JPS629706B2 - - Google Patents

Info

Publication number
JPS629706B2
JPS629706B2 JP53074587A JP7458778A JPS629706B2 JP S629706 B2 JPS629706 B2 JP S629706B2 JP 53074587 A JP53074587 A JP 53074587A JP 7458778 A JP7458778 A JP 7458778A JP S629706 B2 JPS629706 B2 JP S629706B2
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
reactor
skirt
main body
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.)
Expired
Application number
JP53074587A
Other languages
Japanese (ja)
Other versions
JPS552134A (en
Inventor
Tadashi Nakamura
Yasuo Morita
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP7458778A priority Critical patent/JPS552134A/en
Publication of JPS552134A publication Critical patent/JPS552134A/en
Publication of JPS629706B2 publication Critical patent/JPS629706B2/ja
Granted legal-status Critical Current

Links

Classifications

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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、原子力発電所建設工事における原子
炉圧力容器据付方法に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for installing a nuclear reactor pressure vessel in nuclear power plant construction work.

第1図に示すように、原子炉圧力容器5は主と
して圧力容器本体5Aと、その内部構造物と、制
御棒ハウジング5Gとで形成されている。
As shown in FIG. 1, the reactor pressure vessel 5 is mainly formed of a pressure vessel main body 5A, its internal structure, and a control rod housing 5G.

この圧力容器本体5Aは中空状であり、下から
順に半球状の座部、円筒状部および蓋部とで形成
されており、その内部には原子炉炉水を循環させ
るジエツトポンプ5Bの再循環系、炉心を円筒状
に包むシユラウド5C、燃料体を炉心に固定する
ための上、下格子板5D,5E、炉心冷却用外部
配管との炉内配管を接続するLPCI(Low
Pressure Coolant Injection System)カツプリ
ング5F、炉内核計装モニタを保持するためのイ
ンコアハウジング5H、シユラウド5Cにシユラ
ウドヘツドを、挿入、固定するためのガイドロツ
ド5J、炉心強制冷却用コアスプレイライン配管
5K、原子炉内に給水をするための給水スパージ
ヤ5L、等の十数類に及ぶ機器からなる内部構造
物が装着されている。更に、圧力容器本体5Aの
下座部には制御棒を挿入保持するための制御棒ハ
ウジング5Gが突出して設けられているとともに
ドレンライン5Iが設けられている。
This pressure vessel main body 5A is hollow and is formed of a hemispherical seat, a cylindrical part, and a lid in order from the bottom, and inside it is a recirculation system of a jet pump 5B that circulates reactor water. , a shroud 5C that encloses the reactor core in a cylindrical shape, upper and lower grate plates 5D and 5E for fixing fuel bodies to the core, and LPCI (Low
Pressure Coolant Injection System) Coupling 5F, in-core housing 5H for holding the in-core nuclear instrumentation monitor, guide rod 5J for inserting and fixing the shroud head into the shroud 5C, core spray line piping 5K for forced core cooling, inside the reactor An internal structure consisting of more than ten types of equipment is installed, such as a water supply spargeer 5L for supplying water to the tank. Further, a control rod housing 5G for inserting and holding a control rod is provided protruding from the lower seat portion of the pressure vessel main body 5A, and a drain line 5I is also provided.

このような構造を有する原子炉の圧力容器本体
5A並びに内部構造物および制御棒ハウジング5
G等の据付は、従来次のような方法で行なわれて
いた。
Pressure vessel main body 5A, internal structure and control rod housing 5 of a nuclear reactor having such a structure
Conventionally, G etc. were installed using the following method.

すなわち、原子炉の圧力容器本体5Aとその内
部構造物は、各々製作工場で、単独に製作された
後、原子力発電所建設現場に輸送され、順次建設
建場で据付作業を行ない、完成させていた。
In other words, the reactor pressure vessel main body 5A and its internal structures are manufactured individually at a manufacturing factory, then transported to the nuclear power plant construction site, where they are sequentially installed and completed at the construction site. Ta.

この従来の工法を第2図および第3図について
説明する。
This conventional construction method will be explained with reference to FIGS. 2 and 3.

第2図は原子炉建屋1の原子炉格納容器3内に
原子炉の圧力容器本体5Aを据付ける断面図であ
る。まず、原子炉建屋1の最上階の運転操作床面
1aが完成した後に、運転操作床面1aを圧力容
器本体5Aを吊り上げ、かつ水平方向に移動出来
る移動クレーン9のレール7を据付ける。続い
て、そのレール7上に移動クレーン9を組立て
る。これと並行して原子炉格納容器3内におい
て、原子炉圧力容器据付用基礎台4のレベル出し
圧力容器本体5Aを囲む生体遮蔽壁6、格納室内
部構造物10を据付て圧力容器本体5Aの受入準
備を行なう。
FIG. 2 is a cross-sectional view of the reactor pressure vessel main body 5A installed in the reactor containment vessel 3 of the reactor building 1. First, after the operation floor 1a on the top floor of the reactor building 1 is completed, the pressure vessel main body 5A is lifted from the operation floor 1a, and the rails 7 of the mobile crane 9, which can move horizontally, are installed. Subsequently, the mobile crane 9 is assembled on the rail 7. At the same time, inside the reactor containment vessel 3, the biological shielding wall 6 surrounding the pressure vessel main body 5A and the containment chamber internal structure 10 are installed to level the reactor pressure vessel installation foundation 4, and the pressure vessel main body 5A is Prepare for acceptance.

