JP2804787B2 - Method of assembling reactor pressure vessel with main steam flow nozzle - Google Patents
Method of assembling reactor pressure vessel with main steam flow nozzleInfo
- Publication number
- JP2804787B2 JP2804787B2 JP1165212A JP16521289A JP2804787B2 JP 2804787 B2 JP2804787 B2 JP 2804787B2 JP 1165212 A JP1165212 A JP 1165212A JP 16521289 A JP16521289 A JP 16521289A JP 2804787 B2 JP2804787 B2 JP 2804787B2
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- pressure vessel
- nozzle
- reactor pressure
- flow nozzle
- 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 - Fee Related
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Description
【発明の詳細な説明】 ［産業上の利用分野］ 本発明は沸騰水型原子力発電プラントにおける圧力容
器の組み立て方法に関し、とりわけ圧力容器に取り付け
られている主蒸気ノズル内にフローノズルを設ける改良
型沸騰水型原子力プラントにおける圧力容器の組み立て
方法の改良に関する。Description: FIELD OF THE INVENTION The present invention relates to a method for assembling a pressure vessel in a boiling water nuclear power plant, and more particularly to an improved type in which a flow nozzle is provided in a main steam nozzle attached to the pressure vessel. The present invention relates to an improvement in a method for assembling a pressure vessel in a boiling water nuclear power plant.
［従来の技術］ 沸騰水型原子力発電プラントにおいては、原子炉圧力
容器からの主蒸気系にフローノズルが設けられている。
このフローノズルは、主蒸気系の流量を調整する働きの
ものであるためその精度並びに性能の維持はフローノズ
ルの重要な課題である。一方従来の沸騰水型原子力発電
プラントにおけるフローノズルは予め圧力容器に取り付
けられている主蒸気ノズルと原子炉格納容器の貫通部を
結ぶ配管の中に取り付けられる構造であったため、工場
内で組み立てられ、その段階でフローノズルの性能の試
験が行なわれた後、現地においてあらためて据え付ける
ようにしていたのであるが、現在開発中の改良型沸騰水
型原子炉においては同プラントの特性上、フローノズル
を原子炉圧力容器主蒸気ノズル内に組み込んだ構造とな
っているため、主蒸気ノズルは、従来の原子炉における
ものに比べて長いものとならざるを得ない。従って、こ
のようにな長い主蒸気ノズルを備えた圧力容器を現地に
おいて据え付けようとしても同主蒸気ノズルが躯体と干
渉することから、ノズルを第５図に示すように長さ方向
に２分割とし、圧力容器を搬入据え付けた後に分割され
たノズル部分を溶接によって組み立てる方法がとられて
いた。同図において原子炉圧力容器２を原子炉格納容器
内10に設置する場合、原子炉圧力容器２を圧力容器スカ
ート部９が原子炉格納容器ペデスタル８に達するまで上
方から挿入する方法がとられるが、このとき主蒸気ノズ
ルが躯体７と干渉してしまうので、主蒸気ノズル１に溶
接線４を設けて２分割し、原子炉圧力容器を据え付けた
後に両者を溶接接合する方法をとっていた。[Related Art] In a boiling water nuclear power plant, a flow nozzle is provided in a main steam system from a reactor pressure vessel.
Since the flow nozzle functions to adjust the flow rate of the main steam system, maintaining its accuracy and performance is an important issue of the flow nozzle. On the other hand, the flow nozzle in a conventional boiling water nuclear power plant was constructed in a factory because it was attached in a pipe that connects the main steam nozzle previously attached to the pressure vessel and the penetration of the containment vessel. At that stage, after testing the performance of the flow nozzles, they had to re-install them at the site.However, due to the characteristics of this plant, the flow nozzles were Since the structure is incorporated in the main steam nozzle of the reactor pressure vessel, the main steam nozzle is inevitably longer than that in the conventional reactor. Therefore, even if a pressure vessel equipped with such a long main steam nozzle is installed on site, the main steam nozzle interferes with the skeleton, so the nozzle is divided into two parts in the length direction as shown in FIG. Then, a method has been adopted in which the divided nozzle portions are assembled by welding after carrying in and installing the pressure vessel. In the figure, when the reactor pressure vessel 2 is installed in the reactor containment vessel 10, a method is employed in which the reactor pressure vessel 2 is inserted from above until the pressure vessel skirt 9 reaches the reactor containment vessel pedestal 8. At this time, since the main steam nozzle interferes with the skeleton 7, the welding line 4 is provided on the main steam nozzle 1 and divided into two parts. After the reactor pressure vessel is installed, the two are welded and joined.
