JPH02234096A - Assembling and transporting method for nuclear pressure vessel and transport use truck - Google Patents

Assembling and transporting method for nuclear pressure vessel and transport use truck

Info

Publication number
JPH02234096A
JPH02234096A JP1053799A JP5379989A JPH02234096A JP H02234096 A JPH02234096 A JP H02234096A JP 1053799 A JP1053799 A JP 1053799A JP 5379989 A JP5379989 A JP 5379989A JP H02234096 A JPH02234096 A JP H02234096A
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
skirt
reactor
pump casing
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
JP1053799A
Other languages
Japanese (ja)
Other versions
JP2666998B2 (en
Inventor
Takehiko Kurose
黒瀬 武彦
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP1053799A priority Critical patent/JP2666998B2/en
Publication of JPH02234096A publication Critical patent/JPH02234096A/en
Application granted granted Critical
Publication of JP2666998B2 publication Critical patent/JP2666998B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Pressure Vessels And Lids Thereof (AREA)

Abstract

PURPOSE:To simplify the job site work and to shorten the construction process by attaching integrally an in-nuclear reactor recirculating pump casing to a nuclear pressure vessel body in advance in a plant, and attaching, a temporary skirt for containing and protecting its casing. CONSTITUTION:In a plant, an in-nuclear reactor recirculating pump casing 7 is attached integrally to a reactor pressure vessel 1 body, and reamer working of a fitting part and other finish working are executed. Subsequently, one end of a temporary skirt 15 having sufficient length for containing and protecting the casing 7 is attached to a skirt flange 4a of the vessel 1, and the other end is supported by a supporting leg 17 provided on a transport use truck 16. Also, a drum flange 3 part of the vessel 1 is supported by a supporting leg 18. In such a way, in a state that the vessel 1 is placed and fixed on the truck 16, the track 16 is run, and the vessel 1 is transported to a setting job site. Moreover, a support 19 is provided by projecting it from the inside surface of the skirt 15, by which the casing 7 is supported, and the deformation and damage caused by its dead weight are prevented.

Description

【発明の詳細な説明】 (発明の目的〕 (産業上の利用分野) 本発明は沸騰水型原子炉<BWR)の原子炉圧力容器の
組立輸送方法および輸送用台車に係り、特に原子炉圧力
容器を据付川場まで輸送する輸送工程が簡略化でき、ま
た据付現場における組立作業を大幅に簡素化することが
できる原子炉圧力容器の組立輸送方法およびその輸送時
に使用する輸送用台車に関する。
Detailed Description of the Invention (Objective of the Invention) (Industrial Field of Application) The present invention relates to a method for assembling and transporting a reactor pressure vessel of a boiling water reactor (BWR), and a transportation trolley, and particularly relates to a The present invention relates to a method for assembling and transporting a nuclear reactor pressure vessel, which can simplify the transport process of transporting the vessel to the installation site, and can greatly simplify the assembly work at the installation site, and a transport trolley used during the transport.

(従来の技術) 従来、原子炉圧力容器1は一般に第2図に示すように自
立堅形円筒形を有し、その下部に配設された支持スカー
ト2において支持される。原子炉圧力容器1上部には厚
肉の胴7ランジ3が形成され、支持スカート2の底部に
はスカートフランジ4が取付けられる。
(Prior Art) Conventionally, a nuclear reactor pressure vessel 1 generally has a free-standing rigid cylindrical shape as shown in FIG. 2, and is supported on a support skirt 2 disposed at the bottom thereof. A thick-walled shell 7 flange 3 is formed at the top of the reactor pressure vessel 1, and a skirt flange 4 is attached to the bottom of the support skirt 2.

また原子炉圧力容器1の側壁には外部再循環ループ(P
LR)に接続する再循環ノズル5が設けられている。外
部再循環ループは、炉内に配設されたジェットポンプを
介して原子炉冷却材を強!I1循環させる系統であり、
独立した複数のループより成り、各ループには渦巻式の
再循環ポンプが取付審ノられる。
Additionally, an external recirculation loop (P
A recirculation nozzle 5 is provided which connects to LR). The external recirculation loop pumps the reactor coolant through a jet pump located inside the reactor! It is a system that circulates I1,
It consists of multiple independent loops, each of which is fitted with a volute recirculation pump.

