原子
炉圧力容器１およびシュラウド４に溶接し、ＩＣＭ案内
管９を前記炉心支持板５穴に挿入後ＩＣＭハウジング８
に作業員が接近し溶接後、前記ＩＣＭ案内管９をＩＣＭ
案内管スタビライザ１０で固定、上部格子板１３，炉心
スプレイ配管１１，給水スパージャ１２を前記原子炉圧
力容器１内に搬入取付ける。2. Description of the Related Art As shown in FIG. 21, installation of a conventional reactor internal structure at the time of construction of a nuclear power plant is performed by welding a shroud support 2 to a reactor pressure vessel 1, and then, the shroud support 2 and the reactor pressure vessel 1 are welded. A jet pump 3 is attached to the shroud support 2, and then a shroud 4 is welded to the shroud support 2 by an operator approaching the shroud 4, a core support plate 5 is attached to the shroud 4, and a CRD housing 6 is welded to the reactor pressure vessel 1. The stub tube 7 is welded, and the ICM housing 8 is welded to the reactor pressure vessel 1. After that, the differential pressure detection / boric acid water injection pipe 17 is welded to the reactor pressure vessel 1 and the shroud 4, the ICM guide pipe 9 is inserted into the core support plate 5 hole, and then the ICM housing 8 is inserted.
After the worker approaches and welds the ICM guide tube 9 to the ICM
Fixed by the guide tube stabilizer 10, the upper lattice plate 13, the core spray pipe 11, and the feed water sparger 12 are carried in and installed in the reactor pressure vessel 1.
【０００５】また、供用期間中にシュラウド４，炉心支
持板５等の炉内構造物を新規製作の構造物と取替える場
合の据付け方法については、特開昭63−36195 号公報が
有る。Japanese Patent Laid-Open No. 63-36195 discloses an installation method for replacing the in-core structures such as the shroud 4 and the core support plate 5 with newly manufactured structures during the service period.
【０００６】特開昭63−36195 号公報により公知の原子
炉炉内構造物の取替工法はシュラウド４，上部格子板１
３，炉心支持板５の取替工法としては据付け後の機器の
信頼性，作業者の被ばく低減の観点より極めて有望な発
明といえる。The method of replacing the internal structure of a nuclear reactor known from Japanese Patent Laid-Open No. 63-36195 is a shroud 4, an upper grid plate 1
3. As a method of replacing the core support plate 5, it can be said that it is a very promising invention from the viewpoint of reliability of equipment after installation and reduction of worker exposure.
【０００７】[0007]
【発明が解決しようとする課題】従来の原子力発電プラ
ント建設時の炉内構造物据付けでは、炉心支持板５を前
記シュラウド４に取付け後、ＩＣＭ案内管９を前記炉心
支持板５の穴に搬入し、ＩＣＭハウジング８に溶接、そ
の後ＩＣＭ案内管スタビライザ１０で固定するため、Ｉ
ＣＭ案内管スタビライザ１０の据付けは事前にＩＣＭ案
内管９のＩＣＭハウジング８への溶接が終了しているこ
とが前提条件となり機器の据付けに比較的長時間を要し
た。また、シュラウド４のシュラウドサポート２への溶
接、およびＩＣＭ案内管９のＩＣＭハウジング７への溶
接はいずれも作業員が接近し手動溶接により実施してい
るため、シュラウド４のシュラウドサポート２への溶接
では芯出しが困難であり、ＩＣＭ案内管９のＩＣＭハウ
ジング８への溶接はプラント出力にもよるがＩＣＭ案内
管９およびＩＣＭハウジングは多数本あるので据付けに
比較的長時間を要した。In the conventional reactor internal structure installation at the time of construction of a nuclear power plant, after mounting the core support plate 5 on the shroud 4, the ICM guide pipe 9 is carried into the hole of the core support plate 5. Welded to the ICM housing 8 and then fixed with the ICM guide tube stabilizer 10.
The installation of the CM guide tube stabilizer 10 was premised on that the welding of the ICM guide tube 9 to the ICM housing 8 had been completed in advance, and it took a relatively long time to install the equipment. Further, since both the welding of the shroud 4 to the shroud support 2 and the welding of the ICM guide pipe 9 to the ICM housing 7 are carried out by manual welding by the worker, the welding of the shroud 4 to the shroud support 2 is performed. Centering is difficult, and the welding of the ICM guide tube 9 to the ICM housing 8 depends on the plant output, but since there are many ICM guide tubes 9 and ICM housings, it took a relatively long time to install.
【０００８】また、特開昭63−36195 号公報では、ＩＣ
Ｍ案内管９の取替えは前提としておらず、ＩＣＭ案内管
９までを取替える場合、新規ＩＣＭ案内管９の据付けに
長時間を要すこととなる。Further, in Japanese Patent Laid-Open No. 63-36195, an IC
The replacement of the M guide tube 9 is not a precondition, and when replacing the ICM guide tube 9, it takes a long time to install the new ICM guide tube 9.
【０００９】そこで本発明の目的は、新規建設プラント
では炉内構造物据付け工程の短縮を、また供用期間中に
シュラウド４，炉心支持板５等の炉内構造物を新規製作
の構造物と取替える場合には炉内構造物据付け工程の短
縮および作業者の被ばく低減を図る炉内構造物の据付け
法を提供することに有る。Therefore, an object of the present invention is to shorten the installation process of the in-core structure in a new construction plant, and replace the in-core structure such as the shroud 4 and the core support plate 5 with a newly manufactured structure during the service period. In some cases, the object is to provide a method for installing the internal structure of the furnace, which shortens the installation process of the internal structure and reduces the exposure of workers.
【００１０】[0010]
【課題を解決するための手段】上記目的を達成するため
に、本発明においては炉心支持板５，ＩＣＭ案内管９お
よびＩＣＭ案内管スタビライザ１０の各機器を予めシュ
ラウド４内に組込み前記シュラウド４と同時に原子炉圧
力容器１内に搬入する、または上記に加え上部格子板１
３をも予めシュラウド４内に組込み前記シュラウド４と
同時に原子炉圧力容器１内に搬入する。To achieve the above object, in the present invention, the core support plate 5, the ICM guide tube 9 and the ICM guide tube stabilizer 10 are installed in the shroud 4 in advance and the shroud 4 and At the same time, it is loaded into the reactor pressure vessel 1, or in addition to the above, the upper lattice plate 1
3 is also incorporated into the shroud 4 in advance and is carried into the reactor pressure vessel 1 at the same time as the shroud 4.
【００１１】さらに、シュラウド溶接機およびＩＣＭ案
内管溶接機を予めシュラウド４内に組込みシュラウドサ
ポート２の溶接を前記シュラウド４と同時に原子炉圧力
容器１内に搬入する。Further, the shroud welder and the ICM guide pipe welder are installed in the shroud 4 in advance, and the welding of the shroud support 2 is carried into the reactor pressure vessel 1 simultaneously with the shroud 4.
【００１２】さらにシュラウド溶接機，ＩＣＭ案内管溶
接機は複数の溶接ヘッドを有する自動溶接機とする。Further, the shroud welder and the ICM guide pipe welder are automatic welders having a plurality of welding heads.
【００１３】シュラウド４の据付けには芯測定機能を有
するシュラウド吊具兼芯測定装置を使用する。To install the shroud 4, a shroud hanger / core measuring device having a core measuring function is used.
【００１４】シュラウド４をシュラウドサポート２に固
定後、ＩＣＭ案内管９とＩＣＭハウジング８の溶接作業
および炉心スプレイ配管１１，低圧注水配管１４，給水
スパージャ１２の原子炉圧力容器１内への据付けを並行
して進める。After fixing the shroud 4 to the shroud support 2, the welding work of the ICM guide pipe 9 and the ICM housing 8 and the installation of the core spray pipe 11, the low pressure water injection pipe 14, and the feed water sparger 12 in the reactor pressure vessel 1 are carried out in parallel. And proceed.