原子炉圧力容器のノズルは従来は同圧力容器と一体と
されており、例えば実開昭62−143890号公報に見られる
ようなノズル内部の構造の改良に関する技術は開示され
ているが本発明の課題に関するものは見あたらない。Conventionally, the nozzle of a reactor pressure vessel is integrated with the same pressure vessel, and a technique for improving the internal structure of the nozzle as disclosed in, for example, Japanese Utility Model Publication No. Sho 62-143890 has been disclosed. I can't find anything about the issue.
［発明が解決しようとする課題］ このようなフローノズルの組み立て方法は以下のよう
な課題がある。[Problem to be Solved by the Invention] The method for assembling such a flow nozzle has the following problems.
フローノズルは主蒸気の流量を調整する重要な役割を
持つため、工場で予めその性能を確保できることを確認
した上で現地において組み立てることになるが、上記の
分割方法においては性能試験の後でこれを分割し、現地
において再組み立てすることになり、従って、現地にお
ける組み立ては作業精度を非常に厳しいものとせざるを
得ない。Since the flow nozzle plays an important role in adjusting the flow rate of the main steam, it must be assembled at the factory after confirming that the performance can be secured in advance at the factory. Is to be divided and reassembled on-site, so that on-site assembling has to be performed with extremely high working accuracy.
主蒸気ノズルの材質は炭素鋼であり、フローノズルの
材質はステンレス鋼であることから、分割された主蒸気
ノズルとフローノズルを現地において組み立てるには２
種類の溶接方法を採用しなければならないので、フロー
ノズルの溶接接合は内部から行なわなければならないの
とで非常に多くの作業工数が要求される。Since the material of the main steam nozzle is carbon steel and the material of the flow nozzle is stainless steel, it is necessary to assemble the divided main steam nozzle and flow nozzle on site.
Since various types of welding methods must be employed, the welding and joining of the flow nozzle must be performed from the inside, which requires a very large number of work steps.
フローノズルの精度に対する要求が厳しいものである
ために、据え付け後の検査においてもまた定期検査時に
おける同溶接部の供用期間中検査においてもより多大な
工数を必要とされる。Due to strict requirements on the accuracy of the flow nozzle, a greater number of man-hours are required both in the inspection after installation and in the inspection during the service period of the welded part during the periodic inspection.
［課題を解決するための手段］ 本発明は上記の課題を解決するために、原子炉圧力容
器に取り付けられた主蒸気ノズル内に主蒸気フローノズ
ルを設けてなるものを組み立てる方法において、原子炉
圧力容器を現地に据え付けた後に主蒸気ノズルに予め主
蒸気フローノズルを設けたものを同原子炉圧力容器に取
り付けるようにしたことを特徴とする。Means for Solving the Problems In order to solve the above problems, the present invention relates to a method for assembling a reactor having a main steam flow nozzle provided in a main steam nozzle attached to a reactor pressure vessel. After the pressure vessel is installed on site, a main steam nozzle provided with a main steam flow nozzle in advance is attached to the reactor pressure vessel.
［作用］ 本発明においては、主蒸気ノズルに予め主蒸気フロー
ノズルを設けたものを原子炉圧力容器と別体に製作し、
これを現地において取り付けるので、主蒸気ノズルを取
り付けた状態で据え付ける場合のように躯体と干渉する
恐れがなく、フローノズルは製作の段階から据え付けの
段階まで常に一体構造となっているので組み立て后のフ
ローノズルの精度が工場における検査時の状態を維持す
ることが容易である。また据え付け時における取り付け
作業は主蒸気ノズルを原子炉圧力容器に取り付ければよ
いのであるから、主蒸気ノズルとフローノズルをそれぞ
れ接合する場合に比べてはるかに作業が簡単であり、信
頼性も向上する。[Operation] In the present invention, a main steam nozzle provided with a main steam flow nozzle in advance is manufactured separately from the reactor pressure vessel,
Since this is installed on site, there is no danger of interference with the skeleton as in the case of installation with the main steam nozzle attached, and the flow nozzle is always integrated from the manufacturing stage to the installation stage, so after assembly It is easy to maintain the accuracy of the flow nozzle at the time of inspection at the factory. In addition, since the installation work at the time of installation can be performed by simply attaching the main steam nozzle to the reactor pressure vessel, the work is much easier and the reliability is improved compared to the case where the main steam nozzle and the flow nozzle are respectively joined. .
