JPS62132199A - Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container - Google Patents

Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container

Info

Publication number
JPS62132199A
JPS62132199A JP60271535A JP27153585A JPS62132199A JP S62132199 A JPS62132199 A JP S62132199A JP 60271535 A JP60271535 A JP 60271535A JP 27153585 A JP27153585 A JP 27153585A JP S62132199 A JPS62132199 A JP S62132199A
Authority
JP
Japan
Prior art keywords
exhaust pipe
piping
safety valve
main steam
steam relief
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP60271535A
Other languages
Japanese (ja)
Inventor
稔 増田
古川 秀康
高一 斎藤
佐藤 智二郎
寺門 典之
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
Hitachi Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hitachi Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP60271535A priority Critical patent/JPS62132199A/en
Publication of JPS62132199A publication Critical patent/JPS62132199A/en
Pending 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

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の利用−分野〕 本発明は、沸騰水型原子炉格納容器主蒸気逃し安全弁排
気管に係り、特に熱反力激減に好適な主蒸気逃し安全弁
排気管の接続構造に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a main steam safety relief valve exhaust pipe for a boiling water reactor containment vessel, and in particular to a connection of a main steam safety safety valve exhaust pipe suitable for drastically reducing thermal reaction force. Regarding structure.

【発明の背景〕[Background of the invention]

従来の公知例を以下に説明する。 Conventional known examples will be explained below.

第4図に沸騰水型原子炉格納容器の全体図を示す。原子
炉格納容器主蒸気逃し安全弁排気管配管1は、原子炉圧
力容器2内の圧力が過渡に上昇した場合に、主蒸気管3
に設置された主蒸気逃し安全弁4より、主蒸気の一部を
圧力抑制室プール水中5のスパージャ6に導くことを目
的として設置されている。また、主蒸気逃し安全弁排気
管lは、原子炉圧力容器2を内包する原子炉格納容器ド
ライウェル11内よりベローズ9を介し、ダイヤフラム
フロア10を貫通し圧力抑制室12に導かれている。こ
のダイヤフラムフロア10貫通部のベローズ9は、排気
管配管内を流れる主蒸気の高温・高圧等の荷重による排
気管配管の強制変位を吸収し、さらにドライウェル11
と圧力抑制室12とをシールするために設けられている
Figure 4 shows an overall view of the boiling water reactor containment vessel. The reactor containment vessel main steam relief safety valve exhaust pipe piping 1 is used to release the main steam pipe 3 when the pressure inside the reactor pressure vessel 2 rises transiently.
It is installed for the purpose of guiding a part of the main steam to the sparger 6 in the pressure suppression chamber pool underwater 5 through the main steam relief safety valve 4 installed in the pressure suppression chamber. Further, the main steam relief safety valve exhaust pipe 1 is led from inside the reactor containment vessel dry well 11 containing the reactor pressure vessel 2 through the bellows 9, through the diaphragm floor 10, and into the pressure suppression chamber 12. The bellows 9 of the diaphragm floor 10 penetrating portion absorbs the forced displacement of the exhaust pipe due to loads such as high temperature and high pressure of the main steam flowing inside the exhaust pipe, and furthermore, the bellows 9 of the diaphragm floor 10 penetrates
and the pressure suppression chamber 12.

また、第3図に示すように、排気管配管1は、圧力抑制
室12内で地震荷重等の機械的荷重による配管反力に対
する排気管配管1の強度を確保するため数多くの配管サ
ポート14で支持されている。さらに、排気管配管1内
を流れる高温の主蒸気による排気管配管lの熱膨張を逃
し、排気管配管1の熱応力緩和のために、排気管配管1
は、曲がり部が多くなっている。
In addition, as shown in FIG. 3, the exhaust pipe 1 is provided with a number of pipe supports 14 in order to ensure the strength of the exhaust pipe 1 against pipe reaction forces due to mechanical loads such as earthquake loads within the pressure suppression chamber 12. Supported. Furthermore, the exhaust pipe piping 1 is designed to release the thermal expansion of the exhaust pipe piping 1 due to the high temperature main steam flowing inside the exhaust pipe piping 1, and to relieve the thermal stress of the exhaust pipe piping 1.
has many curved parts.