次に、製作工場で完成した圧力容器本体5A
は、海上輸送されて来た。原子力発電所建設現場
に設けられた陸揚水切設備により陸上に吊卸さ
れ、原子炉建屋に設置した移動クレーン9の直下
まで、コロ曳き運搬された後、移動クレーン9の
直下に直立させられる。圧力容器本体5Aの頂部
に移動クレーン吊具9aをボルトにて固着させ、
その後移動クレーン9のウインチを作動させ圧力
容器本体5Aを、移動クレーン9内に吊上げて収
納する。次に、移動クレーン9をレール7に沿つ
て原子炉格納容器3の直上部迄ウインチを用いて
移動し停止する。続いて、移動クレーン9に収納
していた圧力容器本体5Aを吊り下し、基礎台4
上に定座させる。圧力容器本体5Aの定座、芯出
しおよび固定が完了したならば、圧力容器本体5
A内に、ジエツトポンプ5Bを据付けるために、
圧力容器本体5Aの頂部に仮設の更衣室21を設
ける。従来工法においては、先に原子炉格納容器
3に据付けた圧力容器本体5Aに、後から内部構
造物を取付けるものであるから、圧力容器本体5
A内を清浄に保持して作業を行なうために、作業
員が外から着て来た作業服等をこの更衣室21に
おいて圧力容器内作業専用の清潔な作業服と着替
える必要がある。従つて、従来工法ではこの更衣
室21を必ず設けなければならなかつた。
Next, the pressure vessel body 5A completed at the manufacturing factory
was transported by sea. It is hoisted onto land using landing and draining equipment provided at the nuclear power plant construction site, and is towed and transported to directly below the mobile crane 9 installed in the reactor building, and then erected directly below the mobile crane 9. The mobile crane hanging device 9a is fixed to the top of the pressure vessel main body 5A with bolts,
Thereafter, the winch of the mobile crane 9 is operated to lift and store the pressure vessel main body 5A into the mobile crane 9. Next, the mobile crane 9 is moved along the rail 7 to just above the reactor containment vessel 3 using a winch, and then stopped. Next, the pressure vessel main body 5A stored in the mobile crane 9 was suspended, and the base 4
Set it on top. After completing the seating, centering and fixing of the pressure vessel body 5A, the pressure vessel body 5A is
In order to install the jet pump 5B in A,
A temporary changing room 21 is provided at the top of the pressure vessel main body 5A. In the conventional construction method, internal structures are later attached to the pressure vessel body 5A that has been installed in the reactor containment vessel 3 first.
In order to work while keeping the inside of A clean, it is necessary for the worker to change into the changing room 21 the work clothes that he or she has worn from outside with clean work clothes specifically designed for working inside the pressure vessel. Therefore, in the conventional construction method, this changing room 21 must be provided.

この更衣室21の床には圧力容器本体5A内に
作業員が出入したり、内部構造物の構成部材を挿
入するための開閉自在な出入口が設けられてい
る。また、作業員は圧力容器本体5Aの底部へは
内壁面に添設した梯子を用いて往復していた。
The floor of the changing room 21 is provided with a doorway that can be opened and closed for allowing workers to enter and exit the pressure vessel main body 5A and for inserting components of the internal structure. Further, the workers used a ladder attached to the inner wall to go back and forth to the bottom of the pressure vessel main body 5A.

この更衣室21の仮設後に、内部構造物の据付
けが行なわれる。
After the temporary construction of the changing room 21, the internal structure is installed.