【００１５】供用期間中にシュラウド４，炉心支持板５
等の炉内構造物を新規製作の構造物と取替える場合に
は、前記シュラウド４をシュラウドサポート２のレグ部
に固定した後の作業員の前記原子炉圧力容器１内への接
近は、再循環水出口ノズル１５，アクセスホール１６よ
り行う。Shroud 4, core support plate 5 during service
In the case of replacing the in-reactor structure with a newly manufactured structure, the worker after fixing the shroud 4 to the leg portion of the shroud support 2 is recirculated when approaching into the reactor pressure vessel 1. Water outlet nozzle 15 and access hole 16 are used.
【００１６】[0016]
【作用】請求項１においては、炉心支持板５，ＩＣＭ案
内管９およびＩＣＭ案内管スタビライザ１０の各機器
を、更に請求項２では上部格子板１３をも含め予めシュ
ラウド４内に組込み前記シュラウド４と同時に原子炉圧
力容器内１に搬入することにより、原子炉圧力容器内１
内での作業ステップが低減出来炉内構造物の据付け工程
短縮が図れる。また、供用期間中にシュラウド４，炉心
支持板５等の炉内構造物を新規製作の構造物と取替える
場合には、作業ステップの低減により作業員の被ばく低
減となる。According to the present invention, the core support plate 5, the ICM guide tube 9 and the ICM guide tube stabilizer 10 are incorporated into the shroud 4 in advance including the upper lattice plate 13 and the shroud 4 is incorporated. At the same time, by loading into the reactor pressure vessel 1,
The work steps inside can be reduced, and the installation process of the internal structure of the reactor can be shortened. Further, when the in-core structures such as the shroud 4 and the core support plate 5 are replaced with the newly manufactured structures during the service period, the number of work steps is reduced, which reduces the exposure of workers.
【００１７】請求項３〜６においては、シュラウド溶接
機，ＩＣＭ案内管溶接機を予めシュラウド４内に組込み
前記シュラウド４と同時に原子炉圧力容器１内に搬入す
ることにより、作業員が溶接機を設定するために原子炉
圧力容器１内の炉底部に接近する必要がなくなり、作業
ステップの低減および炉内構造物の据付け工程短縮が図
れる。また、供用期間中にシュラウド４，炉心支持板５
等の炉内構造物を新規製作の構造物と取替える場合に
は、作業ステップの低減により作業員の被ばく低減とな
る。In the third to sixth aspects, a shroud welder and an ICM guide pipe welder are installed in the shroud 4 in advance and carried into the reactor pressure vessel 1 at the same time as the shroud 4, so that the worker can weld the welder. Since it is not necessary to approach the bottom of the reactor pressure vessel 1 for setting, it is possible to reduce the work steps and the installation process of the reactor internals. Also, the shroud 4, the core support plate 5 during the service period
When replacing the in-furnace structure such as the one with a newly manufactured structure, the exposure of workers is reduced by reducing the work steps.
【００１８】請求項７においては、シュラウド４の原子
炉圧力容器１内への搬入をシュラウド吊具兼芯測定装置
を使用することでシュラウド４の据付け工程短縮が図れ
る。特に、供用期間中にシュラウド４，炉心支持板５等
の炉内構造物を新規製作の構造物と取替える場合には、
作業員が原子炉圧力容器１内に入りシュラウド４の芯調
整を行う必要は無くなり作業者の被ばく低減に効果的で
ある。According to the seventh aspect, the installation process of the shroud 4 can be shortened by using the shroud suspending tool and the core measuring device for loading the shroud 4 into the reactor pressure vessel 1. In particular, when replacing the in-core structures such as the shroud 4 and the core support plate 5 with newly manufactured structures during the service period,
It is not necessary for an operator to enter the reactor pressure vessel 1 to adjust the core of the shroud 4, which is effective in reducing the exposure of the operator.
【００１９】請求項８においては、作業者が原子炉圧力
容器１内の炉底部に接近するのに再循環水出口ノズルを
利用することで、特に供用期間中にシュラウド４，炉心
支持板５等の炉内構造物を新規製作の構造物と取替える
場合、高線量率となる炉心領域の原子炉圧力容器１とシ
ュラウド４との間を通過する必要がなくなり作業者の被
ばく低減に効果的である。In the present invention, the recirculation water outlet nozzle is used by the worker to approach the bottom of the reactor pressure vessel 1, so that the shroud 4, the core support plate 5, etc. can be used especially during the service period. When replacing the in-core structure with a newly manufactured structure, it is not necessary to pass between the reactor pressure vessel 1 and the shroud 4 in the core region where the dose rate is high, which is effective in reducing the exposure of workers. .
【００２０】請求項９においては、シュラウド４のシュ
ラウドサポート２のレグ部への据付け後の作業を並行作
業とすることで、炉内構造物の据付け工程短縮が図れ
る。According to the ninth aspect of the invention, the work after the installation of the shroud 4 on the leg portion of the shroud support 2 is performed in parallel, so that the installation process of the reactor internal structure can be shortened.
【００２１】請求項１０，１１においては、複数の溶接
ヘッドより構成されるシュラウド溶接機，ＩＣＭ案内管
溶接機を利用することで、シュラウド４およびＩＣＭ案
内管９の据付け工程短縮が図れる。更に、シュラウド４
の溶接を複数のヘッドで同時溶接とすることにより溶接
による倒れ量を制御することが出来る。According to the tenth and eleventh aspects, the installation process of the shroud 4 and the ICM guide pipe 9 can be shortened by using the shroud welder and the ICM guide pipe welder each including a plurality of welding heads. In addition, shroud 4
By performing simultaneous welding of multiple heads with a plurality of heads, the amount of tilt due to welding can be controlled.
【００２２】請求項１２，１３においては、シュラウド
溶接機およびＩＣＭ案内管溶接機を炉心支持板５穴より
搬出できる分割構造とすることで、シュラウド４をシュ
ラウドサポート２に、またＩＣＭ案内管９をＩＣＭハウ
ジング８に溶接後、炉心支持板５をシュラウド４より取
外すことなくそれぞれの溶接機を原子炉圧力容器１外に
搬出することが出来る。In the twelfth and thirteenth aspects, the shroud welder and the ICM guide pipe welder have a divided structure capable of being carried out from the core support plate 5 holes, so that the shroud 4 and the ICM guide pipe 9 are provided. After welding to the ICM housing 8, each welding machine can be carried out of the reactor pressure vessel 1 without removing the core support plate 5 from the shroud 4.
【００２３】請求項１４においては、シュラウド専用の
特殊溶接機を使用することにより、シュラウド溶接品質
の向上，溶接時間の短縮が図れる。According to the fourteenth aspect, by using the special welding machine dedicated to the shroud, the quality of the shroud welding can be improved and the welding time can be shortened.
【００２４】請求項１５においては、シュラウド専用の
吊具兼芯測定装置を使用することにより、シュラウド設
定時間の短縮が図れる。According to the fifteenth aspect, by using the suspension and core measuring device dedicated to the shroud, the shroud setting time can be shortened.
【００２５】[0025]
【実施例】以下、本発明の一実施例を図１〜図２０によ
り説明する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS.
【００２６】以下の説明は新規発電プラント建設時より
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
期間中にシュラウド４，炉心支持板５等の炉内構造物を
新規製作の構造物と取替える場合について記す。In the following description, the internal structure such as the shroud 4, the core support plate 5 and the like are newly manufactured during the service period in which the work is difficult due to various constraint conditions under the radiation environment as compared with the construction of the new power plant. The case of replacing with
【００２７】新規発電プラント建設時も同様な手法によ
り炉内構造物の据付けは可能である。Even when constructing a new power generation plant, it is possible to install the reactor internal structure by the same method.
【００２８】図１に本発明によるシュラウド４内にＩＣ
Ｍ案内管９，ＩＣＭ案内管スタビライザ１０，炉心支持
板５を組込んだ状況を示す。FIG. 1 shows an IC in the shroud 4 according to the present invention.
The situation where the M guide tube 9, the ICM guide tube stabilizer 10 and the core support plate 5 are incorporated is shown.
