JPH04351996A - Reactor container - Google Patents

Reactor container

Info

Publication number
JPH04351996A
JPH04351996A JP3127126A JP12712691A JPH04351996A JP H04351996 A JPH04351996 A JP H04351996A JP 3127126 A JP3127126 A JP 3127126A JP 12712691 A JP12712691 A JP 12712691A JP H04351996 A JPH04351996 A JP H04351996A
Authority
JP
Japan
Prior art keywords
water
container
dry well
cooling water
reactor
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
JP3127126A
Other languages
Japanese (ja)
Inventor
Sadahiko Takigawa
定彦 瀧川
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
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 Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP3127126A priority Critical patent/JPH04351996A/en
Publication of JPH04351996A publication Critical patent/JPH04351996A/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To lower the volume of water source for emergency to lower the load of a container at the time of an earthquake and improve the stability of a plant building by installing a flow preventing means for cooling water which flows at the time of an accident in a vent pipe. CONSTITUTION:In the case that a pipeline 6 is ruptured and water pours itself into a pressure container 3 by a water pouring system 10 from a water source 11 for emergency, since the upper end part of a vent pipe 9 is extruded from a diaphragm floor 15, the cooling water 14 overflowing out of the ruptured part of the pipeline 6 does not flow in the pressure suppressing chamber 8. Consequently, it is not necessary to store water in the amount equivalent to the cooling water 13 of the chamber 8 in the water source 11 and thus the volume of the water source 11 can be lessened. a nuclear reactor container-lower part dry well communicating pipeline 16 which is communicated with a lower part dry well 5 and has a valve 8 is installed in the container 3. As a result, the cooling water 12 flowing in and stored in the dry well 5 flows to the container 3 through the valve 8 opened by an accident signal and the pipeline 16 and the water levels of the container 3 and the dry well 5 are balanced and the nuclear core 2 is submerged.

Description

【発明の詳細な説明】[Detailed description of the invention]

[発明の目的] [Purpose of the invention]

【0001】0001

【産業上の利用分野】本発明は原子炉格納容器、特に別
置きの非常用水源を有する非常用注水系を具えた原子炉
格納容器に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor containment vessel, and more particularly to a nuclear reactor containment vessel equipped with an emergency water injection system having a separate emergency water source.

【0002】0002

【従来の技術】図4は沸騰水型原子炉の概略構成を示す
模式的縦断面図である。この図において、原子炉格納容
器(以下PCVと呼ぶ)1内には炉心2を収容した原子
炉圧力容器(以下RPVと呼ぶ)3が配置されている。 PCV1は上部ドライウェル(以下U/ Dと呼ぶ)4
と下部ドライウェル(以下L/ Dと呼ぶ)5とを具え
、これ等のドライウェル内でRPV3に接続する配管6
が破断した場合に、PCV1内の圧力を低減させる圧力
抑制室(以下S/ Pと呼ぶ)8を有する。このS/ 
P8は冷却水7を貯蔵し、気相域をベント管9によって
ドライウェル内と連通されている。
2. Description of the Related Art FIG. 4 is a schematic longitudinal cross-sectional view showing the general structure of a boiling water nuclear reactor. In this figure, a reactor pressure vessel (hereinafter referred to as RPV) 3 containing a reactor core 2 is arranged within a reactor containment vessel (hereinafter referred to as PCV) 1. PCV1 is the upper dry well (hereinafter referred to as U/D) 4
and a lower dry well (hereinafter referred to as L/D) 5, and piping 6 connected to the RPV 3 within these dry wells.
It has a pressure suppression chamber (hereinafter referred to as S/P) 8 that reduces the pressure inside the PCV 1 when the PCV 1 ruptures. This S/
P8 stores cooling water 7, and communicates the gas phase region with the inside of the dry well through a vent pipe 9.

【0003】また、前記ドライウェル内でRPV3に接
続した配管6の破断事故時には、RPV3から炉心2の
冷却材が溢水し、そのままにしておけば炉心2が過熱す
ることとなる。この過熱を防止するため、PCV1には
RPV3内に冷却用の多量の水を注入する注水系10お
よびその非常用水源11が設けられている。
[0003] Furthermore, in the event of a rupture accident in the pipe 6 connected to the RPV 3 in the dry well, the coolant for the core 2 will overflow from the RPV 3, and if left as it is, the core 2 will overheat. In order to prevent this overheating, the PCV 1 is provided with a water injection system 10 for injecting a large amount of cooling water into the RPV 3 and an emergency water source 11 thereof.