上記のような外部再循環ループ(PLR)を据付現場に
おいて組付ける従来の原子炉圧力容器1は、製作工場に
おいて容器本体を組立てた後に最終焼鈍を実施し、再循
環ノズル5を溶接した後に、倒伏状態にて輸送用台車や
船舶に載荷され、据付現場に輸送されていた。
In the conventional reactor pressure vessel 1 in which the external recirculation loop (PLR) as described above is assembled at the installation site, after the vessel body is assembled in the manufacturing factory, final annealing is performed and the recirculation nozzle 5 is welded. It was loaded onto a transport trolley or ship in a lying position and transported to the installation site.

この従来の原子炉圧力容器1は、ほぼ円筒状を呈し、容
器本体側壁や円筒形の支持スカート2から突出するノズ
ル等も少ないため、輸送時の取扱いも容易であった。す
なわち原子炉圧力容器1はスカートフランジ4およぴ頂
部に形成した胴フランジ3にそれぞれ支持S造物を介し
て輸送用台車に固定され、据付現場へと輸送されていた
This conventional reactor pressure vessel 1 has a substantially cylindrical shape and has few nozzles protruding from the side wall of the vessel body or the cylindrical support skirt 2, so it is easy to handle during transportation. That is, the reactor pressure vessel 1 was fixed to a transportation trolley via supporting S structures at the skirt flange 4 and the trunk flange 3 formed at the top, respectively, and was transported to an installation site.

しかし、近年、原子炉圧力容器1外部に配設されていた
再循環ループを廃止して、再循環系の構造を簡素化する
ために、再循環ポンプを原子炉圧力容器1の底縁部に一
体的に装備する原子炉内蔵型再循環ボンブ(RIP)が
多く採用されるに至っている。
However, in recent years, in order to simplify the structure of the recirculation system by abolishing the recirculation loop that was installed outside the reactor pressure vessel 1, the recirculation pump has been installed at the bottom edge of the reactor pressure vessel 1. Reactor-integrated recirculation bombs (RIPs), which are integrally equipped, are increasingly being adopted.

この原子炉内蔵型再WJ環ポンプ(RIP)は第3図に
示すように原子炉圧力容器1の下部鎖板6外周部に複数
基取付番プられる。この再循環ボンブのポンプケーシン
グ7は従来、据付現場において下部鎮板6の下方に大き
く突設するように配設される。また圧力容器1側壁には
拡開した支持スカート2aが形成され、支持スカート2
aの下端にスカートフランジ4aが配設される。
A plurality of reactor built-in re-WJ ring pumps (RIPs) are mounted on the outer periphery of the lower chain plate 6 of the reactor pressure vessel 1, as shown in FIG. Conventionally, the pump casing 7 of this recirculation bomb is arranged so as to protrude significantly below the lower base plate 6 at the installation site. Further, an expanded support skirt 2a is formed on the side wall of the pressure vessel 1.
A skirt flange 4a is disposed at the lower end of a.

上記ポンプケーシング7の上端部は、第4図に示すよう
に原子炉圧力容器1の下部鏡板6に穿設した取付ノズル
8に嵌装され、溶接接合によって一体に固定される。こ
の溶接接合部9を含めた取付ノズル8には高速回転する
再循環ボンブの回転軸が挿通されるため、溶接接合部9
および取付ノズル8は溶接後に、リーマ加工やキー溝加
工等が施工され、高精度に仕上げられる。
As shown in FIG. 4, the upper end of the pump casing 7 is fitted into a mounting nozzle 8 formed in the lower end plate 6 of the reactor pressure vessel 1, and is fixed together by welding. Since the rotating shaft of the recirculation bomb that rotates at high speed is inserted into the mounting nozzle 8 including this welded joint 9, the welded joint 9
After welding, the mounting nozzle 8 is reamed, keyed grooved, etc., and finished with high precision.