【００２９】ＩＣＭ案内管９はプラント出力により本数
が異なるが２９本〜６２本と複数本設けられており、そ
れぞれＩＣＭ案内管スタビライザ１０で水平方向に支持
されている。Although the number of ICM guide tubes 9 varies depending on the plant output, a plurality of ICM guide tubes 9 to 62 are provided, and each ICM guide tube 9 is horizontally supported by an ICM guide tube stabilizer 10.
【００３０】本発明では、シュラウド４を原子炉圧力容
器１に搬入する前にＩＣＭ案内管９をシュラウド４内に
組込まれた炉心支持板５の穴に挿入しＩＣＭ案内管スタ
ビライザ１０で固定し、ＩＣＭ案内管９を炉心支持板５
に仮止めしておく。In the present invention, before carrying the shroud 4 into the reactor pressure vessel 1, the ICM guide tube 9 is inserted into the hole of the core support plate 5 incorporated in the shroud 4 and fixed by the ICM guide tube stabilizer 10. Connect the ICM guide tube 9 to the core support plate 5
Temporarily stop at.
【００３１】図２にＩＣＭ案内管９とＩＣＭ案内管スタ
ビライザ１０の結合部の状況およびＩＣＭ案内管９設定
後の炉心支持板５，ＩＣＭハウジング８との取り合い状
況を示す。FIG. 2 shows the state of the joint between the ICM guide tube 9 and the ICM guide tube stabilizer 10 and the state of the connection between the core support plate 5 and the ICM housing 8 after the ICM guide tube 9 is set.
【００３２】ＩＣＭ案内管９はボルト１８およびＩＣＭ
案内管スタビライザ１０にてＩＣＭ案内管９同士水平方
向に結合されている。The ICM guide tube 9 includes a bolt 18 and an ICM.
ICM guide tubes 9 are horizontally connected to each other by a guide tube stabilizer 10.
【００３３】本発明によらず、従来の様にＩＣＭ案内管
９をＩＣＭハウジング８に溶接後原子炉圧力容器１内に
作業員が接近し、ＩＣＭ案内管スタビライザ１０をボル
ト１８で結合するのは員数が多数あり作業員の被ばく低
減上好ましいとは言えない。Not according to the present invention, after welding the ICM guide tube 9 to the ICM housing 8 as before, an operator approaches the inside of the reactor pressure vessel 1 and joins the ICM guide tube stabilizer 10 with the bolts 18. Since the number of workers is large, it cannot be said to be preferable in reducing the exposure of workers.
【００３４】図３にＩＣＭ案内管９を炉心支持板５に仮
止めした状況を示す。FIG. 3 shows a state in which the ICM guide tube 9 is temporarily fixed to the core support plate 5.
【００３５】同図に示す様にＩＣＭ案内管スタビライザ
１０をワイヤロープ１９にて炉心支持板５に仮吊りし、
シュラウド４をシュラウドサポート２に設置後ワイヤロ
ープ１９を緩めＩＣＭ案内管９を降下しＩＣＭハウジン
グ８に設定する。As shown in the figure, the ICM guide tube stabilizer 10 is temporarily suspended by the wire rope 19 on the core support plate 5,
After the shroud 4 is installed on the shroud support 2, the wire rope 19 is loosened and the ICM guide tube 9 is lowered to set the ICM housing 8.
【００３６】図３の例は１例でありこの他ＩＣＭ案内管
仮固定治具を使用することも出来る。The example of FIG. 3 is only one example, and an ICM guide tube temporary fixing jig can also be used.
【００３７】図４に本発明によるシュラウド４内にＩＣ
Ｍ案内管９，ＩＣＭ案内管スタビライザ１０，炉心支持
板５，上部格子板１３を組込み、更にＩＣＭ案内管自動
溶接機２０，シュラウド自動溶接機３０を組込んだ状況
を示す。FIG. 4 shows an IC in the shroud 4 according to the present invention.
The M guide tube 9, the ICM guide tube stabilizer 10, the core support plate 5, and the upper grid plate 13 are incorporated, and further the ICM guide tube automatic welding machine 20 and the shroud automatic welding machine 30 are incorporated.
【００３８】ＩＣＭ案内管自動溶接機２０はＩＣＭ案内
管９全数の下端に設定する。The ICM guide pipe automatic welding machine 20 is set at the lower end of all ICM guide pipes 9.
【００３９】また、シュラウド自動溶接機３０はシュラ
ウド４内面の下端に設定する。The shroud automatic welding machine 30 is set at the lower end of the inner surface of the shroud 4.
【００４０】図４の例ではＩＣＭ案内管溶接機２０を全
ＩＣＭ案内管に設定した例を示すが必ずしも全数設定す
る必要は無い。In the example of FIG. 4, the ICM guide pipe welding machine 20 is set to all the ICM guide pipes, but it is not always necessary to set all the ICM guide pipes.
【００４１】図５にＩＣＭ案内管自動溶接機２０の概念
図を示す。FIG. 5 shows a conceptual diagram of the ICM guide pipe automatic welding machine 20.
【００４２】ＩＣＭ案内管自動溶接機２０は、クランプ
兼本体２１，溶接機ガイド２２，溶接トーチ２３より構
成され、ケーブル２４にて電源２５，制御盤２６に接続
される。The ICM guide tube automatic welding machine 20 comprises a clamp / main body 21, a welding machine guide 22, and a welding torch 23, and is connected to a power source 25 and a control panel 26 by a cable 24.
【００４３】電源２５および制御盤２６は原子炉圧力容
器１外に設置することで作業者の被ばく低減を図れる。By installing the power supply 25 and the control panel 26 outside the reactor pressure vessel 1, it is possible to reduce the exposure of workers.
【００４４】図６にシュラウド自動溶接機３０の概念図
を示す。FIG. 6 shows a conceptual diagram of the shroud automatic welding machine 30.
【００４５】シュラウド自動溶接機３０は、ヘッド走行
モータ３１，ワイヤリール３２，左右位置決めセンサ３
３，アーク監視用カメラ３４，ＡＶＣモータ３５，オシ
レートモータ３６，溶接トーチ３７，ワイヤ送給モータ
４３より構成され、ヘッド走行レール３８に設置しケー
ブル３９により、電源４０、および制御盤４１に接続さ
れる。The automatic shroud welding machine 30 includes a head traveling motor 31, a wire reel 32, and a left and right positioning sensor 3.
3, an arc monitoring camera 34, an AVC motor 35, an oscillating motor 36, a welding torch 37, and a wire feeding motor 43, which are installed on a head traveling rail 38 and connected to a power source 40 and a control panel 41 by a cable 39. It
【００４６】ヘッド走行レール３８はシュラウド４内面
の下端にボルト４２で固定され、ヘッド走行モータ３１
によりヘッド走行レール３８上を左右（周方向）に移動
できる構造としている。The head traveling rail 38 is fixed to the lower end of the inner surface of the shroud 4 with bolts 42, and the head traveling motor 31
Thus, the head traveling rail 38 can be moved left and right (circumferential direction).
【００４７】また溶接トーチ３７の上下，前後の移動は
オシレートモータ３６、およびAVCモータ３５により行
いアーク監視用カメラ３４にて溶接状況を確認する。The welding torch 37 is moved up and down and back and forth by the oscillating motor 36 and the AVC motor 35, and the welding condition is confirmed by the arc monitoring camera 34.
【００４８】電源４０および制御盤４１はケーブル３９
によりシュラウド自動溶接機３０に接続され、原子炉圧
力容器１外に設置することで作業員の被ばく低減を図れ
る。図６に示す様にシュラウド自動溶接機３０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４の溶接による倒れを少なくし、また溶接作業時間
の短縮も図れる。The power source 40 and the control panel 41 are cables 39
Thus, it is connected to the shroud automatic welding machine 30 and installed outside the reactor pressure vessel 1 to reduce the exposure of workers. As shown in FIG. 6, the shroud automatic welding machine 30 is composed of 4 sets, and by welding 4 sets at the same time, the fall of the shroud 4 due to welding can be reduced and the welding work time can be shortened.