さらに、排気情況g1は、スパージャ6の頂部開口と溶
接により接続され、スパージャ6は、下部のスパージャ
サポート7及びアンカボルト8を介し、原子炉格納容器
底部マット13に固定されている。
Further, the exhaust condition g1 is connected to the top opening of the sparger 6 by welding, and the sparger 6 is fixed to the reactor containment vessel bottom mat 13 via a lower sparger support 7 and an anchor bolt 8.

また、本主蒸気逃し安全弁排気管1の配管ルート設計は
、以下の要領で行われる。
In addition, the piping route design for the main steam relief safety valve exhaust pipe 1 is performed in the following manner.

(i)地震荷重及び機械的荷重による配管反力に対する
補強のための配管サポート14配置設計。
(i) Piping support 14 layout design for reinforcement against piping reaction force due to earthquake load and mechanical load.

(ii)高温による配管の軸方向熱膨張を逃すため、排
気管配管1を曲がり管を用いて、迂回させる配管ルート
設計。
(ii) A piping route design in which the exhaust pipe piping 1 is detoured by using a bent pipe in order to release the axial thermal expansion of the piping due to high temperature.

(iii )上記(i)の配管サポート14により、排
気管配管1は拘束され、配管内主蒸気による熱応力が厳
しくなるため、上記(i)及び(ii)のバランス設計
(iii) The exhaust pipe piping 1 is restrained by the piping support 14 in the above (i), and the thermal stress caused by the main steam in the piping becomes severe, so the design balances the above (i) and (ii).

このような構造であるため、次のような問題点がある。This structure has the following problems.

(a)地震荷重及び機械的荷重に対する配管サポート配
置設計と、サポート拘束による配管の熱応力緩和のため
の配管ルート設計とのバランス設計が必要であり、設計
工数の増大となる。
(a) A balanced design is required between the piping support arrangement design for seismic loads and mechanical loads, and the piping route design for mitigating the thermal stress of the piping due to support restraint, which increases the number of design steps.

(b)配管サポートの拘束による熱応力低減のため配管
に曲がり管を設け、大きく迂回した配管ルートとするた
め、工数増大、及びコストアップとなる。
(b) In order to reduce the thermal stress due to the restriction of the piping support, bent pipes are provided in the piping and the piping route is made with a large detour, which increases the number of man-hours and costs.

(c)上記(b)において、他の容器内構造物との干渉
を避は大きく迂回した配管ルートとなるため、容器内の
空間スペースが減少し有効活用が図れない。
(c) In (b) above, since the piping route is largely detoured to avoid interference with other internal structures of the container, the space inside the container is reduced and cannot be used effectively.

以上のような従来技術の問題点を解決すべく、抜本的な
構造上の対策が必要となっている。
In order to solve the problems of the prior art as described above, drastic structural measures are required.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、沸騰水型原子炉格納容器主蒸気逃し安
全弁排気管において、熱荷重による応力を激減できる管
の重ね合わせ構造を有する主蒸気逃し安全弁排気管構造
を提供するものである。
An object of the present invention is to provide a main steam safety safety valve exhaust pipe structure for a boiling water reactor containment vessel, which has a structure in which pipes are overlapped to drastically reduce stress due to thermal load.

〔発明の概要〕[Summary of the invention]

本発明は、従来の主蒸気逃し安全弁における配管の迂回
による熱応力緩和方法における配管サポート数の増加と
いう問題点を解決すべく、排気管配管1とスパージャ6
の頂部開口部との継手を単純な管の重ね合わせたはめ合
い構造を用いている。
The present invention solves the problem of an increase in the number of piping supports in the conventional main steam relief safety valve by detouring the piping to alleviate the thermal stress.
The joint with the top opening of the pipe uses a simple overlapping structure of pipes.