すなわち、先ずジエツトポンプ5Bを、前記出
入口を通して圧力容器本体5A内に搬入し、据付
作業を実施する。次に仮設の更衣室21を移動し
シユラウド5Cを搬入し、仮設更衣室21を元の
位置に復旧して圧力容器本体5Aの底部に溶接固
定する。続いて、上下の構子板5D,5Eをシユ
ラウド5Cと同様の方法で圧力容器本体5A内に
搬入し組込みを行なう。続いて、原子炉格納容器
3内に特設したシユートを通して、圧力容器本体
5Aの下部の基礎台4内の空間へ多数の制御棒ハ
ウジング5G、インコアハウジング5Hを搬入
し、その後圧力容器本体5Aの底部の中心部から
周辺に向けて順次圧力容器本体5Aの内部へ挿入
し、内部にて溶接固着させる。これらの制御棒ハ
ウジング5Gおよびインコアハウジング5Hは、
合せて200数十本に及び本数となるため、工期も
長期にわたる。
That is, first, the jet pump 5B is carried into the pressure vessel main body 5A through the above-mentioned entrance and exit port, and installation work is performed. Next, the temporary changing room 21 is moved, the shroud 5C is brought in, the temporary changing room 21 is restored to its original position, and it is welded and fixed to the bottom of the pressure vessel main body 5A. Subsequently, the upper and lower structure plates 5D and 5E are carried into the pressure vessel main body 5A and assembled in the same manner as the shroud 5C. Next, a large number of control rod housings 5G and in-core housings 5H are carried into the space in the foundation 4 at the bottom of the pressure vessel main body 5A through a specially installed chute inside the reactor containment vessel 3, and then the bottom of the pressure vessel main body 5A is transported. are sequentially inserted into the pressure vessel main body 5A from the center toward the periphery, and are welded and fixed inside. These control rod housing 5G and in-core housing 5H are
Since there will be over 200 pieces in total, the construction period will be long.

これらの作業が完了した後、ガイドロツド5
J、コアスプレイライン配管5K、給水スパージ
ヤ5L等を順次炉内に搬入し、据付け、その後溶
接して完成させる。
After completing these tasks, remove the guide rod 5.
J, core spray line piping 5K, water supply spargeer 5L, etc. are sequentially carried into the furnace, installed, and then welded to complete the process.

原子炉炉内構造物の据付けは上述の如く据付け
られるが、本作業と並行して原子炉格納容器3内
では、機器11、原子炉内や制御棒圧力機構へ冷
却水を供給する配管12等が順次据付けられ、原
子炉圧力容器5との接続も行ない、原子炉格納容
器3内の据付けを完了させてゆく。
The reactor internals are installed as described above, but in parallel with this work, inside the reactor containment vessel 3, equipment 11, piping 12 that supplies cooling water to the inside of the reactor and the control rod pressure mechanism, etc. are installed one after another, connections with the reactor pressure vessel 5 are also made, and the installation within the reactor containment vessel 3 is completed.

しかるに、従来の原子炉圧力容器据付方法はこ
れら部品を解体したまま多数回にわけて建設現場
に輸送するものであるから輸送が著しく繁雑であ
り、またこれら部品は寸法が大きく重量がある為
現場における部品の正確な位置決め、芯出しは困
難であり、位置決め、芯出し作業の為に専用の設
備も必要となり、またこれらの作業は天候、塵
埃、外気温、雰囲気等の影響を受けるので例えば
溶接部等の品質管理上溶接部が良好となる時期だ
けを選んで溶接しなければならず、工期が長くな
り、また屋外での作業であるため風雪、雨水から
守る大きな防護シートを格納容器の上方にかける
必要があり、また仮設の更衣室を設けなければな
らず、更に原子炉圧力容器となる各部品の搬入以
後は原子炉建屋の建設現場と原子炉格納容器内の
作業を同時並行して行わねばならないので完成し
た原子炉圧力容器の安全性、品質に問題が生ずる
虞れがある。
However, in the conventional method of installing a reactor pressure vessel, these parts are disassembled and transported to the construction site in multiple shipments, making transportation extremely complicated. Accurate positioning and centering of parts is difficult, and special equipment is required for positioning and centering work, and these operations are affected by weather, dust, outside temperature, atmosphere, etc., so for example, welding For quality control purposes, it is necessary to weld only when the welds are in good condition, which increases the construction period.Also, since the work is outdoors, a large protective sheet is placed above the containment vessel to protect it from wind, snow, and rain. Furthermore, after the parts that will become the reactor pressure vessel are brought in, work on the reactor building construction site and inside the reactor containment vessel must be carried out simultaneously. Since this process has to be carried out, there is a risk that problems may arise with the safety and quality of the completed reactor pressure vessel.

このように、原子炉圧力容器を製作工場で組立
てて輸送するのでなく、多数の部品を発電所建設
現場で組立てる従来方法は、圧力容器内部構造物
の据付時間が著しく長期にわたり原子力発電所の
全体建設期間におけるクリチカルパスとなり、全
体建設工程が長期に及ぶ最大の原因となつてい
た。
In this way, the conventional method of assembling a large number of parts at the power plant construction site, rather than assembling the reactor pressure vessel at a manufacturing factory and transporting it, requires a significantly long time to install the internal structure of the pressure vessel, and it takes a long time to install the entire nuclear power plant. This became a critical path during the construction period, and was the biggest reason why the entire construction process took a long time.