【００４９】図６に示す例は、４セットで構成されるシ
ュラウド自動溶接機３０の例であるが、６セット，８セ
ットでシュラウド自動溶接機３０を構成することも可能
で有る。The example shown in FIG. 6 is an example of the shroud automatic welding machine 30 composed of 4 sets, but it is also possible to construct the shroud automatic welding machine 30 with 6 sets or 8 sets.
【００５０】シュラウド自動溶接機３０の原子炉圧力容
器１外への搬出は作業員が原子炉圧力容器１内に接近し
走行レール３８よりシュラウド自動溶接機３０をおよび
ケーブル３９を取外し、ボルト４２を緩め走行レール３
８をシュラウド４より取外し分解することで炉心支持板
５穴より搬出できる。To carry out the automatic shroud welder 30 to the outside of the reactor pressure vessel 1, an operator approaches the inside of the reactor pressure vessel 1, removes the shroud automatic welder 30 and the cable 39 from the traveling rail 38, and attaches the bolt 42. Loosen running rail 3
By removing 8 from the shroud 4 and disassembling it, it can be carried out from the hole 5 of the core support plate.
【００５１】走行レール３８は予め炉心支持板５穴より
搬出できる分割数とし、またシュラウド自動溶接機３０
も炉心支持板５穴より搬出できる様コンパクトな構造と
する。The traveling rails 38 are divided in advance so that they can be carried out through the five holes in the core support plate, and the automatic shroud welding machine 30 is used.
Also has a compact structure so that it can be carried out from the core support plate 5 holes.
【００５２】また、図示は省略するが走行レール３８は
シュラウド４と一体構造とし取外し不要とすることも可
能で有る。Although not shown, the traveling rail 38 may be integrally formed with the shroud 4 and may not be detached.
【００５３】図７に図１に示すシュラウド４内にＩＣＭ
案内管９，ＩＣＭ案内管スタビライザ１０，炉心支持板
５を組込んだ炉内構造物を原子炉建屋内の原子炉圧力容
器１内に搬入する搬入手順を示す。FIG. 7 shows an ICM in the shroud 4 shown in FIG.
The carrying-in procedure for carrying in the reactor internal structure incorporating the guide tube 9, the ICM guide tube stabilizer 10, and the core support plate 5 into the reactor pressure vessel 1 in the reactor building is shown.
【００５４】上記炉内構造物を組込んだシュラウド４を
原子炉建屋の大物搬入口５０より天井クレーン（図示せ
ず）により原子炉ウェル５１に設置する。The shroud 4 incorporating the above-mentioned reactor internals is installed in the reactor well 51 from the large object inlet 50 of the reactor building by an overhead crane (not shown).
【００５５】原子炉ウェル５１には予め遮蔽兼架台５２
を設置しシュラウド４を仮置きする。In the reactor well 51, a shield / stand 52 is provided in advance.
Is installed and the shroud 4 is temporarily placed.
【００５６】遮蔽兼架台５２に仮置したシュラウド４に
ＩＣＭ案内管自動溶接機２０，シュラウド自動溶接機３
０の設定を行い、次にシュラウド遮蔽体５３を設定す
る。The ICM guide pipe automatic welding machine 20 and the shroud automatic welding machine 3 are attached to the shroud 4 temporarily placed on the shielding / mounting base 52.
0 is set, and then the shroud shield 53 is set.
【００５７】その後シュラウド吊具兼芯測定装置６０を
シュラウド４の上面に取付けシュラウド４の原子炉圧力
容器１内への搬入準備が完了となる。Thereafter, the shroud suspending device / core measuring device 60 is attached to the upper surface of the shroud 4, and the preparation for carrying the shroud 4 into the reactor pressure vessel 1 is completed.
【００５８】図７ではシュラウド内にシュラウド遮蔽体
５３を組込んだ状況を示すが、新規プラントの建設では
シュラウド遮蔽体５３は不要である。FIG. 7 shows the situation in which the shroud shield 53 is incorporated in the shroud, but the shroud shield 53 is not necessary in the construction of a new plant.
【００５９】また、上部格子板１３を予めシュラウド４
内に組込むことも可能である（図示せず。）。Further, the upper grid plate 13 is previously attached to the shroud 4
It is also possible to incorporate in (not shown).
【００６０】図８にシュラウド吊具兼芯測定装置６０の
概念図を示す。FIG. 8 shows a conceptual diagram of the shroud suspension / core measuring device 60.
【００６１】シュラウド吊具兼芯測定装置６０は、電動
チェーンブロック６１，ベース６２，旋回テーブル６
３，Ｘテーブル６４，Ｙテーブル６５，旋回駆動装置６
６，Ｘ方向駆動装置６７，Ｙ方向駆動装置６８、および
芯測定装置６９より構成される。The shroud suspending device / core measuring device 60 comprises an electric chain block 61, a base 62, and a turning table 6.
3, X table 64, Y table 65, turning drive device 6
6, an X-direction driving device 67, a Y-direction driving device 68, and a core measuring device 69.
【００６２】シュラウド４の原子炉圧力容器１への搬入
はシュラウド吊具兼芯測定装置６０のベース６２を原子
炉圧力容器フランジ５４に設定する。The shroud 4 is carried into the reactor pressure vessel 1 by setting the base 62 of the shroud suspension / core measuring device 60 on the reactor pressure vessel flange 54.
【００６３】その後４セットの電動チューンブロック６
１にて吊り下げられたシュラウド４を電動チューンブロ
ック６１により原子炉圧力容器１内を降下しシュラウド
サポート２のシリンダ部上に設定する。After that, four sets of electric tune blocks 6
The shroud 4 suspended at 1 is lowered in the reactor pressure vessel 1 by the electric tune block 61 and set on the cylinder portion of the shroud support 2.
【００６４】シュラウド４の芯設定要領の図示は省略す
るがＣＲＤスタブチューブ７の芯に対し所定の公差に入
るように設定する必要があり、シュラウド吊具兼芯測定
装置６０の４セットの電動チューンブロック６１，旋回
駆動装置６６，Ｘ方向駆動装置６７，Ｙ方向駆動装置６
８により調整することで可能となる。Although illustration of the core setting procedure of the shroud 4 is omitted, it is necessary to set it so that it falls within a predetermined tolerance with respect to the core of the CRD stub tube 7. Block 61, turning drive device 66, X-direction drive device 67, Y-direction drive device 6
It becomes possible by adjusting with 8.
【００６５】芯測定は芯測定装置６９により行う。The core measurement is performed by the core measuring device 69.
【００６６】芯測定要領の詳細は特開昭63−36195 号に
記載の方法に準ずる。Details of the core measuring procedure are based on the method described in JP-A-63-36195.
【００６７】シュラウド吊具兼芯測定装置６０によりシ
ュラウド４の芯測定を行い所定の公差内にシュラウド４
の芯を設定後図９に示す様にシュラウド４外面と原子炉
圧力容器１内面間にシュラウド４固定用の水圧ジャッキ
７０を設定する。The core of the shroud 4 is measured by the shroud suspending device / core measuring device 60, and the shroud 4 is kept within a predetermined tolerance.
After the core is set, a hydraulic jack 70 for fixing the shroud 4 is set between the outer surface of the shroud 4 and the inner surface of the reactor pressure vessel 1 as shown in FIG.
【００６８】水圧ジャッキ７０はシュラウド４の下端部
近傍および上端部近傍それぞれ円周方向に３セット以上
設置しシュラウド４を固定する。Three or more sets of hydraulic jacks 70 are installed in the circumferential direction near the lower end and near the upper end of the shroud 4 to fix the shroud 4.
【００６９】本発明では、シュラウド４の芯設定後に水
圧ジャッキ７０を設定する例を示すが、図７に示す原子
炉ウェル５１の遮蔽兼架台５２にシュラウド４を仮置き
した状態で予めシュラウド４外面に水圧ジャッキ７０を
設定することも可能で有る。図９は本発明によるシュラ
ウド４据付けの概念を示す。The present invention shows an example in which the hydraulic jack 70 is set after the core of the shroud 4 is set. However, the outer surface of the shroud 4 is preliminarily placed in a state in which the shroud 4 is temporarily placed on the shielding / mounting base 52 of the reactor well 51 shown in FIG. It is also possible to set the water pressure jack 70 on the. FIG. 9 illustrates the concept of shroud 4 installation according to the present invention.