［実施例］ 以下、本発明の実施例を、図面を用いて説明する。Example An example of the present invention will be described below with reference to the drawings.
本発明による主蒸気ノズルの据え付け方法を第１図に
示す。原子炉圧力容器２と主蒸気ノズル１を分離してお
き、原子炉圧力容器２を据え付け後、圧力容器内部か
ら、フローノズルを組込まれた主蒸気ノズルを設置し、
接合部３にて原子炉圧力容器２と主蒸気ノズル１を接合
する。FIG. 1 shows a method for installing a main steam nozzle according to the present invention. After the reactor pressure vessel 2 and the main steam nozzle 1 are separated and the reactor pressure vessel 2 is installed, a main steam nozzle incorporating a flow nozzle is installed from inside the pressure vessel,
At the joint 3, the reactor pressure vessel 2 and the main steam nozzle 1 are joined.
原子炉圧力容器２と主蒸気ノズルとを接合する方法の
実施例をそれぞれ第２図、第３図及び第４図に示す。Embodiments of the method for joining the reactor pressure vessel 2 and the main steam nozzle are shown in FIGS. 2, 3 and 4, respectively.
溶接による接合としては、第２図に示す如く、原子炉
圧力容器２の殻壁の一部を主蒸気ノズル１の基部に形成
し、ノズルを内部から設置できるように加工しておく。
主蒸気ノズル１を設置後、溶接部４の如く溶接にて接合
し、主蒸気ノズルの基部に形成された殻壁の一部を圧力
容器の殻壁と一体化させる。As for the joining by welding, as shown in FIG. 2, a part of the shell wall of the reactor pressure vessel 2 is formed at the base of the main steam nozzle 1 and processed so that the nozzle can be installed from the inside.
After the main steam nozzle 1 is installed, the main steam nozzle 1 is joined by welding like a welded portion 4, and a part of the shell wall formed at the base of the main steam nozzle is integrated with the shell wall of the pressure vessel.
ボルト結合による方法としては、第３図の如く主蒸気
ノズル１は、原子炉圧力容器２に内側からはめ込む構造
となっている。主蒸気ノズル１をはめ込んだ後、植込み
ボルト３とナット４により蒸気ノズル１と原子炉圧力容
器２を接合する。なお、本方法による場合は、Ｏリング
５を接合面に設け内部流体の漏洩を防護する手段を講じ
るものとする。As a method by bolt connection, as shown in FIG. 3, the main steam nozzle 1 is configured to be fitted into the reactor pressure vessel 2 from the inside. After fitting the main steam nozzle 1, the steam nozzle 1 and the reactor pressure vessel 2 are joined by the studs 3 and the nuts 4. In the case of this method, a means for protecting the leakage of the internal fluid by providing the O-ring 5 on the joint surface is taken.
ネジ結合による方法としては、第４図に示す如く、主
蒸気ノズル１と原子炉圧力容器２の結合面にネジ６を設
け接合する。尚、本方法もボルト結合による方法と同じ
く、内部流体の漏洩を防護する手段として、Ｏリング５
を結合面に設ける。As a method by screw connection, as shown in FIG. 4, a screw 6 is provided on the connection surface between the main steam nozzle 1 and the reactor pressure vessel 2 and joined. In this method, similarly to the method by bolt connection, as a means for protecting the leakage of the internal fluid, an O-ring 5 is used.
Is provided on the coupling surface.
［発明の効果］ 本発明による改良型沸騰水型原子力発電プラントの原
子炉圧力容器の主蒸気ノズルの据付方法を採用すること
により、以下に示す効果が得られる。[Effects of the Invention] The following effects can be obtained by employing the method of installing the main steam nozzle of the reactor pressure vessel of the improved boiling water nuclear power plant according to the present invention.
（１）据付時の工数、仕上げ、検査の工数の大幅削減を
図ることができる。(1) Man-hours for installation, finishing, and inspection can be significantly reduced.