【0004】上記構成の沸騰水型原子炉において、配管
6の破断が生じて非常用の注水系10からRPV3に注
水がなされた場合、冷却水の一部は図示14のように配
管6の破断箇所からPCV1内に流出し、ダイヤフラム
フアロア(以下D/ Fと呼ぶ)15上部を経由してL
/ D5に流入し、ここに貯溜される(図中冷却水12
として示す)。また、ベント管9の開口からベント管9
内に入りS/ P8へも流入する(図中冷却水13とし
て示す)。
In the boiling water reactor having the above configuration, when the pipe 6 breaks and water is injected from the emergency water injection system 10 into the RPV 3, a portion of the cooling water is absorbed into the pipe 6 as shown in FIG. 14. It flows out into PCV1 from the point and flows through the upper part of diaphragm lower (hereinafter referred to as D/F) 15 to L.
/ Flows into D5 and is stored here (cooling water 12 in the figure)
). Also, from the opening of the vent pipe 9 to the vent pipe 9
It also flows into the S/P8 (shown as cooling water 13 in the figure).

【0005】また、事故後長期にわたって炉心2の崩壊
熱除去のため炉心2を冠水させなければならないが、非
常用水源11はRPV3内に注入し炉心2を冠水させる
に必要な水量のみでなく、L/ D5内およびS/ P
8内に流入貯溜される冷却水12、13を賄えるだけの
大量の水を蓄え得るものとしなければならない。
[0005] Furthermore, the reactor core 2 must be submerged in water for a long period of time after the accident to remove decay heat from the reactor core 2, but the emergency water source 11 not only has the amount of water necessary to inject into the RPV 3 and submerge the reactor core 2, but also Inside L/D5 and S/P
It must be possible to store a large amount of water to cover the cooling water 12, 13 flowing into and stored in the cooling water tank 8.

【0006】[0006]

【発明が解決しようとする課題】上記のように従来の沸
騰水型原子炉においては、非常用の注水系10の非常用
水源11はRPV3内に注入され炉心2内に注入される
水のみでなく、L/ D5、S/ P8内に流入貯溜さ
れ炉心2の冷却、冠水に全く関与しない水まで蓄える大
容量のものとする必要があった。このように大容量の非
常用水源11をPCV1に設けることは、単にPCV1
の設計上の制限となるだけでなく、PCV1のトップヘ
ビイ状態を招きPCV1の脚部に大きな地震負担をおよ
ぼし、地震時のプラント建屋の安定性をも損ねるおそれ
があった。
[Problems to be Solved by the Invention] As mentioned above, in the conventional boiling water reactor, the emergency water source 11 of the emergency water injection system 10 is only the water that is injected into the RPV 3 and into the reactor core 2. It was necessary to have a large capacity to store water that flows into L/D5 and S/P8 and is not involved in cooling the reactor core 2 or flooding. Providing the large-capacity emergency water source 11 in the PCV1 in this way simply means that the PCV1
Not only would this be a design limitation, but it would also lead to a top-heavy state of PCV1, which would place a large earthquake load on the legs of PCV1, and could potentially impair the stability of the plant building during an earthquake.

【0007】本発明は上記の事情に基づきなされたもの
で、事故時に炉心の冷却、冠水のためRPVに注入され
た冷却水のS/ Pへの流入を抑止し、非常用水源の容
量を削減することができるPCVを提供することを目的
としている。 [発明の構成]
[0007] The present invention was made based on the above circumstances, and suppresses the flow of cooling water injected into the RPV into the S/P for cooling the reactor core and flooding during an accident, thereby reducing the capacity of the emergency water source. The purpose is to provide a PCV that can [Structure of the invention]

【0008】[0008]

【課題を解決するための手段】本発明の原子炉格納容器
は、上部ドライウェルと、下部ドライウェルと、前記上
部ドライウェルの気相域にベント管を介して連通する圧
力抑制室と、別置きの非常用水源を具え、炉心を収容し
た原子炉圧力容器を包囲するものにおいて、前記ベント
管には事故時に前記原子炉圧力容器から前記上部ドライ
ウェルに流出した冷却水の流入を防止する手段を設けた
ことを特徴とする。
[Means for Solving the Problems] The reactor containment vessel of the present invention includes an upper dry well, a lower dry well, and a pressure suppression chamber that communicates with the gas phase region of the upper dry well via a vent pipe, and separate In the reactor pressure vessel containing the reactor core, which is equipped with a standalone emergency water source, and which surrounds the reactor pressure vessel housing the reactor core, means for preventing cooling water that has flowed from the reactor pressure vessel into the upper dry well in the event of an accident from flowing into the vent pipe. It is characterized by having the following.