【００７０】図９に示すシュラウド吊具兼芯測定装置６
０，シュラウド自動溶接機３０はいずれも模式的に記し
たもので詳細は図６および図８による。Shroud lifting device and core measuring device 6 shown in FIG.
0 and the shroud automatic welding machine 30 are all shown schematically, and details are shown in FIGS. 6 and 8.
【００７１】また、本図においてはＩＣＭ案内管９，Ｉ
ＣＭ案内管スタビライザ１０および炉心支持板５の記載
は省略した。Further, in this figure, the ICM guide tubes 9, I
The description of the CM guide tube stabilizer 10 and the core support plate 5 is omitted.
【００７２】シュラウド４をシュラウドサポート２に設
定後シュラウド自動溶接機３０によりシュラウド４とシ
ュラウドサポート２の溶接後水圧ジャッキ７０およびシ
ュラウド自動溶接機３０は原子炉圧力容器１外に搬出す
る。After the shroud 4 is set on the shroud support 2, the shroud 4 and the shroud support 2 after welding the hydraulic jack 70 and the shroud automatic welder 30 are carried out of the reactor pressure vessel 1 by the shroud automatic welding machine 30.
【００７３】その後炉心支持板５の芯測定をシュラウド
吊具兼芯測定装置６０の芯測定装置６９により行い、炉
心支持板５をシュラウド４に設定する。After that, the core of the core supporting plate 5 is measured by the core measuring device 69 of the shroud suspender / core measuring device 60, and the core supporting plate 5 is set to the shroud 4.
【００７４】炉心支持板の芯測定要領の詳細も特開昭63
−36195 号に記載の方法に準ずる。炉心支持板５設定後
に差圧検出／ほう酸水注入管１７を原子炉圧力容器１内
に搬入し溶接する。The details of the core measuring method of the core support plate are also disclosed in JP-A-63-63.
Follow the method described in −36195. After setting the core support plate 5, the differential pressure detection / boric acid water injection pipe 17 is carried into the reactor pressure vessel 1 and welded.
【００７５】その後ＩＣＭ案内管９とＩＣＭハウジング
８の溶接を図５に示すＩＣＭ案内管自動溶接機２０によ
り行い、ＩＣＭ案内管自動溶接機２０を原子炉圧力容器
１外に搬出する。After that, the ICM guide tube 9 and the ICM housing 8 are welded by the ICM guide tube automatic welding machine 20 shown in FIG. 5, and the ICM guide tube automatic welding machine 20 is carried out of the reactor pressure vessel 1.
【００７６】その後上部格子板１３をシュラウド４に設
定するが、供用期間中にシュラウド４等の炉内構造物を
取替えるケースでは、上部格子板１３設定前にシュラウ
ド遮蔽体５３の搬出を行う。After that, the upper lattice plate 13 is set to the shroud 4, but in the case where the reactor internal structure such as the shroud 4 is replaced during the service period, the shroud shield 53 is carried out before the upper lattice plate 13 is set.
【００７７】シュラウド遮蔽体５３搬出完了後、上部格
子板１３をシュラウド４内に搬入し芯測定を行いシュラ
ウド４に固定する。After carrying out the shroud shield 53, the upper lattice plate 13 is carried into the shroud 4, the core is measured, and the shroud 4 is fixed.
【００７８】その後炉心スプレイ配管１１，給水スパー
ジャ１２の据付けを行う。Thereafter, the core spray pipe 11 and the water supply sparger 12 are installed.
【００７９】本発明の一実施例による据付け手順を図１
０に示す。FIG. 1 shows an installation procedure according to an embodiment of the present invention.
0 is shown.
【００８０】図１１に本発明の他の実施例による炉内構
造物の据付け手順を示す。FIG. 11 shows a procedure for installing the reactor internal structure according to another embodiment of the present invention.
【００８１】図１１に示す様に、本実施例ではシュラウ
ド４のシュラウドサポート２への溶接完了後炉底部の作
業（例えばＩＣＭ案内管９のＩＣＭハウジング８との溶
接）と炉上部の作業（例えば炉心スプレイ配管１１の据
付け）を並行して進めるケースを示し、図１０のケース
に比し炉内構造物の据付け工程上有利といえる。As shown in FIG. 11, in the present embodiment, after the welding of the shroud 4 to the shroud support 2 is completed, the work of the furnace bottom (for example, the welding of the ICM guide tube 9 with the ICM housing 8) and the work of the upper part of the furnace (for example, The case of advancing the installation of the core spray pipe 11) in parallel is shown, which can be said to be advantageous in the installation process of the in-core structure as compared with the case of FIG.
【００８２】図１２に従来の炉内構造物の据付け手順の
一例を示す。FIG. 12 shows an example of a conventional procedure for installing internal furnace structures.
【００８３】本手順では順次シュラウド４，炉心支持板
５，差圧検出／ほう酸水注入配管１７，ＩＣＭ案内管
９，ＩＣＭ案内管スタビライザ１０，上部格子板１３，
炉心スプレイ配管１１，給水スパージャ１２の据付けを
行うケースで、作業員の炉底部への接近は５回と成る。In this procedure, the shroud 4, core support plate 5, differential pressure detection / boric acid water injection pipe 17, ICM guide pipe 9, ICM guide pipe stabilizer 10, upper grid plate 13,
In the case where the core spray pipe 11 and the water supply sparger 12 are installed, an operator approaches the bottom of the reactor 5 times.
【００８４】一方、本発明による図１０および図１１の
ケースでは作業員の炉底部への接近は１回と、供用期間
中にシュラウド４，炉心支持板５等の炉内構造物を新規
製作の構造物と取替える場合、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１２に示す従来
の据付け手順に比し有利と言える。On the other hand, in the case of FIGS. 10 and 11 according to the present invention, the worker approaches the bottom of the reactor once, and during the period of service, the shroud 4, core support plate 5 and other in-core structures are newly manufactured. When replacing with a structure, 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. 12 from the viewpoint of reducing the exposure of the worker.
【００８５】また、作業ステップ上も本発明による図１
０，図１１に示すケースが従来の図１２に示すケースに
比し少なく炉内構造物据付け工程の面でも有利といえ
る。The working steps are also shown in FIG.
0, the case shown in FIG. 11 is less than the case shown in FIG. 12 of the related art, and it can be said that the case shown in FIG.
【００８６】図１０〜図１３は低圧注水配管１４の無い
プラントの例を示すが、低圧注水配管１４が有っても同
様なことが言える。10 to 13 show an example of a plant without the low-pressure water injection pipe 14, the same can be said with the low-pressure water injection pipe 14.
【００８７】また、いずれも模式的に主要作業手順のみ
記した。Further, in each case, only the main work procedure is schematically shown.
【００８８】図１３に再循環水出口ノズル１５，アクセ
スホール１６より炉底部に作業員が接近する場合のアク
セスルートを示す。FIG. 13 shows an access route when a worker approaches the bottom of the furnace through the recirculation water outlet nozzle 15 and the access hole 16.
【００８９】図中に記載の寸法は代表的な原子力発電プ
ラントでの例で同図に示す様に作業員は低圧注水配管１
４から原子炉圧力容器１，アクセスホール１６，足場５
５，シュラウドサポート２開口部を通過し炉底部に接近
することが可能で有る。The dimensions shown in the figure are examples of a typical nuclear power plant, and as shown in FIG.
4 to reactor pressure vessel 1, access hole 16, scaffold 5
5, It is possible to pass through the opening of the shroud support 2 and approach the bottom of the furnace.