（２）主蒸気フローノズルの性能の確保が図れ、信頼性
が向上する。(2) The performance of the main steam flow nozzle can be ensured, and the reliability is improved.
第１図は、本発明による原子炉圧力容器と主蒸気ノズル
の据付方法を示す概念図、第２図、第３図及び第４図は
それぞれ、原子炉圧力容器と主蒸気ノズルの接合に関
し、溶接による方法、ボルト接合による方法及びネジ結
合による方法を示す主要部断面図、第５図は改良型沸騰
水型原子力発電プラントの原子炉圧力容器の据付状態を
示す略線図である。 １……主蒸気ノズル、２……原子炉圧力容器、３……接
合部、４……溶接接合、５……Ｏリング。FIG. 1 is a conceptual diagram showing a method of installing a reactor pressure vessel and a main steam nozzle according to the present invention, and FIGS. 2, 3 and 4 respectively relate to joining of a reactor pressure vessel and a main steam nozzle, FIG. 5 is a schematic cross-sectional view of a main part showing a method by welding, a method by bolt connection and a method by screw connection, and FIG. 5 is a schematic diagram showing an installation state of a reactor pressure vessel of an improved boiling water nuclear power plant. 1 ... main steam nozzle, 2 ... reactor pressure vessel, 3 ... joint, 4 ... weld joint, 5 ... O-ring.
Claims (2)
ズル内に主蒸気フローノズルを設けてなるものを組み立
てる方法において、 前記主蒸気ノズルの基部に原子炉圧力容器の殻壁の一部
を予め形成し、 原子炉圧力容器を現地に据え付けた後に、予め主蒸気フ
ローノズルを設けた前記主蒸気ノズルを原子炉圧力容器
に取り付けるようにしたことを特徴とする主蒸気フロー
ノズルを有する原子炉圧力容器の組み立て方法。1. A method of assembling a reactor having a main steam flow nozzle provided in a main steam nozzle attached to a reactor pressure vessel, wherein a part of a shell wall of the reactor pressure vessel is previously provided at a base of the main steam nozzle. The reactor pressure having a main steam flow nozzle, wherein the main steam nozzle provided with a main steam flow nozzle beforehand is attached to the reactor pressure vessel after the reactor pressure vessel is installed on site. How to assemble the container.
ルの基部に前記圧力容器の殻壁の一部を形成するフラン
ジ部を形成し、予め同フランジ部を収納するように形成
された同圧力容器の殻壁にこの主蒸気ノズルのフランジ
部を同殻壁とのネジ結合またはボルト結合により取りつ
け、その際同フランジ部と同殻壁の間にＯリングを介在
させるようにしたことを特徴とする主蒸気フローノズル
を有する原子炉圧力容器の組み立て方法。2. The invention according to claim 1, wherein a flange portion forming a part of a shell wall of said pressure vessel is formed at a base portion of said main steam nozzle, and said flange portion is formed in advance to receive said flange portion. The flange portion of the main steam nozzle is mounted on the shell wall of the pressure vessel by screw connection or bolt connection with the shell wall, and an O-ring is interposed between the flange portion and the shell wall. Of assembling a reactor pressure vessel having a main steam flow nozzle.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1165212A JP2804787B2 (en) | 1989-06-29 | 1989-06-29 | Method of assembling reactor pressure vessel with main steam flow nozzle |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1165212A JP2804787B2 (en) | 1989-06-29 | 1989-06-29 | Method of assembling reactor pressure vessel with main steam flow nozzle |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0331795A JPH0331795A (en) | 1991-02-12 |
| JP2804787B2 true JP2804787B2 (en) | 1998-09-30 |
Family
ID=15807979
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1165212A Expired - Fee Related JP2804787B2 (en) | 1989-06-29 | 1989-06-29 | Method of assembling reactor pressure vessel with main steam flow nozzle |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2804787B2 (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6280587A (en) * | 1985-10-03 | 1987-04-14 | 株式会社東芝 | Pressure vessel device for nuclear reactor and assembling method thereof |
-
1989
- 1989-06-29 JP JP1165212A patent/JP2804787B2/en not_active Expired - Fee Related
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6280587A (en) * | 1985-10-03 | 1987-04-14 | 株式会社東芝 | Pressure vessel device for nuclear reactor and assembling method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0331795A (en) | 1991-02-12 |
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