本発明により、排気管配管1のスパジャ6継手部の配管
軸方向が、拘束されないため、熱応力が激減でき、配管
の迂回及びそれに伴う配管サポート14部を削減できる
効果を奏する。
According to the present invention, the piping axis direction of the sparger 6 joint part of the exhaust pipe piping 1 is not restricted, so thermal stress can be drastically reduced, and the detour of the piping and the accompanying piping support 14 can be reduced.

〔発明の実施例〕[Embodiments of the invention]

以下本発明の一実施例を第1図及び第2図により説明す
る。
An embodiment of the present invention will be described below with reference to FIGS. 1 and 2.

第1図において、本実施例は、排気管配管1は、スパー
ジャ6頂部開口部の内側にわずかな間隙をもって重ね合
わせはめ込まれており、排気管配管1とスパージャ6は
、配管の軸方向において、各々独立の変位が可能である
In FIG. 1, in this embodiment, the exhaust pipe 1 is fitted inside the top opening of the sparger 6 with a slight gap, and the exhaust pipe 1 and the sparger 6 are arranged in the axial direction of the pipe. Each independent displacement is possible.

第2図において、ダイヤフラムフロア10より下方の圧
力抑制室12内の排気管配管1は、迂回することなく、
真直な最短距離の配管ルートを通り、スパージャ6に接
合されている。
In FIG. 2, the exhaust pipe piping 1 in the pressure suppression chamber 12 below the diaphragm floor 10 does not take a detour.
It passes through the straight, shortest piping route and is connected to the sparger 6.

このため1本発明における排気管配管1とスパージャ6
の接合部で、排気管配管1の軸方向が拘束されないため
、排気管配管の熱膨張にょる熱応   力は発生しない
For this reason, 1 the exhaust pipe piping 1 and the sparger 6 in the present invention
Since the axial direction of the exhaust pipe 1 is not constrained at the joint, no thermal stress is generated due to thermal expansion of the exhaust pipe.

また、排気管配管1とスパージャ6頂部開口部との接合
部には、わずかな間隙が設けられ配管が重ね合わされて
いるが、この間隙は、スパージャ6同様に水中に設けら
れ、スパージャ6の排気口からの蒸気吹き出し量に比べ
てこの間隙部からのリーク量はごく微量のため、構造及
びメンテナンス上も特に問題がない。
In addition, a small gap is provided at the joint between the exhaust pipe 1 and the top opening of the sparger 6, and the pipes are overlapped. Since the amount of leakage from this gap is very small compared to the amount of steam blown out from the mouth, there are no particular problems in terms of structure and maintenance.

(発明の効果) 本発明は、上記のように構成され作用するので次の効果
を奏することができる。
(Effects of the Invention) Since the present invention is configured and operates as described above, the following effects can be achieved.

(i)排気管配管とスパージャ頂部を配管の重ね合わせ
はめ合い構造とすることにより、配管の熱応力低減のた
めの迂回配管ルートを設けることなく、最短距離の配管
ルートとでき、大幅な物量の低減に伴うコスト低減が可
能となる。
(i) By making the exhaust pipe piping and the top of the sparger overlap and fit together, the shortest piping route is possible without the need for a detour piping route to reduce thermal stress in the piping, and a significant amount of material can be saved. It is possible to reduce costs as a result of this reduction.

(n)上記(i)より、配管の熱応力低域のための迂回
ルートがなくなり、それに伴い、配管サポ−トが削減で
きる。
(n) From (i) above, there is no detour route for the low thermal stress region of the piping, and accordingly, the number of piping supports can be reduced.