【0009】[0009]

【作用】上記構成の本発明の原子炉格納容器においては
、ベント管の上端には冷却水の流入を防止する手段が設
けられているため、配管の破断箇所から溢流した冷却水
は圧力抑制室内に流れ込むことはなく、前記別置きの非
常用水源に従来のように圧力抑制室内に流入、貯溜され
る水量を蓄えておく必要はなく、非常用水源の容量を削
減することができる。これにより、従来の大容量の非常
用水源によって生じる諸問題を解決することができる。
[Function] In the reactor containment vessel of the present invention having the above configuration, the upper end of the vent pipe is provided with a means for preventing the inflow of cooling water, so that the pressure of the cooling water overflowing from the broken part of the pipe is suppressed. It does not flow into the room, and there is no need to store the amount of water that flows into and is stored in the pressure suppression chamber in the separate emergency water source as in the conventional case, and the capacity of the emergency water source can be reduced. This solves the problems caused by conventional large capacity emergency water sources.

【0010】0010

【実施例】図4と同一部分には同一符号を付した図1は
、本発明の第1の実施例の要部の模式的縦断面図である
。この図において、ベント管9の上端部がS/P8の上
面壁すなわちD/F15から突出されている。また、R
PV3には前記L/ D5内と連通史L/ D5内の端
部に弁18を有するRPV−L/ D連通配管16が設
けられている。
DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1, in which the same parts as in FIG. 4 are denoted by the same reference numerals, is a schematic longitudinal cross-sectional view of a main part of a first embodiment of the present invention. In this figure, the upper end of the vent pipe 9 protrudes from the upper wall of the S/P 8, that is, the D/F 15. Also, R
The PV3 is provided with an RPV-L/D communication pipe 16 having a valve 18 at an end between the L/D5 and the communication history L/D5.

【0011】上記のようにベント管9の上端がD/F1
5上面から突出しているため、配管6の破断箇所から溢
流した冷却水14はS/ P8内に流れ込むことはなく
、非常用水源11に図4におけるS/ P8内の冷却水
13に相当する水量を蓄えておく必要はなく、非常用水
源11の容量を削減することができる。
As mentioned above, the upper end of the vent pipe 9 is connected to the D/F1
5 protrudes from the top surface, so the cooling water 14 overflowing from the broken part of the pipe 6 does not flow into the S/P8, and instead is sent to the emergency water source 11, which corresponds to the cooling water 13 in the S/P8 in Fig. 4. There is no need to store water, and the capacity of the emergency water source 11 can be reduced.

【0012】これにより、従来の大容量の非常用水源1
1によって生じる諸問題を解決することができる。また
、L/ D5内に流入、貯溜された冷却水12は、事故
信号により開放された弁18、RPV−L/ D連通配
管16を介してRPV6内に流入して、RPV3内とL
/ D5内の水位を均衡させ炉心2の冠水に寄与する。
[0012] As a result, the conventional large-capacity emergency water source 1
The various problems caused by 1 can be solved. In addition, the cooling water 12 that has flowed into and stored in the L/D5 flows into the RPV6 via the valve 18 opened by the accident signal and the RPV-L/D communication pipe 16, and is connected to the RPV3 and the L/D5.
/ Balances the water level in D5 and contributes to flooding of core 2.

【0013】図1、図4と同一部分には同一符号を付し
た図2は、本発明の第2の実施例の要部の模式的縦断面
図である。この図において、ベント管9はS/P8の側
面壁に開口されている。このため、D/F15上面に流
下した冷却水14はベント管9内に流入することはなく
、上記第1の実施例と同様の効果が得られる。
FIG. 2, in which the same parts as in FIGS. 1 and 4 are denoted by the same reference numerals, is a schematic vertical sectional view of the main part of a second embodiment of the present invention. In this figure, the vent pipe 9 is opened in the side wall of the S/P 8. Therefore, the cooling water 14 that has flowed down onto the upper surface of the D/F 15 does not flow into the vent pipe 9, and the same effect as in the first embodiment can be obtained.