【００９０】図１４から図２０に低圧注水配管１４の無
いプラントでの通常ケースの炉内構造物の据付け手順
（シュラウド４以降の手順）図を示す。14 to 20 are diagrams showing the installation procedure (procedure after the shroud 4) of the internal structure of the normal case in the plant without the low-pressure water injection pipe 14.
【００９１】図１４にシュラウド４の据付けが完了した
状況を示す。FIG. 14 shows a situation in which the installation of the shroud 4 has been completed.
【００９２】図１５に炉心支持板５の据付けが完了した
状況を示す。FIG. 15 shows a situation in which the installation of the core support plate 5 is completed.
【００９３】図１６に差圧検出／ほう酸水注入管１７の
据付けが完了した状況を示す。FIG. 16 shows a state in which the differential pressure detection / borate water injection pipe 17 is completely installed.
【００９４】図１７にＩＣＭ案内管９の据付けが完了し
た状況を示す。FIG. 17 shows the situation where the installation of the ICM guide tube 9 is completed.
【００９５】図１８にＩＣＭ案内管スタビライザ１０の
据付けが完了した状況を示す。FIG. 18 shows a state where the installation of the ICM guide tube stabilizer 10 is completed.
【００９６】図１９に上部格子板１３の据付けが完了し
た状況を示す。FIG. 19 shows a situation in which the installation of the upper grid plate 13 is completed.
【００９７】図２０に炉心スプレイ配管１１および給水
スパージャ１２の据付けが完了した状況を示す。FIG. 20 shows a situation in which the installation of the core spray pipe 11 and the water supply sparger 12 is completed.
【００９８】以上の実施例では、以下の利点がある。The above embodiment has the following advantages.
【００９９】炉心支持板５，上部格子板１３，ＩＣＭ案
内管９およびＩＣＭ案内管スタビライザ１０の各機器お
よびシュラウド溶接機，ＩＣＭ案内管溶接機を予めシュ
ラウド４内に組込み前記シュラウド４と一体で原子炉圧
力容器１内に搬入することにより、原子炉圧力容器１内
での作業ステップが低減出来炉内構造物の据付け工程短
縮，作業員の被ばく低減となる。The core support plate 5, the upper lattice plate 13, the ICM guide tube 9 and the ICM guide tube stabilizer 10, the shroud welder, and the ICM guide tube welder are installed in the shroud 4 in advance and integrated with the shroud 4. By loading into the reactor pressure vessel 1, the work steps in the reactor pressure vessel 1 can be reduced, and the installation process of the reactor internal structure can be shortened and the exposure of workers can be reduced.
【０１００】また、シュラウド４の原子炉圧力容器１内
への搬入をシュラウド吊具兼芯測定装置を使用すること
でシュラウド４の据付け工程短縮，作業者の被ばく低減
に効果的である。Further, by using the shroud suspending tool and the core measuring device for loading the shroud 4 into the reactor pressure vessel 1, it is effective in shortening the installation process of the shroud 4 and reducing the exposure of the worker.
【０１０１】また、作業者が原子炉圧力容器１内の炉底
部に接近するのに再循環水出口ノズルを利用すること
で、特に供用期間中にシュラウド４，炉心支持板５等の
炉内構造物を新規製作の構造物と取替える場合、高線量
率となる炉心領域の原子炉圧力容器１とシュラウド４と
の間を通過する必要がなくなり作業者の被ばく低減に効
果的である。Further, since the worker uses the recirculation water outlet nozzle to approach the bottom of the reactor pressure vessel 1, the internal structure of the shroud 4, the core support plate 5, etc. can be improved especially during the service period. When the object is replaced with a newly manufactured structure, it is not necessary to pass between the reactor pressure vessel 1 and the shroud 4 in the core region where the dose rate is high, which is effective in reducing the exposure of the worker.
【０１０２】また、シュラウド４のシュラウドサポート
２のレグ部への据付け後の作業を並行作業とすること
で、炉内構造物の据付け工程短縮が図れる。Further, by performing the work after the installation of the shroud 4 on the leg portion of the shroud support 2 in parallel, the installation process of the reactor internal structure can be shortened.
【０１０３】また、複数の溶接ヘッドより構成されるシ
ュラウド溶接機，ＩＣＭ案内管溶接機を利用すること
で、工程短縮が図れ、更に、シュラウド４の溶接を複数
のヘッドで同時溶接とすることにより溶接による倒れ量
を制御することが出来る。Further, by using a shroud welder and an ICM guide pipe welder composed of a plurality of welding heads, the process can be shortened, and further, the shroud 4 can be welded simultaneously by a plurality of heads. The amount of tilt due to welding can be controlled.
【０１０４】[0104]
【発明の効果】本発明による各据付け方法によれば、原
子炉圧力容器内での作業ステップが低減出来炉内構造物
の据付け工程短縮，作業員の被ばく低減となる。According to each installation method of the present invention, the work steps in the reactor pressure vessel can be reduced, the installation process of the internal structure of the reactor can be shortened, and the exposure of workers can be reduced.
【０１０５】本発明による原子炉シュラウド溶接機によ
れば、原子炉シュラウドを溶接するに好適な溶接機が提
供できて、本発明による据付け方法の迅速化を助長する
ことが出来る。According to the reactor shroud welding machine of the present invention, a welding machine suitable for welding the reactor shroud can be provided, and the installation method of the present invention can be accelerated.
【０１０６】本発明による原子炉シュラウド吊具兼芯測
定装置によれば、本発明による据付け方法の迅速化を助
長することが出来る。According to the reactor shroud hanger / core measuring apparatus of the present invention, it is possible to promote the speeding up of the installation method of the present invention.
【図１】シュラウド内に炉内構造物を組込んだ状態のシ
ュラウド縦断面図。FIG. 1 is a vertical cross-sectional view of a shroud in which a reactor internal structure is incorporated in the shroud.
【図２】ＩＣＭ案内管とその他機器の取り合い状況を示
したシュラウド縦断面図。FIG. 2 is a vertical cross-sectional view of a shroud showing a state of connection between an ICM guide tube and other devices.
【図３】ＩＣＭ案内管のシュラウド内仮吊り状態におけ
るシュラウド縦断面図。FIG. 3 is a longitudinal sectional view of the shroud of the ICM guide tube in a temporarily suspended state inside the shroud.
【図４】シュラウド内に溶接機を組込んだ状態のシュラ
ウド縦断面図。FIG. 4 is a vertical cross-sectional view of a shroud in which a welding machine is incorporated in the shroud.
【図５】ＩＣＭ案内管自動溶接機の説明図。FIG. 5 is an explanatory view of an ICM guide pipe automatic welding machine.
【図６】シュラウド自動溶接機の説明図。FIG. 6 is an explanatory view of an automatic shroud welding machine.
【図７】シュラウドの原子炉圧力容器内への吊り込み搬
入状態を示す図であり、（ａ）図は芯測定兼吊具でシュ
ラウドを吊っている状態図を示し、（ｂ）図は吊り込み
搬入手順を示す図。FIG. 7 is a diagram showing a state in which the shroud is suspended and loaded into the reactor pressure vessel, FIG. 7A shows a state diagram in which the shroud is suspended by the core measuring and suspending tool, and FIG. The figure which shows the carry-in procedure.
【図８】芯測定兼吊具を示しており、（ａ）図は立面図
であり、（ｂ）図は（ａ）図のＡ−Ａ矢視上平面図であ
る。8A and 8B show a lead measuring and suspending tool, wherein FIG. 8A is an elevational view, and FIG. 8B is a plan view taken along the line AA of FIG. 8A.
【図９】シュラウド据付け説明図。FIG. 9 is an explanatory diagram of shroud installation.
【図１０】炉内構造物据付け工程図。FIG. 10 is a process diagram for installing the internal structure of the furnace.
【図１１】他の例による炉内構造物据付け工程図。FIG. 11 is a process diagram for installing the internal structure of the reactor according to another example.
【図１２】従来の炉内構造物据付け工程図。FIG. 12 is a process diagram of a conventional in-core structure installation process.
【図１３】炉底部への作業者アクセスルート説明図。FIG. 13 is an explanatory diagram of an operator access route to the bottom of the furnace.