本発明は、上述の種々の不都合を解消する為案
出されたもので、製作工場において原子炉圧力容
器の製作、組立てを行い、更に原子炉圧力容器に
輸送養生手段を構じ、然る後、原子炉圧力容器を
輸送することにより輸送の実現、安全化を図る一
方、発電所建設現場における原子炉圧力容器の組
立て作業をなくし、輸送されて来た原子炉圧力容
器を直ちに移動クレーンにより据付け作業をする
だけで良く、もつて大幅な工期の短縮が図り得、
また原子炉圧力容器の組立て作業の安全性の向上
及び品質の確保を図り得る原子炉圧力容器据付方
法を提供するものである。
The present invention was devised to solve the various inconveniences mentioned above, and involves manufacturing and assembling a nuclear reactor pressure vessel in a manufacturing factory, further configuring transportation and curing means for the reactor pressure vessel, and then By transporting the reactor pressure vessel, transportation is realized and made safer, while the assembly work of the reactor pressure vessel at the power plant construction site is eliminated, and the transported reactor pressure vessel is immediately installed using a mobile crane. All you have to do is do the work, and the construction period can be significantly shortened.
The present invention also provides a method for installing a reactor pressure vessel that can improve the safety of the reactor pressure vessel assembly work and ensure quality.

本発明のように、原子炉圧力容器、内部構造物
および制御棒ハウジングを予め製作工場で製し、
それを海上輸送等により原子力発電所の建設現場
へ運搬し、そのまま格納容器内に据付けること
は、従来全く行なわれていなかつた。
As in the present invention, the reactor pressure vessel, internal structure, and control rod housing are manufactured in advance at a manufacturing factory,
It has never been done in the past to transport nuclear power plants by sea or other means to the construction site of a nuclear power plant and install them in a containment vessel.

これは、沸騰水型原子炉においては原子炉圧力
容器、内部構造物および制御棒ハウジングの合計
重量が千数百トンにも及ぶものであるため、輸送
中に構成各部に生じる応力集中の影響が大きいと
考えられているからである。また原子炉という極
めて高い安全性を要求される技術分野でもあるた
め、工法の安全性を予め検証する必要がある。従
来はこのような新たな工法は全く考慮せず、伝統
的な建設現場での組立工法が採られていたもので
ある。
This is because in a boiling water reactor, the total weight of the reactor pressure vessel, internal structures, and control rod housing is over 1,000 tons, so the stress concentration that occurs in each component during transportation is This is because it is considered large. Furthermore, since nuclear reactors are a technical field that requires an extremely high level of safety, it is necessary to verify the safety of construction methods in advance. In the past, such new construction methods were not considered at all, and traditional assembly methods were used at the construction site.

本発明はこのような原子炉技術分野の特殊性に
鑑み、原子炉圧力容器、内部構造物および制御棒
ハウジングを予め製作工場で製し、これを原子力
発電所の建設現場へ運搬することに対する強度上
の要請を克服し、更に実際の運搬を行なつて構成
各部の安全性を実証したことにより提案されたも
のである。
In view of the uniqueness of the field of nuclear reactor technology, the present invention has been developed to manufacture reactor pressure vessels, internal structures, and control rod housings in advance in a manufacturing factory, and to provide sufficient strength to transport them to the construction site of a nuclear power plant. This was proposed after overcoming the above requirements and further verifying the safety of each component through actual transportation.

このような技術的要請に基づいて案出された本
発明の工法を、以下、本発明の原子炉圧力容器を
据付けた原子炉設備の構成を示す第4図及び第5
図を参照して説明する。
The construction method of the present invention, devised based on such technical requirements, will be described below as shown in Figures 4 and 5, which show the configuration of nuclear reactor equipment in which the reactor pressure vessel of the present invention is installed.
This will be explained with reference to the figures.

第4図は、原子炉建屋内に収容した原子炉圧力
容器の据付状態を示す縦断正面図である。原子炉
建屋1は中央部に格納壁2により画成された格納
室3を有し、この格納室3内に圧力容器据付用基
礎台4とこの基礎台4上に設置する原子炉圧力容
器5を囲繞する為の円筒状の生体遮蔽壁6を有し
て構築されている。この原子炉建屋1は原子炉圧
力容器5が製作工場で製作され輸送されて来る時
までに構築されるものである。原子炉圧力容器5
は、格納室3が真下に来るように横架したレール
7上に乗つており原子炉建屋1内に構築された屋
根トラス8を案内として水平移動できる移動クレ
ーン9により吊上げられ格納室3内へ上方より降
すようにして収容され圧力容器据付用基礎台4上
に据付けられるものである。圧力容器据付用基礎
台4及び生体遮蔽壁6は格納室内部構造物10を
介して格納壁2に支持されており、格納室3内に
は生体遮蔽壁6の外側に原子炉圧力容器5を制御
する為の所要の機器11が格納室内部構造物10
を利用して設置され、また原子炉圧力容器5に冷
却水等を供給する配管12は建屋内に設けられ格
納壁2を貫通し、更に生体遮断壁6を貫通して原
子炉圧力容器5の所要箇所と接続されている。
FIG. 4 is a longitudinal sectional front view showing the installed state of the reactor pressure vessel housed in the reactor building. The reactor building 1 has a containment chamber 3 defined by a containment wall 2 in the center, and inside the containment chamber 3 there is a pressure vessel installation foundation 4 and a reactor pressure vessel 5 installed on the foundation 4. It is constructed with a cylindrical biological shielding wall 6 for surrounding the body. This reactor building 1 is constructed before the reactor pressure vessel 5 is manufactured at a manufacturing factory and transported. Reactor pressure vessel 5
is mounted on a horizontal rail 7 so that the containment room 3 is directly below, and is lifted into the containment room 3 by a mobile crane 9 that can move horizontally using a roof truss 8 built inside the reactor building 1 as a guide. It is housed so as to be lowered from above and installed on the pressure vessel installation base 4. The pressure vessel installation base 4 and the biological shielding wall 6 are supported by the containment wall 2 via the containment chamber internal structure 10, and the reactor pressure vessel 5 is installed outside the biological shielding wall 6 in the containment chamber 3. The necessary equipment 11 for controlling is the internal structure 10 of the containment chamber.
The piping 12 that supplies cooling water etc. to the reactor pressure vessel 5 is installed inside the building and penetrates the containment wall 2 and further penetrates the biological barrier wall 6 to supply cooling water etc. to the reactor pressure vessel 5. Connected to required locations.