【0014】前記各図と同一部分には同一符号を付した
図3は、本発明の第3の実施例の要部の模式的縦断面図
である。この図において、ベント管9は図4に示した従
来のベント管と同様にD/F15に開口され、その開口
周囲には円筒状の堰17が設けられている。上記堰17
はD/F15に流下した冷却水のベント管9への流入を
防止するので、この実施例においても前記実施例と同様
の効果が得られる。
FIG. 3, in which the same parts as those in the previous figures are given the same reference numerals, is a schematic longitudinal sectional view of the main part of a third embodiment of the present invention. In this figure, the vent pipe 9 is opened to the D/F 15 similarly to the conventional vent pipe shown in FIG. 4, and a cylindrical weir 17 is provided around the opening. Weir 17 above
Since this prevents the cooling water that has flowed down to the D/F 15 from flowing into the vent pipe 9, the same effects as in the previous embodiment can be obtained in this embodiment as well.

【0015】なお、本発明は上記各実施例のみに限定さ
れない。例えば、RPV−L/ D連通配管16の設置
を省略してもよい。また、PCVの形状、構造も例示の
ものに限定されない。
It should be noted that the present invention is not limited to the above embodiments. For example, the installation of the RPV-L/D communication piping 16 may be omitted. Furthermore, the shape and structure of the PCV are not limited to those illustrated.

【0016】[0016]

【発明の効果】上記から明らかなように本発明の原子炉
格納容器においては、配管破断事故時に原子炉圧力容器
内に非常用冷却水が注入された場合において、配管破断
箇所から原子炉格納容器内に流出した冷却水は圧力抑制
室に流入することはないから、非常用水源は炉心の冷却
、冠水に寄与する分の水量のみを蓄えるだけの容量でよ
い。従って、非常用水源の重量を減じることができ原子
炉格納容器のトップヘビーの状態を生じることはないか
ら、地震時の原子炉格納容器脚部の過大な負荷を避ける
ことができる。また、原子力プラント建屋の安定性を向
上させることも可能である。
Effects of the Invention As is clear from the above, in the reactor containment vessel of the present invention, when emergency cooling water is injected into the reactor pressure vessel in the event of a pipe rupture accident, the reactor containment vessel Since the cooling water that flows into the reactor does not flow into the pressure suppression chamber, the emergency water source only needs to have a capacity that stores enough water to cool the core and contribute to flooding. Therefore, the weight of the emergency water source can be reduced and the top-heavy condition of the reactor containment vessel will not occur, so that excessive loads on the reactor containment vessel legs during an earthquake can be avoided. It is also possible to improve the stability of nuclear plant buildings.

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

【図1】本発明の第1の実施例の要部の模式的縦断面図
FIG. 1 is a schematic vertical cross-sectional view of the main parts of a first embodiment of the present invention.

【図2】本発明の第2の実施例の要部の模式的縦断面図
FIG. 2 is a schematic vertical cross-sectional view of the main parts of a second embodiment of the present invention.

【図3】本発明の第3の実施例の要部の模式的縦断面図
FIG. 3 is a schematic longitudinal cross-sectional view of the main parts of a third embodiment of the present invention.

【図4】沸騰水型原子炉の概略構成を示す模式的縦断面
図。
FIG. 4 is a schematic vertical cross-sectional view showing the schematic configuration of a boiling water reactor.

【符号の説明】[Explanation of symbols]

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】  上部ドライウェルと、下部ドライウェ
ルと、前記上部ドライウェルの気相域にベント管を介し
て連通する圧力抑制室と、別置きの非常用水源を具え、
炉心を収容した原子炉圧力容器を包囲するものにおいて
、前記ベント管には事故時に前記原子炉圧力容器から前
記上部ドライウェルに流出した冷却水の流入を防止する
手段を設けたことを特徴とする原子炉格納容器。
1. An upper dry well, a lower dry well, a pressure suppression chamber communicating with the gas phase region of the upper dry well via a vent pipe, and a separate emergency water source,
In the reactor pressure vessel surrounding the reactor core containing the reactor core, the vent pipe is provided with means for preventing cooling water flowing out from the reactor pressure vessel into the upper dry well in the event of an accident. Reactor containment vessel.
JP3127126A 1991-05-30 1991-05-30 Reactor container Pending JPH04351996A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3127126A JPH04351996A (en) 1991-05-30 1991-05-30 Reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3127126A JPH04351996A (en) 1991-05-30 1991-05-30 Reactor container

Publications (1)

Publication Number Publication Date
JPH04351996A true JPH04351996A (en) 1992-12-07

Family

ID=14952256

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3127126A Pending JPH04351996A (en) 1991-05-30 1991-05-30 Reactor container

Country Status (1)

Country Link
JP (1) JPH04351996A (en)

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