(発明が解決しようとする課題) しかしながら、再循環ポンプのポンプケーシング7は原
子炉圧力容器1の底部に大きく突出する形状を有してい
るため、輸送時における変形や破門から防護するための
養生が困難であった。そのため、従来は原子炉圧力容器
1とポンプケーシング7とは、別便にて現場に搬入し、
据付現場においてポンプケーシング7の取付けおよび加
工調整作業を実施していた。
(Problem to be Solved by the Invention) However, since the pump casing 7 of the recirculation pump has a shape that largely protrudes from the bottom of the reactor pressure vessel 1, it is necessary to provide curing to protect it from deformation and excommunication during transportation. was difficult. Therefore, conventionally, the reactor pressure vessel 1 and the pump casing 7 were delivered to the site by separate delivery.
At the installation site, the pump casing 7 was installed and processed and adjusted.

ところが、原子炉圧力容器1を現場の原子炉格納容器内
に据付けた段階においては、第5図に示すように多くの
機器の組立工事が並行して実施されるため、組立工程が
錯綜し円滑な組立作業が実施できない問題点がある。
However, at the stage when the reactor pressure vessel 1 is installed in the reactor containment vessel at the site, as shown in Figure 5, many equipment assembly works are carried out in parallel, making the assembly process complicated and difficult to proceed smoothly. There is a problem that assembly work cannot be carried out.

すなわち、原子炉設備の全体の建設工程や原子炉圧力容
器1下方の作業空間における作業効率を肋案ずると、原
子炉圧力容器1が現地据付される時点においては、制御
棒駆動機構(CRD)用配管11、再循環ボンブ交換機
12およびポンプヶーシング7が取付く位置周辺に配設
される構造物13等は既に搬入が完了し据付けられてい
る必要がある。
In other words, considering the overall construction process of the reactor equipment and the work efficiency in the working space below the reactor pressure vessel 1, when the reactor pressure vessel 1 is installed on site, the control rod drive mechanism (CRD) The piping 11, the recirculation bomb exchanger 12, the structures 13, etc. that are disposed around the locations where the pump casing 7 will be attached must have already been delivered and installed.

これらの機器の据付けが全て完了しでいる場合において
も、狭い下部ドライウエル10内において、10数基分
のポンプケーシング7を原子炉圧力容器1の取付ノズル
8に挿入し、次に芯出し位社決め後に溶接し、ざらにリ
ーマ加工等の仕上げ作業を実施することは多くの困難を
伴う。そしてam搬入設備計画、芯出支持装置の設置等
で非常に作業工程が錯綜し、工期が遅延するおそれもあ
る。
Even if the installation of all these devices has been completed, the pump casings 7 for more than ten pumps are inserted into the installation nozzle 8 of the reactor pressure vessel 1 in the narrow lower drywell 10, and then the centering position is Performing finishing work such as welding and rough reaming after company approval involves many difficulties. There is also a risk that the work process will be extremely complicated due to am loading equipment planning, installation of centering support equipment, etc., and the construction period will be delayed.

またポンプケーシング7と取付ノズル8との溶接作業お
よび機械加工作業を行う場合は.1原子炉圧力容i21
1内部から作業員がアプローチして行う必要がある。し
かるに外部再循環ループ( P L R )を有しない
原子炉圧力容器1では再循環ノズルがないため、作業員
は、原子炉圧力容器1の頂部の胴フランジ3の開口部、
原子炉圧力容器1と炉心シュラウド14との間隙部を経
由する他、原子炉圧力容器1内に出入りすることが不可
能であり、作業性が極めて悪い問題点がある。
Also, when performing welding and machining work between the pump casing 7 and the mounting nozzle 8. 1 reactor pressure capacity i21
1. It is necessary for a worker to approach from inside. However, since there is no recirculation nozzle in the reactor pressure vessel 1 which does not have an external recirculation loop (PLR), the operator must open the opening of the shell flange 3 at the top of the reactor pressure vessel 1,
It is impossible to enter or exit the reactor pressure vessel 1 other than through the gap between the reactor pressure vessel 1 and the core shroud 14, which poses the problem of extremely poor workability.