第5図は輸送可能状態を示す原子炉圧力容器5
の縦断正面図である。原子炉圧力容器5は、圧力
容器本体5Aと、圧力容器内部構造物であるジエ
ツトポンプ5B、シユラウド5C、炉心支持板5
D、上部格子板5E、LPCIカツプリング5F、
インコアハウジング5H、ガイドロツド5J、コ
アスプレイライン5K、及び給水スパージヤ5L
と、制御棒ハウジング5Gおよびドレイライン5
Iとを溶接組立てして形成されている。
Figure 5 shows the reactor pressure vessel 5 in a transportable state.
FIG. The reactor pressure vessel 5 includes a pressure vessel main body 5A, a jet pump 5B which is an internal structure of the pressure vessel, a shroud 5C, and a core support plate 5.
D, upper grid plate 5E, LPCI coupling ring 5F,
In-core housing 5H, guide rod 5J, core spray line 5K, and water supply spargeer 5L
, control rod housing 5G and drain line 5
It is formed by welding and assembling the parts I and I.

原子炉圧力容器5は、製作工場において製作組
立てられ、輸送車両の輸送高さ制限より倒伏状態
に輸送されるものである。制御棒ハウジング5G
は、圧力容器本体5Aの下部より突出しており輸
送の際不慮の事故により破損の虞れがあるので、
圧力容器本体5Aの下座部5Mに設置されている
輸送養生用のスカート13により覆われている。
更に、原子炉圧力容器5はスカート13に取付け
た支持構造物14及び圧力容器本体5Aの頭部一
側に取付けた支持構造物15を介して組をなす輸
送スキツド16上に乗せられている。
The reactor pressure vessel 5 is manufactured and assembled in a manufacturing factory, and is transported in a collapsed state due to transport height restrictions of transport vehicles. Control rod housing 5G
protrudes from the bottom of the pressure vessel main body 5A, and there is a risk of damage due to an unexpected accident during transportation.
It is covered by a transport curing skirt 13 installed on the lower seat 5M of the pressure vessel main body 5A.
Further, the reactor pressure vessel 5 is placed on a transport skid 16 which forms a set via a support structure 14 attached to the skirt 13 and a support structure 15 attached to one side of the head of the pressure vessel body 5A.

次に、本発明の原子炉圧力容器据付方法を上述
した構成の実施例において説明する。
Next, the reactor pressure vessel installation method of the present invention will be explained using an embodiment of the above-mentioned configuration.

先ず、製作工場内において、各製作機械により
圧力容器本体5Aと圧力内部構造物であるジエツ
トポンプ5B、シユラウド5C、炉心支持板5
D、上部格子板5E、LPCIカツプリング5F、
インコアハウジング5H、ガイドロツド5J、コ
アスプレイライン5K、及び給水スパージヤ5L
および制御棒ハウジング5G、ドレンライン5
I、とをそれぞれ製作してこれら部品を所要順序
により溶接組立てして完成品たる原子炉圧力容器
5を製作する。
First, in the manufacturing factory, the pressure vessel main body 5A, the jet pump 5B, which is the pressure internal structure, the shroud 5C, and the core support plate 5 are manufactured by each manufacturing machine.
D, upper grid plate 5E, LPCI coupling ring 5F,
In-core housing 5H, guide rod 5J, core spray line 5K, and water supply spargeer 5L
and control rod housing 5G, drain line 5
The reactor pressure vessel 5, which is a completed product, is manufactured by welding and assembling these parts in the required order.