【図１４】シュラウド据付け完了状況を示す原子炉圧力
容器縦断面図。FIG. 14 is a vertical cross-sectional view of the reactor pressure vessel showing the completion of shroud installation.
【図１５】炉心支持板据付け完了状況を示す原子炉圧力
容器縦断面図。FIG. 15 is a vertical cross-sectional view of the reactor pressure vessel showing the completion of installation of the core support plate.
【図１６】差圧検出／ほう酸水注入管据付け完了状況を
示す原子炉圧力容器縦断面図。FIG. 16 is a vertical cross-sectional view of a reactor pressure vessel showing the completion of differential pressure detection / boric acid water injection pipe installation.
【図１７】ＩＣＭ案内管据付け完了状況を示す原子炉圧
力容器縦断面図。FIG. 17 is a vertical cross-sectional view of the reactor pressure vessel showing the installation completion status of the ICM guide tube.
【図１８】ＩＣＭ案内管スタビライザ据付け完了状況を
示す原子炉圧力容器縦断面図。FIG. 18 is a vertical cross-sectional view of the reactor pressure vessel showing the installation completion status of the ICM guide tube stabilizer.
【図１９】上部格子板据付け完了状況を示す原子炉圧力
容器縦断面図。FIG. 19 is a vertical cross-sectional view of the reactor pressure vessel showing the completion of installation of the upper lattice plate.
【図２０】炉心スプレイ配管，給水スパージャ据付け完
了状況を示す原子炉圧力容器縦断面図。FIG. 20 is a vertical cross-sectional view of the reactor pressure vessel showing the installation completion status of the core spray piping and the feedwater sparger.
【図２１】従来の原子力発電プラント建設時の概略手順
図。FIG. 21 is a schematic procedure diagram when constructing a conventional nuclear power plant.
１…原子炉圧力容器、２…シュラウドサポート、３…ジ
ェットポンプ、４…シュラウド、５…炉心支持板、６…
ＣＲＤハウジング、７…ＣＲＤスタブチューブ、８…Ｉ
ＣＭハウジング、９…ＩＣＭ案内管、１０…ＩＣＭ案内
管スタビライザ、１１…炉心スプレイ配管、１２…給水
スパージャ、１３…上部格子板、１４…低圧注水配管、
１５…再循環水出口ノズル、１６…アクセスホール、１
７…差圧検出／ほう酸水注入管、１８，４２…ボルト、
１９…ワイヤロープ、２０…ICM案内管自動溶接機、２
１…クランプ兼本体、２２…溶接機ガイド、２３，３７
…溶接トーチ、２４，３９…ケーブル、２５，４０…電
源、２６，４１…制御盤、３０…シュラウド自動溶接
機、３１…ヘッド走行モータ、３２…ワイヤリール、３
３…左右位置決めセンサ、３４…アーク監視用カメラ、
３５…ＡＶＣモータ、３６…オシレートモータ、３８…
ヘッド走行レール、４３…ワイヤ送給モータ、５０…大
物搬入口、５１…原子炉ウェル、５２…遮蔽兼架台、５
３…シュラウド遮蔽体、５４…原子炉圧力容器フラン
ジ、５５…足場、６０…シュラウド吊具兼芯測定装置、
６１…電動チューンブロック、６２…ベース、６３…旋
回テーブル、６４…Ｘテーブル、６５…Ｙテーブル、６
６…旋回駆動装置、６７…Ｘ方向駆動装置、６８…Ｙ方
向駆動装置、６９…芯測定装置、７０…水圧ジャッキ。1 ... Reactor pressure vessel, 2 ... Shroud support, 3 ... Jet pump, 4 ... Shroud, 5 ... Core support plate, 6 ...
CRD housing, 7 ... CRD stub tube, 8 ... I
CM housing, 9 ... ICM guide tube, 10 ... ICM guide tube stabilizer, 11 ... Core spray piping, 12 ... Water supply sparger, 13 ... Upper lattice plate, 14 ... Low pressure water injection piping,
15 ... Recirculating water outlet nozzle, 16 ... Access hole, 1
7 ... Differential pressure detection / boric acid water injection pipe, 18, 42 ... Bolt,
19 ... Wire rope, 20 ... ICM automatic guide pipe welding machine, 2
1 ... Clamp and main body, 22 ... Welder guide, 23, 37
... welding torch, 24, 39 ... cable, 25, 40 ... power supply, 26, 41 ... control board, 30 ... automatic shroud welder, 31 ... head traveling motor, 32 ... wire reel, 3
3 ... Left / right positioning sensor, 34 ... Arc monitoring camera,
35 ... AVC motor, 36 ... Oscillating motor, 38 ...
Head traveling rail, 43 ... Wire feeding motor, 50 ... Large-sized material carrying-in port, 51 ... Reactor well, 52 ... Shielding / mounting stand, 5
3 ... Shroud shield, 54 ... Reactor pressure vessel flange, 55 ... Scaffolding, 60 ... Shroud suspension and core measuring device,
61 ... Electric tune block, 62 ... Base, 63 ... Turning table, 64 ... X table, 65 ... Y table, 6
6 ... Revolving drive device, 67 ... X-direction drive device, 68 ... Y-direction drive device, 69 ... Core measuring device, 70 ... Hydraulic jack.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 黒沢 孝一 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 古川 秀康 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 千葉 功男 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 菊地 敏一 茨城県日立市幸町三丁目２番２号 日立ニ ュークリアエンジニアリング株式会社内 (72)発明者 真鍋 二三夫 広島県呉市宝町６番９号 バブコック日立 株式会社呉工場内 (72)発明者 近藤 由▲英▼ 広島県呉市宝町６番９号 バブコック日立 株式会社呉工場内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Koichi Kurosawa 3-1-1, Saiwaicho, Hitachi-shi, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Hideyasu Furukawa 3-chome, Saiwaicho, Hitachi, Ibaraki No. 1 Hitachi Ltd., Hitachi Plant (72) Inventor Isao Chiba 3-1-1, Saiwaicho, Hitachi City, Ibaraki Hitachi Ltd. Hitachi Ltd., Hitachi Plant (72) Inventor Toshikazu Kikuchi Hitachi, Ibaraki Prefecture 2-2, 3-chome, Saiwaicho, Hitachi (72) Inventor Fumio Manabe 6-9 Takara-cho, Kure-shi, Hiroshima Babcock Hitachi Ltd. Kure Factory (72) Inventor Yoshi Kondo ▼ 6-9 Takaracho, Kure-shi, Hiroshima Babcock Hitachi Kure factory
Claims (15)
おいて、炉心支持板，ＩＣＭ案内管およびＩＣＭ案内管
スタビライザの各機器を予めシュラウド内に組込み前記
シュラウドと同時に前記原子炉圧力容器内に搬入するこ
とを特徴とする原子炉内構造物の据付け方法。1. In a reactor internal structure in a boiling water reactor pressure vessel, core support plate, ICM guide tube, and ICM guide tube stabilizer are incorporated in a shroud in advance, and the reactor pressure vessel is installed at the same time as the shroud. A method for installing internal structures of a nuclear reactor, which is characterized in that the internal structure is carried in.
おいて、上部格子板，炉心支持板，ＩＣＭ案内管および
ＩＣＭ案内管スタビライザの各機器を予めシュラウド内
に組込み前記シュラウドと同時に前記原子炉圧力容器内
に搬入することを特徴とする原子炉内構造物の据付け方
法。2. In a reactor internal structure in a boiling water reactor pressure vessel, the upper lattice plate, the core support plate, the ICM guide tube, and the ICM guide tube stabilizer are incorporated in advance in the shroud and at the same time as the shroud. A method for installing a reactor internal structure, which is characterized in that it is carried into a reactor pressure vessel.