さらに、従来のようにポンプケーシング7を別送し、現
地で原子炉圧力容器1に組付ける場合、原子炉圧力容器
1の水圧試験までに下部ドライウエル10内で完了させ
る必要がある他の工事との関連を考慮すると、ポンプケ
ーシング7は、原子炉圧力容器1の据付完了後、即時に
他の周辺機器の作業に先行して実施することが望ましい
。しかしこの時点では原子炉圧力容器1を収納する原子
炉建屋が建設中であるため、作業員が建屋外から原子炉
圧力容器1の胴7ランジ3部まで到達するまでのアクセ
ス性が悪くなる。
Furthermore, when the pump casing 7 is shipped separately and assembled into the reactor pressure vessel 1 on site as in the past, other work must be completed in the lower dry well 10 before the hydraulic pressure test of the reactor pressure vessel 1. Considering this relationship, it is desirable to carry out work on the pump casing 7 immediately after the installation of the reactor pressure vessel 1 is completed, prior to work on other peripheral equipment. However, at this point, the reactor building housing the reactor pressure vessel 1 is under construction, so the accessibility for workers from outside the building to the 3 part of the flange 7 of the reactor pressure vessel 1 is poor.

さらに従来はポンプケーシング7およびその加工に要す
る機械設備を原子炉圧力容器本体とは別便で現地に輸送
しているため輸送工程が煩雑となる問題点があった。
Furthermore, in the past, the pump casing 7 and the mechanical equipment required for processing the pump casing 7 were transported to the site separately from the reactor pressure vessel main body, which caused the problem that the transportation process was complicated.

本発明は上記の問題点を解決するためになされたもので
あり、原子炉内再循環ポンプ(RIP)ケーシングおよ
び原子炉圧力容器を据付現場まで輸送する輸送工程を簡
略化し、また据付現場における組立作業を大幅に簡素化
することができる原子炉圧力容器の組立輸送方法および
その輸送時に使用する輸送用台中を提供することを目的
とする。
The present invention has been made to solve the above problems, and it simplifies the transportation process of transporting the reactor recirculation pump (RIP) casing and the reactor pressure vessel to the installation site, and also simplifies the assembly process at the installation site. An object of the present invention is to provide a method for assembling and transporting a nuclear reactor pressure vessel that can greatly simplify the work, and a transport platform used during the transport.

〔発明の構成〕[Structure of the invention]

《課題を解決するための手段》 上記目的を達成するため本発明に係る原子炉圧力容器の
組立輸送方法は、工場において原子炉内再循環ポンプケ
ーシングを予め原子炉圧力容品本体に一体に取付け、仕
上加工を行った後に、上記原子炉内再循環ポンプケーシ
ングを収納保護するに充分な長さを有する仮スカー1・
を用意し、仮スカートの一端を原子炉圧力容器スカート
フランジに取付けるとともに、他端を輸送用台車上に設
けた支持脚で支持した状態で輸送用台車を走行せしめ原
子炉圧力容器を据付現場まで輸送することを特徴とする
<<Means for Solving the Problems>> In order to achieve the above object, the method for assembling and transporting a reactor pressure vessel according to the present invention includes integrally attaching the reactor recirculation pump casing to the reactor pressure vessel main body in advance in a factory. , After the finishing process, a temporary scar 1.
One end of the temporary skirt is attached to the reactor pressure vessel skirt flange, and the other end is supported by the support legs provided on the transport trolley, and the transport trolley is driven to the reactor pressure vessel installation site. It is characterized by being transported.

また本発明に係る原子炉圧力容器の輸送用台車は、原子
炉内再循環ポンプケーシングを一体に取付けた原子炉圧
力容器を輸送する輸送用台車において、上記原子炉内再
循環ポンプケーシングを収納保護するに充分な長さを有
し、原子炉圧力容器のスカートフランジに着脱可能な、
仮スカートを装備したことを特徴とする。
Further, the reactor pressure vessel transportation trolley according to the present invention is a transportation trolley for transporting a reactor pressure vessel to which a reactor recirculation pump casing is integrally attached, in which the reactor recirculation pump casing is housed and protected. It has a sufficient length for
It is characterized by being equipped with a temporary skirt.

《作用》 上記構成に係る原子炉圧力容器の組立輸送方法によれば
、予め原子炉内再循環ポンプケーシングが、作業環境が
優れた工場において予め原子炉圧力容器に一体に取付け
られ、また仕上加工が実施されているため、現地におけ
る取付作業および仕上げ加工作業を省略でき、現場作業
を著しく簡素化することができる。
<<Operation>> According to the method for assembling and transporting a reactor pressure vessel according to the above configuration, the reactor recirculation pump casing is preliminarily installed integrally with the reactor pressure vessel in a factory with an excellent working environment, and is also subjected to finishing processing. Since this has been implemented, on-site installation work and finishing work can be omitted, significantly simplifying on-site work.