次に、圧力容器本体5Aの下座部5Mより突出
する制御棒ハウジング5Gを覆うようにスカート
13を圧力容器本体5Aの下座部5Mに取付け、
更にこのスカート13に支持構造物14を固着す
る一方、圧力容器本体5Aの頭部一側にも支持構
造物15を取付け、然る後原子炉圧力容器5を上
記一対の支持構造物14及び15をして一対の輸
送スキツド16,16上に乗せて固定する。この
輸送スキツド16はコロを有しているもの或いは
丸鋼管を多数並べてコロとするもののいずれでも
良く、原子炉圧力容器5は一対の輸送スキツド1
6,16によつて移動可能状態となる。しかして
原子炉圧力容器5をウインチ(図示せず)等を使
用して少くし所要位置まで移動しクレーンを使用
して輸送車両(あるいは船舶)に積載し、製作工
場から原子力発電所建設現場まで輸送する。
Next, the skirt 13 is attached to the lower seat part 5M of the pressure vessel main body 5A so as to cover the control rod housing 5G protruding from the lower seat part 5M of the pressure vessel main body 5A,
Further, a support structure 14 is fixed to this skirt 13, and a support structure 15 is also attached to one side of the head of the pressure vessel main body 5A, and then the reactor pressure vessel 5 is fixed to the pair of support structures 14 and 15. Then, place it on a pair of transportation skids 16, 16 and fix it. The transport skid 16 may be one having rollers or one having many round steel pipes lined up to form a roller.
6 and 16, it becomes movable. Then, the reactor pressure vessel 5 is lowered using a winch (not shown), etc., moved to the required position, loaded onto a transport vehicle (or ship) using a crane, and transported from the manufacturing plant to the nuclear power plant construction site. transport.

一方、原子力発電所建設現場においては上述し
た原子炉圧力容器5の工場製作と並行して原子炉
建屋1を建設する。原子炉建屋1は、原子炉圧力
容器5が輸送されて来るまでに建設させて置くも
ので、中央部に圧力容器据付用基礎台4と原子炉
圧力容器5を囲繞する為の円筒状の生体遮蔽壁6
等を格納室3内に有するように構築し、また原子
炉圧力容器5に冷却水を供給する為の配管12は
原子炉圧力容器5との接続部分を除き全て設備し
て置き、その他サポートやパイプホイツプストラ
クチユア(PIPEWHIP―STRUCTURE)、各種
機器も設備して置く。そして、生体遮蔽壁6から
内部に突出する配管等はその内方端が原子炉圧力
容器5の外径より外側にあるようにして、原子炉
圧力容器5の吊り降しを可能にさせている。なお
パイプホイツプストラクチユアとは格納室内部構
造物10の一部分であり、万一の配管破断に伴う
配管のむち打ち現象から他の健全な配管、設備等
を防護するものである。
On the other hand, at the nuclear power plant construction site, the reactor building 1 is constructed in parallel with the above-mentioned factory fabrication of the reactor pressure vessel 5. The reactor building 1 is constructed before the reactor pressure vessel 5 is transported, and has a base 4 for installing the pressure vessel and a cylindrical living body to surround the reactor pressure vessel 5 in the center. Shielding wall 6
etc., in the containment chamber 3, and piping 12 for supplying cooling water to the reactor pressure vessel 5 is all installed except for the connection part with the reactor pressure vessel 5, and other supports and PIPEWHIP-STRUCTURE and various equipment will also be installed. The inner ends of the pipes, etc. that protrude inward from the biological shielding wall 6 are located outside the outer diameter of the reactor pressure vessel 5, thereby making it possible to suspend the reactor pressure vessel 5. . Note that the pipe whip structure is a part of the internal structure 10 of the containment chamber, and is used to protect other healthy pipes, equipment, etc. from the whiplash phenomenon of the pipes in the unlikely event that the pipes break.

次に、建設現場に輸送されて来た原子炉圧力容
器5は、原子炉建屋1にできるだけ近い位置でク
レーンを使用して輸送車両より積み降し、次にウ
インチを使用して原子炉建屋1に設備された移動
クレーン9を吊上げ位置まで適宜の方向変換を与
えながら輸送スキツドにより移動し、続いて移動
クレーン9により僅かに吊上げ停止した後一対の
輸送スキツド16,16、一対の支持構造物1
4,15及びスカート13を原子炉圧力容器5か
ら取外し、引続いて移動クレーンにより所要高さ
まで吊上げてから水平方向に移動し、格納室3の
真下まで来たら吊降して格納室3内の据付用基礎
台4上に下座部5Mをして着座させ、適正位置に
芯出しをして固定させる。然る後、原子炉圧力容
器5と配管12その他の附属設備とを接続し、最
終的に原子炉建屋1の上部残り工事を行えば原子
炉圧力容器5の据付工事と原子炉建屋1の構築を
完了する。
Next, the reactor pressure vessel 5 that has been transported to the construction site is unloaded from the transport vehicle using a crane at a position as close to the reactor building 1 as possible. The mobile crane 9 installed at
4, 15 and the skirt 13 from the reactor pressure vessel 5, and then hoisted to the required height by a mobile crane, moved horizontally, and when they reach just below the containment room 3, are lowered and placed inside the containment room 3. The lower seat part 5M is placed on the installation base 4 and is seated, centered and fixed at an appropriate position. After that, the reactor pressure vessel 5 is connected to the piping 12 and other auxiliary equipment, and finally the remaining work on the upper part of the reactor building 1 is completed, which completes the installation work of the reactor pressure vessel 5 and the construction of the reactor building 1. complete.