おいて、炉心支持板，ＩＣＭ案内管およびＩＣＭ案内管
スタビライザの各機器、およびシュラウド溶接機を予め
シュラウド内に組込み前記シュラウドと同時に前記原子
炉圧力容器内に搬入することを特徴とする原子炉内構造
物の据付け方法。3. In a reactor internal structure in a boiling water reactor pressure vessel, core support plate, ICM guide tube and ICM guide tube stabilizer equipment, and a shroud welder are installed in the shroud in advance and at the same time as the shroud. A method of installing a reactor internal structure, which is characterized in that it is carried into the reactor pressure vessel.
おいて、上部格子板，炉心支持板，ＩＣＭ案内管および
ＩＣＭ案内管スタビライザの各機器、およびシュラウド
溶接機を予めシュラウド内に組込み前記シュラウドと同
時に前記原子炉圧力容器内に搬入することを特徴とする
原子炉内構造物の据付け方法。4. In a reactor internal structure in a boiling water reactor pressure vessel, an upper lattice plate, a core support plate, ICM guide tubes, ICM guide tube stabilizers, and a shroud welder are installed in advance in the shroud. A method for installing a reactor internal structure, which is carried into the reactor pressure vessel at the same time as the shroud.
おいて、炉心支持板，ＩＣＭ案内管およびＩＣＭ案内管
スタビライザの各機器、およびＩＣＭ案内管溶接機を予
めシュラウド内に組込み前記シュラウドと同時に前記原
子炉圧力容器内に搬入することを特徴とする原子炉内構
造物の据付け方法。5. In a reactor internal structure in a boiling water reactor pressure vessel, a core support plate, ICM guide tube and ICM guide tube stabilizer equipment, and an ICM guide tube welder are previously installed in the shroud. At the same time, it is carried into the reactor pressure vessel, and a method for installing a reactor internal structure.
おいて、上部格子板，炉心支持板，ＩＣＭ案内管および
ＩＣＭ案内管スタビライザの各機器、およびＩＣＭ案内
管溶接機を予めシュラウド内に組込み前記シュラウドと
同時に前記原子炉圧力容器内に搬入することを特徴とす
る原子炉内構造物の据付け方法。6. In a reactor internal structure in a boiling water reactor pressure vessel, an upper lattice plate, a core support plate, an ICM guide tube and an ICM guide tube stabilizer, and an ICM guide tube welder are previously installed in a shroud. The method for installing the internal structure of a nuclear reactor, comprising: loading into the reactor pressure vessel together with the shroud.
記原子炉圧力容器内への搬入をシュラウド吊具兼芯測定
装置を使用することを特徴とする原子炉内構造物の据付
け方法。7. The method for installing a reactor internal structure according to any one of claims 1 to 6, wherein the shroud is carried into the reactor pressure vessel by using a shroud suspender / core measuring device.
シュラウドサポートレグに固定後、作業員の前記原子炉
圧力容器内外への出入りを再循環水出口ノズルより行う
ことを特徴とする原子炉内構造物の据付け方法。8. The nuclear reactor according to claim 1, wherein after the shroud is fixed to the shroud support leg, a worker reciprocates into and out of the reactor pressure vessel through a recirculation water outlet nozzle. How to install a structure.
ュラウドサポートレグに固定後、前記ＩＣＭ案内管とＩ
ＣＭハウジングの溶接作業を前記シュラウドと炉心スプ
レイ配管の溶接，給水スパージャの前記原子炉圧力容器
内への据付けと並行して行うことを特徴とする原子炉内
構造物の据付け方法。9. The ICM guide tube and I according to claim 1, after fixing the shroud to a shroud support leg.
A method for installing a reactor internal structure, characterized in that the welding work of the CM housing is performed in parallel with the welding of the shroud and the core spray pipe and the installation of the water supply sparger in the reactor pressure vessel.
より構成されるシュラウド溶接機を使用することを特徴
とする原子炉内構造物の据付け方法。10. A method for installing a reactor internal structure, comprising using a shroud welder comprising a plurality of welding heads according to claims 3 and 4.
より構成されるＩＣＭ案内管溶接機を使用することを特
徴とする原子炉内構造物の据付け方法。11. A method of installing a reactor internal structure, comprising using an ICM guide pipe welder composed of a plurality of welding heads according to claims 5 and 6.
ウド溶接機は炉心支持板穴より搬出が出来る構造とする
ことを特徴とする原子炉内構造物の据付け方法。12. A method for installing a reactor internal structure according to claim 3, 4, or 10, wherein said shroud welder has a structure capable of being carried out from a core support plate hole.
案内管溶接機は炉心支持板穴より搬出が出来る構造とす
ることを特徴とする原子炉内構造物の据付け方法。13. The ICM according to claim 5, 6, or 12.
The guide pipe welding machine is constructed so that it can be carried out from the hole in the core support plate.
ルを設け、前記ヘッド走行レールにヘッド走行モータ，
ワイヤリール，左右位置決めセンサ，アーク監視用カメ
ラ，ＡＶＣモータ，オシレートモータ，溶接トーチ，ワ
イヤ送給モータより構成される溶接機本体を設定し前記
シュラウド内面より前記シュラウドとシュラウドサポー
トレグの溶接を行うことを特徴とする原子炉シュラウド
溶接機。14. A head traveling rail is provided on the inner surface of the lower part of the shroud, and a head traveling motor is provided on the head traveling rail.
A welding machine body including a wire reel, a left / right positioning sensor, an arc monitoring camera, an AVC motor, an oscillating motor, a welding torch, and a wire feeding motor is set, and the shroud and the shroud support leg are welded from the inner surface of the shroud. Reactor shroud welding machine characterized by.
ース、および旋回テーブル，Ｘテーブル，Ｙテーブル，
旋回駆動装置，Ｘ方向駆動装置，Ｙ方向駆動装置，電動
チェーンブロック，芯測定装置より構成され、前記シュ
ラウドの芯設定および水平，鉛直方向の調整を行うこと
を特徴とする原子炉シュラウド吊具兼芯測定装置。15. A base set on a flange of a reactor pressure vessel, and a turning table, an X table, a Y table,
Reactor shroud suspender characterized by comprising a swivel drive device, an X-direction drive device, a Y-direction drive device, an electric chain block, and a core measuring device, and performing core setting and horizontal and vertical adjustment of the shroud. Core measuring device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6241023A JPH08105990A (en) | 1994-10-05 | 1994-10-05 | Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6241023A JPH08105990A (en) | 1994-10-05 | 1994-10-05 | Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH08105990A true JPH08105990A (en) | 1996-04-23 |
Family
ID=17068192
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6241023A Pending JPH08105990A (en) | 1994-10-05 | 1994-10-05 | Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH08105990A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5687206A (en) * | 1996-03-15 | 1997-11-11 | Mpr Associates, Inc. | Method of replacing a boiling water reactor core shroud |
| US5828713A (en) * | 1996-10-15 | 1998-10-27 | Mpr Associates, Inc. | Replacement core shroud assembly for a boiling water reactor |
| JP2008232678A (en) * | 2007-03-16 | 2008-10-02 | Toshiba Corp | Core shroud replacement method |
| JP2009031013A (en) * | 2007-07-24 | 2009-02-12 | Hitachi-Ge Nuclear Energy Ltd | Method for surface treatment of weld zone in nuclear reactor |
| 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 |
| JP2014028373A (en) * | 2012-07-31 | 2014-02-13 | Toshiba Corp | Shroud installation device and method |
-
1994
- 1994-10-05 JP JP6241023A patent/JPH08105990A/en active Pending
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5687206A (en) * | 1996-03-15 | 1997-11-11 | Mpr Associates, Inc. | Method of replacing a boiling water reactor core shroud |
| US5828713A (en) * | 1996-10-15 | 1998-10-27 | Mpr Associates, Inc. | Replacement core shroud assembly for a boiling water reactor |
| JP2008232678A (en) * | 2007-03-16 | 2008-10-02 | Toshiba Corp | Core shroud replacement method |
| JP2009031013A (en) * | 2007-07-24 | 2009-02-12 | Hitachi-Ge Nuclear Energy Ltd | Method for surface treatment of weld zone in nuclear reactor |
| 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 |
| JP2014028373A (en) * | 2012-07-31 | 2014-02-13 | Toshiba Corp | Shroud installation device and method |
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