また工場にて取付けられたポンプケーシングを収納保護
するに充分な長さを有する仮スカートによって輸送時に
おける変形、損傷を効果的に防止することができる。
Furthermore, the temporary skirt, which is long enough to house and protect the pump casing installed at the factory, can effectively prevent deformation and damage during transportation.

ざらに、本発明に係る輸送用台車によればポンプケーシ
ングを原子炉圧力容器本体と同時に輸送することが可能
となり、従来のようにポンプケーシングやその仕上加工
に要づる機器を別便にて輸送していた場合と比較して、
機器の輸送工程を大幅に簡略化させることができる。
In general, the transportation trolley according to the present invention makes it possible to transport the pump casing at the same time as the reactor pressure vessel body, instead of transporting the pump casing and the equipment required for finishing it separately, as in the past. compared to if
The transportation process for equipment can be greatly simplified.

(実施例) 以下本発明の一実施例についで添4−J図面を参照して
説明する。第1図は本発明方法および輸送用台車を使用
して原子炉圧力容器を輸送する状態を示す側面図である
。なお第2図〜・第5図に承り従来例と同一要素には同
一首号を付している。
(Example) An example of the present invention will be described below with reference to the attached drawings 4-J. FIG. 1 is a side view showing a state in which a nuclear reactor pressure vessel is transported using the method of the present invention and a transport trolley. In addition, as shown in FIGS. 2 to 5, elements that are the same as those of the conventional example are given the same numbers.

すなわち本実施例に係る原子炉圧力容器の組立輸送方法
は、まず工場において原子炉内再循環ポンプケーシング
7を予め原子炉圧力容!1本体に一体に取付け、取付部
のりーマ加工やキー溝加工等の仕上加工を行った後に、
上記原子炉内再循環ポンプケーシング7を収納保護する
に充分な長さを有する仮スカート15を用意し、仮スカ
ート15の一端を、原子炉圧力容器1のスカートフラン
ジ4aに取付けるとともに、他端を輸送用台車16上に
設けた支持脚17で支持しさらに原子炉圧力容器1の胴
フランジ3部を支持脚18で支持した状態で輸送用台車
16を走行せしめ、原子炉内再循環ポンプケーシング7
を一体に組み付けた原子炉圧力容器1を据付現場まで輸
送するものである。
That is, in the method for assembling and transporting the reactor pressure vessel according to this embodiment, first, the reactor recirculation pump casing 7 is assembled into the reactor pressure vessel in advance at the factory. 1 After installing it in one body and performing finishing processes such as reaming and keyway machining on the mounting part,
A temporary skirt 15 having a length sufficient to house and protect the reactor recirculation pump casing 7 is prepared, one end of the temporary skirt 15 is attached to the skirt flange 4a of the reactor pressure vessel 1, and the other end is attached to the skirt flange 4a of the reactor pressure vessel 1. The transport trolley 16 is supported by support legs 17 provided on the transport trolley 16, and the trunk flange 3 of the reactor pressure vessel 1 is supported by the support legs 18, and the transport trolley 16 is run to transport the reactor recirculation pump casing 7.
The reactor pressure vessel 1, which has been assembled into one piece, is transported to the installation site.

また輸送時に使用する好適な輸送用台車16は、原子炉
内再循環ポンプケーシング7を一体に取付けた原子炉圧
力容器1を輸送する輸送用台車16において、上記原子
炉内再循環ポンプケーシング7を収納保護するに充分な
良さを有し、原子炉圧力容器1のスカートフランジ4a
に者脱可能な、仮スカート15を装備して構成される。
Further, a suitable transport trolley 16 used during transportation is a transport trolley 16 for transporting the reactor pressure vessel 1 to which the reactor recirculation pump casing 7 is integrally attached. The skirt flange 4a of the reactor pressure vessel 1 has sufficient properties for storage and protection.
It is equipped with a temporary skirt 15 that can be taken off.