このように、本発明の原子炉圧力容器据付方法
は原子炉圧力容器と原子炉格納容器とを分割して
それぞれ別個に製し、受け入れ態勢が整つた原子
炉格納容器内へ工場で製した原子炉圧力容器を輸
送して来て据付けるものであるから、次のような
効果を奏する。
As described above, the reactor pressure vessel installation method of the present invention involves dividing the reactor pressure vessel and the reactor containment vessel, manufacturing them separately, and inserting the factory-produced nuclear reactor into the reactor containment vessel that is ready to receive the reactor pressure vessel. Since the reactor pressure vessel is transported and installed, the following effects are achieved.

(1) 原子炉圧力容器および原子炉格納容器を独立
して製することができるので、双方の製作工程
の干渉がなくなり、工期の短縮が図られる。ま
た、それぞれの製作は広い作業空間のもとで行
なうことができ、作業が安全でかつ迅速とな
る。
(1) Since the reactor pressure vessel and the reactor containment vessel can be manufactured independently, there is no interference between the manufacturing processes of both, and the construction period can be shortened. Moreover, each production can be carried out in a wide working space, making the work safe and quick.

(2) 原子炉発電所の建設現場で原子炉圧力容器を
組立てる従来の工法に比べて、清浄保持用の更
衣室や、制御棒ハウジングを圧力容器本体下部
に搬入する特設シユート等を原子炉格納容器内
に設けてなくてもよく、また、シユラウド、原
子炉圧力容器の芯出し作業の為の専用設備や芯
出しの為の精密な作業を必要としない。
(2) Compared to the conventional method of assembling the reactor pressure vessel at the construction site of a nuclear power plant, it is easier to store the reactor, such as a changing room for keeping it clean and a special chute to carry the control rod housing into the lower part of the pressure vessel body. It does not need to be provided inside the vessel, and does not require special equipment for centering the shroud or reactor pressure vessel or precise work for centering.

(3) 原子炉圧力容器を製作工場にて製するから、
例えば溶接部等の品質管理は、天候、外気温等
に影響されないので、工期が著しく短縮される
とともに、品質も更によくなる。
(3) Because the reactor pressure vessel is manufactured at the manufacturing factory,
For example, quality control of welded parts etc. is not affected by weather, outside temperature, etc., so the construction period is significantly shortened and the quality is further improved.

また、本発明の原子炉圧力容器据付方法は制御
棒ハウジングにスカートを被せた原子炉圧力容器
を支持構造物を介して輸送スキツドに乗せて輸送
するようにしたので完成品たる原子炉圧力容器を
製作工場において製作し、原子力発電所建設現場
までの安全な輸送が実現できる。
In addition, in the reactor pressure vessel installation method of the present invention, the reactor pressure vessel, in which the control rod housing is covered with a skirt, is transported on a transportation skid via a support structure, so that the reactor pressure vessel as a completed product is transported. It can be manufactured at a manufacturing factory and safely transported to the nuclear power plant construction site.

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

第1図は原子炉圧力容器と内部構造物を示す断
面図、第2図は従来の原子炉圧力容器据付方法を
示す原子炉格納容器部の断面図、第3図は従来の
原子炉圧力容器の内部構造物の据付状態を示す第
2図同様の断面図、第4図は本発明の原子炉圧力
容器据付方法の実施例に係り、原子炉建屋内に収
容した原子炉圧力容器の据付状態の説明用縦断正
面図、第5図は原子炉圧力容器の構造と運搬可能
状態の説明用正面図である。 1…原子炉建屋、4…圧力容器据付用基礎台、
5…原子炉圧力容器、6…生体遮蔽壁、9…移動
クレーン、13…スカート、14,15…支持構
造物、16…輸送スキツド、5A…圧力容器本
体、5C…シユラウド、5G…制御棒ハウジン
グ。
Figure 1 is a sectional view showing the reactor pressure vessel and its internal structures, Figure 2 is a sectional view of the reactor containment vessel section showing a conventional reactor pressure vessel installation method, and Figure 3 is a sectional view of the conventional reactor pressure vessel. Figure 4 is a cross-sectional view similar to Figure 2 showing the installed state of the internal structure of the reactor pressure vessel, and Figure 4 shows the installed state of the reactor pressure vessel accommodated in the reactor building, according to an embodiment of the reactor pressure vessel installation method of the present invention. FIG. 5 is an explanatory front view of the structure and transportable state of the reactor pressure vessel. 1...Reactor building, 4...Pressure vessel installation foundation,
5... Reactor pressure vessel, 6... Biological shielding wall, 9... Mobile crane, 13... Skirt, 14, 15... Support structure, 16... Transport skid, 5A... Pressure vessel body, 5C... Shroud, 5G... Control rod housing .