(iii)上記(i)より、配管迂回ルートによる容器
内の空間スペース確保ができ、容器内の据付作業の作業
性向上が図れる。
(iii) From the above (i), the space inside the container can be secured by the piping bypass route, and the workability of the installation work inside the container can be improved.

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

第1図は本発明を利用した沸騰水型原子炉格納容器主蒸
気逃し安全弁排気管の詳細図、第2図は本発明を利用し
た沸騰水型原子炉格納容器の縦断面図、第3図は従来の
沸騰水型原子炉格納容器主蒸気逃がし安全弁排気管の鳥
徹図、第4図は従来の沸騰水型原子炉格納容器の縦断面
図である。 1・・・排気管配管、2・・・原子炉圧力容器、3・・
・主蒸気管、4・・・主蒸気逃し安全弁、5・・・圧力
抑制室プール水、6・・・スパージャ、7・・・スパー
ジャサポート、8・・・アンカボルト、9・・・ベロー
ズ、10・・・ダイヤワラ11フロア、11・・・原子
炉格納容器ドライウェル、12・・・原子炉格納容器圧
力抑制室、13・・・原子炉格納容器底部マット、14
・・・配管サポート。               
          、−−一11、代理人 弁理士 
小川勝男□  1 も1図 豹2図 佑3図
Fig. 1 is a detailed view of the boiling water reactor containment vessel main steam relief safety valve exhaust pipe using the present invention, Fig. 2 is a longitudinal sectional view of the boiling water reactor containment vessel using the present invention, and Fig. 3 4 is a perspective view of the main steam relief valve exhaust pipe of a conventional boiling water reactor containment vessel, and FIG. 4 is a vertical sectional view of the conventional boiling water reactor containment vessel. 1...Exhaust pipe piping, 2...Reactor pressure vessel, 3...
・Main steam pipe, 4... Main steam relief safety valve, 5... Pressure suppression chamber pool water, 6... Sparger, 7... Sparger support, 8... Anchor bolt, 9... Bellows, 10... Diamond wall 11 floor, 11... Reactor containment vessel dry well, 12... Reactor containment vessel pressure suppression chamber, 13... Reactor containment vessel bottom mat, 14
...Piping support.
,--11, Agent Patent Attorney
Katsuo Ogawa □ 1 Mo1 figure Leopard 2 figure Yu 3 figure

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉格納容器主蒸気逃し安全弁排気管配管と水中
に設けられた主蒸気逃し安全弁スパージヤよりなる主蒸
気逃し安全弁排気管において、排気管配管と安全弁スパ
ージヤとの接続を管の重ね合わせによるはめ合い構造と
したことを特徴とする原子炉格納容器主蒸気逃がし安全
弁排気管の接続構造。
1. In the main steam relief safety valve exhaust pipe, which consists of the reactor containment vessel main steam safety valve exhaust pipe piping and the main steam relief safety valve spargeer installed underwater, the connection between the exhaust pipe piping and the safety valve spargeer is made by overlapping the pipes. A connection structure for a reactor containment vessel main steam relief safety valve exhaust pipe, characterized by having a mating structure.
JP60271535A 1985-12-04 1985-12-04 Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container Pending JPS62132199A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60271535A JPS62132199A (en) 1985-12-04 1985-12-04 Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60271535A JPS62132199A (en) 1985-12-04 1985-12-04 Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container

Publications (1)

Publication Number Publication Date
JPS62132199A true JPS62132199A (en) 1987-06-15

Family

ID=17501417

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60271535A Pending JPS62132199A (en) 1985-12-04 1985-12-04 Connecting structure of exhaust pipe for main-steam relief safety valve of nuclear reactor container

Country Status (1)

Country Link
JP (1) JPS62132199A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02503222A (en) * 1988-02-22 1990-10-04 ヤツギ,クロード Fittings for fluid conduits

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02503222A (en) * 1988-02-22 1990-10-04 ヤツギ,クロード Fittings for fluid conduits

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