また上記仮スカート15は円筒状に形成ざれ、原子炉圧
力容器1のスカートフランジ4aから突出するポンプケ
ーシング7を収容するに充分な長さを有するように形成
される。
The temporary skirt 15 is formed into a cylindrical shape and has a length sufficient to accommodate the pump casing 7 protruding from the skirt flange 4a of the reactor pressure vessel 1.

工場においてポンプケーシング7を一体に接合し仕上げ
加工を行った原子炉圧力容器1を輸送する場合は、まず
スカートフランジ4aに仮スカート15の一端を取付け
、次に仮スカート15の仙端に支持脚17を取付けると
ともに、胴フランジ311にも支持脚18を取付け、こ
れら輸送用台車に装備された一対の支持脚17.18を
介して輸送用台車16上に載置固定する。
When transporting the reactor pressure vessel 1 with the pump casing 7 joined together and finished at the factory, first attach one end of the temporary skirt 15 to the skirt flange 4a, and then attach a support leg to the sacrum end of the temporary skirt 15. 17 is attached, and support legs 18 are also attached to the body flange 311, and the carrier is mounted and fixed on the transportation truck 16 via a pair of support legs 17 and 18 provided on the transportation truck.

なお、スカートフランジ4aと仮スカート15との結合
部、仮スカート15と支持脚17との結合部および胴フ
ランジ3部と支持脚18との結合部を気密な構造とし、
内部に窒素ガス等を封入することにより輸送時における
防錆対策が可能となる。
Note that the joint between the skirt flange 4a and the temporary skirt 15, the joint between the temporary skirt 15 and the support leg 17, and the joint between the body flange 3 and the support leg 18 are made to have an airtight structure.
By filling the inside with nitrogen gas, etc., it is possible to prevent rust during transportation.

また原子炉圧力容器1底部から突出したポンプケーシン
グ7の輸送時における保護対策として、仮スカート15
内面から支持サポート19を突設せしめ、支持サポート
19によってポンプケーシング7を支持し、その自重に
よる変形や損傷を防止することもできる。
In addition, as a protection measure during transportation of the pump casing 7 protruding from the bottom of the reactor pressure vessel 1, a temporary skirt 15 is installed.
It is also possible to provide a support 19 protruding from the inner surface and support the pump casing 7 by the support support 19 to prevent deformation or damage due to its own weight.

このように本実施例に係る原子炉圧力容器の組立輸送方
法によれば、原子炉内再循環ポンプケーシング7が予め
工場において、原子炉圧力容器1に一体に取付けられて
仕上げ加工まで実施された上で据付現場に搬入されるた
め、現場における取付加工を省略することができ、原子
炉圧力容器下部の作業空間の狭さに起因する作業性の悪
さが解消し、現場作業を著しく簡素化することができる
As described above, according to the method for assembling and transporting a nuclear reactor pressure vessel according to this embodiment, the reactor recirculation pump casing 7 is integrally attached to the reactor pressure vessel 1 in advance at a factory, and the final processing is carried out. Since it is delivered to the installation site at the top, it is possible to omit the installation process on site, which eliminates the poor workability caused by the narrow working space at the bottom of the reactor pressure vessel, and significantly simplifies the on-site work. be able to.

また突出したポンプケーシング7は輸送時に仮スカート
15によって保護され、輸送途中の変形や損傷が効果的
に防止される。
Further, the protruding pump casing 7 is protected by a temporary skirt 15 during transportation, and deformation and damage during transportation are effectively prevented.

さらに本実施例に係る輸送用台車16によれば、ポンプ
ケーシング7を原子炉圧力容器1本体と同時に輸送する
ことが可能となり、従来のようにポンプケーシング7や
その仕上加工に要するm器を別便にて輸送していた場合
と比較して機器の発送返送も省略され、輸送工程を大幅
に簡略化させることができる。
Furthermore, according to the transportation trolley 16 according to this embodiment, it is possible to transport the pump casing 7 at the same time as the reactor pressure vessel 1 body, and unlike the conventional method, the pump casing 7 and the equipment required for its finishing can be transported separately. Compared to the case where the equipment was transported by , the shipping and return of the equipment is also omitted, which greatly simplifies the transportation process.