Claims (1)

【特許請求の範囲】[Claims] 1 予め製作工場において、原子炉圧力容器の圧
力容器本体を製作し、その圧力容器本体内に少な
くともシユラウドを設けるとともに、圧力容器本
体の下座部より突出するようにして制御棒ハウジ
ングを前記シユラウドと芯合わして設けて原子炉
圧力容器を製し、次に圧力容器本体の下座部より
突出する制御棒ハウジングをスカート及びこのス
カートに取付ける第1の支持構造物で覆い、さら
に圧力容器本体の頭に取付ける第2の支持構造物
を介して前記原子炉圧力容器を倒伏状態にして一
対の輸送用スキツド上に乗せて製作工場から建設
現場までのうち陸上部を輸送し、一方原子炉圧力
容器の輸送時までに、原子炉圧力容器据付用基礎
台と原子炉圧力容器を収容する生体遮蔽壁と、前
記原子炉圧力容器に接続される配管、サポートお
よびパイプホイツプストラクチユア等の付属設備
とを原子炉圧力容器の吊り降し可能なように予め
構築して置き、輸送して来た原子炉圧力容器をク
レーンにより吊上げ上記輸送用スキツドと第1及
び第2の支持構造物とスカートとを取外し上記原
子炉圧力容器据付用基礎台上に着座固定させ、然
る後上記配管とサポートと及びパイプホイツプス
トラクチユア等の原子炉圧力容器に対する接続箇
所を原子炉圧力容器と接続して成ることを特徴と
する原子炉圧力容器据付方法。
1 The pressure vessel body of the reactor pressure vessel is manufactured in advance at a manufacturing factory, and at least a shroud is provided within the pressure vessel body, and the control rod housing is attached to the shroud so as to protrude from the lower seat of the pressure vessel body. The control rod housing protruding from the lower seat of the pressure vessel body is covered with a skirt and a first support structure attached to the skirt, and the head of the pressure vessel body is then covered with a skirt and a first support structure attached to the skirt. The reactor pressure vessel is laid down and placed on a pair of transport skids to transport the land portion from the fabrication plant to the construction site via a second support structure attached to the reactor pressure vessel. By the time of transportation, the reactor pressure vessel installation foundation, the biological shielding wall that accommodates the reactor pressure vessel, and attached equipment such as piping, supports, and pipe whip structures connected to the reactor pressure vessel The reactor pressure vessel is constructed in advance so that it can be lifted and lowered, and the transported reactor pressure vessel is lifted by a crane and the transportation skid, the first and second support structures, and the skirt are assembled. Remove the reactor pressure vessel and seat it on the base for installing the reactor pressure vessel, and then connect the piping and supports and the connection points to the reactor pressure vessel such as the pipe whip structure with the reactor pressure vessel. A nuclear reactor pressure vessel installation method characterized by comprising:
JP7458778A 1978-06-20 1978-06-20 Method of installing pressure vessel for nuclear reactor Granted JPS552134A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7458778A JPS552134A (en) 1978-06-20 1978-06-20 Method of installing pressure vessel for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7458778A JPS552134A (en) 1978-06-20 1978-06-20 Method of installing pressure vessel for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS552134A JPS552134A (en) 1980-01-09
JPS629706B2 true JPS629706B2 (en) 1987-03-02

Family

ID=13551434

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7458778A Granted JPS552134A (en) 1978-06-20 1978-06-20 Method of installing pressure vessel for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS552134A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03126285U (en) * 1990-04-03 1991-12-19
WO2021019480A1 (en) 2019-07-31 2021-02-04 深圳智科微铝科技有限公司 Production method for electrode for power storage device, and electrode for power storage device

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5963188B2 (en) * 2012-02-09 2016-08-03 三菱重工業株式会社 Skid, apparatus carrying-in apparatus provided with the same, and apparatus carrying-in method using the same
US11725411B2 (en) * 2020-08-17 2023-08-15 Terrapower, Llc Nuclear fuel assembly with multi-pitch wire wrap

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5032391A (en) * 1973-07-25 1975-03-29

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5032391A (en) * 1973-07-25 1975-03-29

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03126285U (en) * 1990-04-03 1991-12-19
WO2021019480A1 (en) 2019-07-31 2021-02-04 深圳智科微铝科技有限公司 Production method for electrode for power storage device, and electrode for power storage device

Also Published As

Publication number Publication date
JPS552134A (en) 1980-01-09

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