なお、工場、港、据付現場等において原子炉圧力容器1
を取扱うIII機、輸送用船舶、トレーラーの設備仕様
等によって重ffi増加による影響が発生しない限りに
おいで、原子炉圧力容1a1内部に取付けられる他の構
造物、例えば第5図に示す炉心シュラウド14等も予め
工場で取付けて現場に輸送することも可能である。
In addition, reactor pressure vessel 1 may be used at factories, ports, installation sites, etc.
As long as there is no effect due to increased heavy ffi due to the equipment specifications of the III aircraft, transportation vessel, trailer, etc. to be handled, other structures installed inside the reactor pressure vessel 1a1, such as the core shroud 14 shown in FIG. It is also possible to install them in advance at the factory and transport them to the site.

〔発明の効果〕〔Effect of the invention〕

以上説明の通り本発明に係る原子炉圧力容器の組立輸送
方法によれば、予め原子炉内再循環ポンプケーシングが
、作業環境が優れた工場において予め原子炉圧力容器に
一体に取付けられ、また仕上加工が実施されているため
、現地における取付作業および仕上げ加工作業を省略で
き、現場作業を著しく簡素化し、工事工程の短縮および
安全性の向上に大きな効果を奏する。
As explained above, according to the method for assembling and transporting a reactor pressure vessel according to the present invention, the reactor recirculation pump casing is previously integrally attached to the reactor pressure vessel in a factory with an excellent working environment, and Since the process has been carried out, on-site installation work and finishing work can be omitted, significantly simplifying on-site work, and having a significant effect on shortening the construction process and improving safety.

また工場にて取付けられたポンプケーシングを収納保護
するに充分な良さを有する仮スカートによって輸送時に
おける変形、損傷を効果的に防止することができる。
In addition, the temporary skirt, which is strong enough to house and protect the pump casing installed at the factory, can effectively prevent deformation and damage during transportation.

さらに、本発明に係る輸送用台車によればポンプケーシ
ングを原子炉圧力容器本体と同時に輸送することが可能
となり、従来のようにポンプケーシングやその仕上加工
に要する機器を別便にて輸送していた場合と比較して、
機器の輸送工程を大幅に簡略化させることができる。
Furthermore, according to the transportation trolley of the present invention, it is possible to transport the pump casing at the same time as the reactor pressure vessel main body, and unlike conventional methods, the pump casing and the equipment required for its finishing were transported separately. Compared to the case
The transportation process for equipment can be greatly simplified.

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

第1図は本発明に係る輸送用台車を使用して原子炉圧力
容器を輸送している状態を示す側面図、第2図は外部再
循環ループと接続される従来の原子炉圧ノノ容器の縦断
面図、第3図は原子炉内蔵型再循環ポンプを装備する原
子炉圧力容器の縦断面図、第4図はポンプケーシングの
取付構造を示す断面図、第5図は現場に据付けた原子炉
圧力容器とその周辺の作lAm境を示す断面図である。 1・・・原子炉圧力容器、2.28・・・支持スカート
、3・・・胴7ランジ、4,4a・・・スカートフラン
ジ、5・・・再循環ノズル、6・・・下部鏡板、7・・
・ポンプケーシング、8・・・取付ノズル、9・・・溶
接接合部、10・・・下部ドライウエル、11・・・制
御棒駆動機構用配管、12・・・再循環ボンブ交換機、
13・・・構造物、14・・・炉心シュラウド、15・
・・仮スカート、16・・・輸送用台車、17・・・支
持脚、18・・・支持脚、19・・・支持サポート。 名 巨 羊 図
FIG. 1 is a side view showing a state in which a reactor pressure vessel is being transported using a transportation trolley according to the present invention, and FIG. 2 is a side view of a conventional reactor pressure vessel connected to an external recirculation loop. Figure 3 is a vertical cross-sectional view of the reactor pressure vessel equipped with a recirculation pump built into the reactor, Figure 4 is a cross-sectional view showing the mounting structure of the pump casing, and Figure 5 is a cross-sectional view of the reactor pressure vessel equipped with a recirculation pump built into the reactor. FIG. 2 is a cross-sectional view showing the reactor pressure vessel and its surrounding area. DESCRIPTION OF SYMBOLS 1... Reactor pressure vessel, 2.28... Support skirt, 3... Trunk 7 flange, 4, 4a... Skirt flange, 5... Recirculation nozzle, 6... Lower end plate, 7...
・Pump casing, 8... Mounting nozzle, 9... Welding joint, 10... Lower dry well, 11... Piping for control rod drive mechanism, 12... Recirculation bomb exchanger,
13... Structure, 14... Core shroud, 15.
...Temporary skirt, 16...Transportation trolley, 17...Support leg, 18...Support leg, 19...Support support. famous giant sheep

Claims (1)

【特許請求の範囲】 1、工場において原子炉内再循環ポンプケーシングを予
め原子炉圧力容器本体に一体に取付け、仕上加工を行っ
た後に、上記原子炉内再循環ポンプケーシングを収納保
護するに充分な長さを有する仮スカートを用意し、仮ス
カートの一端を原子炉圧力容器スカートフランジに取付
けるとともに、他端を輸送用台車上に設けた支持脚で支
持した状態で輸送用台車を走行せしめ原子炉圧力容器を
据付現場まで輸送することを特徴とする原子炉圧力容器
の組立輸送方法。 2、原子炉内再循環ポンプケーシングを一体に取付けた
原子炉圧力容器を輸送する輸送用台車において、上記原
子炉内再循環ポンプケーシングを収納保護するに充分な
長さを有し、原子炉圧力容器のスカートフランジに着脱
可能な仮スカートを装備したことを特徴とする輸送用台
車。
[Claims] 1. After the reactor recirculation pump casing has been integrally attached to the reactor pressure vessel main body in advance at the factory and finishing processing is performed, the reactor recirculation pump casing is sufficiently housed and protected. A temporary skirt with a certain length is prepared, one end of the temporary skirt is attached to the reactor pressure vessel skirt flange, and the other end is supported by a support leg provided on the transport trolley, and the transport trolley is run. A method for assembling and transporting a reactor pressure vessel characterized by transporting the reactor pressure vessel to an installation site. 2. A transportation trolley for transporting the reactor pressure vessel to which the reactor recirculation pump casing is integrally attached, has a length sufficient to house and protect the reactor recirculation pump casing, and has a length sufficient to accommodate and protect the reactor recirculation pump casing, and the reactor pressure vessel is A transportation trolley characterized by being equipped with a removable temporary skirt on the skirt flange of a container.
JP1053799A 1989-03-08 1989-03-08 Reactor pressure vessel assembly and transportation method and transportation cart Expired - Lifetime JP2666998B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1053799A JP2666998B2 (en) 1989-03-08 1989-03-08 Reactor pressure vessel assembly and transportation method and transportation cart

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1053799A JP2666998B2 (en) 1989-03-08 1989-03-08 Reactor pressure vessel assembly and transportation method and transportation cart

Publications (2)

Publication Number Publication Date
JPH02234096A true JPH02234096A (en) 1990-09-17
JP2666998B2 JP2666998B2 (en) 1997-10-22

Family

ID=12952865

Family Applications (1)

Application Number Title Priority Date Filing Date
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Country Status (1)

Country Link
JP (1) JP2666998B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05256990A (en) * 1992-03-16 1993-10-08 Hitachi Ltd Placing method for pipe whip structure
KR101218879B1 (en) * 2011-05-02 2013-01-09 한국원자력연구원 Trailer for spent nuclear fuel carring vessel and loading method for the same

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101493289B1 (en) * 2013-02-25 2015-02-16 두산중공업 주식회사 Apparatus for shipping for modularized reactor vessel internals

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01141398A (en) * 1987-11-27 1989-06-02 Ishikawajima Harima Heavy Ind Co Ltd Reactor pressure vessel

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01141398A (en) * 1987-11-27 1989-06-02 Ishikawajima Harima Heavy Ind Co Ltd Reactor pressure vessel

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05256990A (en) * 1992-03-16 1993-10-08 Hitachi Ltd Placing method for pipe whip structure
KR101218879B1 (en) * 2011-05-02 2013-01-09 한국원자력연구원 Trailer for spent nuclear fuel carring vessel and loading method for the same

Also Published As

Publication number Publication date
JP2666998B2 (en) 1997-10-22

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