JPH02222872A - Cooling arrangement of reactor container - Google Patents

Cooling arrangement of reactor container

Info

Publication number
JPH02222872A
JPH02222872A JP1039304A JP3930489A JPH02222872A JP H02222872 A JPH02222872 A JP H02222872A JP 1039304 A JP1039304 A JP 1039304A JP 3930489 A JP3930489 A JP 3930489A JP H02222872 A JPH02222872 A JP H02222872A
Authority
JP
Japan
Prior art keywords
reactor
vessel
containment vessel
header
pedestal
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
JP1039304A
Other languages
Japanese (ja)
Inventor
Makoto Akinaga
秋永 誠
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 JP1039304A priority Critical patent/JPH02222872A/en
Publication of JPH02222872A publication Critical patent/JPH02222872A/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 maintain the soundness of a reactor container and to improve the safety thereof by disposing a water injection header between a reactor pressure vessel and a shielding wall and also by providing an opening for introducing cooling water into a pedestal region. CONSTITUTION:A container water injection header 10 connected to a branch pipe 11 from a dry well spray header 8 is disposed in a gap part between a reactor pressure vessel 2 and a reactor shielding wall 9, and further an opening 12 for introducing cooling water from the header 10 into the region of a pedestal 4 is provided in a support part of the vessel 2. In the case when an accident wherein a core is damaged and melted and the vessel 2 is broken down takes place, a spray cooling system is started and cooling water is injected from the header 8 into a dry well 3, while the cooling water from the header 10 is injected into the gap part between the vessel 2 and the wall 9 and flows into the region of the pedestal 4 through the opening 12. Accordingly, the core is cooled down directly and effectively, while erosion of concrete of the pedestal 4 is prevented, and thus the soundness of the vessel 2 can be maintained.

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、原子炉格納容器の冷却装置に係わり、特に沸
騰水型原子炉に適用するのに好適な原子炉格納容器冷却
装置に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a cooling device for a nuclear reactor containment vessel, and in particular, a reactor containment vessel suitable for application to a boiling water reactor. Regarding a cooling device.

(従来の技術) 一般に原子炉では、安全のために炉心は原子炉圧力容器
内に収容され、原子炉圧力容器は原子炉格納容器内に格
納されている。
(Prior Art) Generally, in a nuclear reactor, a reactor core is housed in a reactor pressure vessel for safety, and the reactor pressure vessel is housed in a reactor containment vessel.

第2図は従来の沸騰水形原子炉の原子炉格納容器の一例
を示すもので、原子炉格納容器1内には、炉心(図示せ
ず)を収納する原子炉圧力容器2が格納されるドライウ
ェル3と、原子炉圧力容器2を支持するペデスタル4と
、ペデスタル4の周囲を囲み冷却水を貯蔵する圧力抑制
室5が配設されており、ドライウェル3と圧力抑制室5
とは圧力抑制室5の水中まで伸びたベント管6によって
連通されている。このように構成された原子炉格納容器
において、万一原子炉格納容器内の配管が破断するよう
な冷却材喪失事故が発生した場合、原子炉圧力容器内か
ら放出された蒸気と水の混合物は、ベント管6を通して
圧力抑制室5に導かれ、蒸気が凝縮されることによって
格納容器内圧の上昇が抑制され、放散された放射性物質
は格納容器1内に保留される。さらに、ドライウェル3
の上部には圧力抑制室5内の冷却水をポンプ7によって
ドライウェル3内に注水するドライウェルスプレィヘッ
ダー8が設置されており、冷却材喪失事故時の格納容器
内の温度、圧力を低減することにより格納容器1の健全
性を保ち、格納容器1内に浮遊する放射性物質が格納容
器1外へ漏洩するのを押えるような格納容器スプレィ冷
却系が備えられている。また、上記のような冷却材喪失
事故が発生した場合に原子炉圧力容器2内に収納された
炉心の健全性を保つため、圧力抑制室5内の冷却水を原
子炉へ注水する非常用炉心冷却系(図示せず)が多重に
設置されている。
FIG. 2 shows an example of a reactor containment vessel of a conventional boiling water reactor. Inside the reactor containment vessel 1, a reactor pressure vessel 2 containing a reactor core (not shown) is housed. A dry well 3, a pedestal 4 that supports the reactor pressure vessel 2, and a pressure suppression chamber 5 that surrounds the pedestal 4 and stores cooling water are provided.
The vent pipe 6 is connected to the pressure suppression chamber 5 by a vent pipe 6 extending into the water. In a reactor containment vessel configured in this way, in the event that a loss of coolant accident occurs in which the piping inside the reactor containment vessel ruptures, the mixture of steam and water released from inside the reactor pressure vessel will The steam is guided to the pressure suppression chamber 5 through the vent pipe 6 and condensed, thereby suppressing the increase in the internal pressure of the containment vessel, and the released radioactive substances are retained within the containment vessel 1. In addition, Drywell 3
A dry well spray header 8 is installed above the pressure suppression chamber 5 to inject cooling water from the pressure suppression chamber 5 into the dry well 3 using a pump 7, reducing the temperature and pressure inside the containment vessel in the event of a loss of coolant accident. A containment vessel spray cooling system is provided that maintains the integrity of the containment vessel 1 and prevents radioactive substances floating within the containment vessel 1 from leaking out of the containment vessel 1. In addition, in order to maintain the integrity of the core housed in the reactor pressure vessel 2 in the event of a loss of coolant accident as described above, an emergency core is installed to inject cooling water in the pressure suppression chamber 5 into the reactor. Multiple cooling systems (not shown) are installed.

(発明が解決しようとする課題) 以上のように構成された原子カプラントにおいて、万一
冷却材喪失事故が発生し、非常用炉心冷却系の多重故障
によって炉心の冷却が長時間にわたって不十分となる場
合には、炉心が損傷・溶融し、溶融した炉心が原子炉圧
力容器の底部を溶融・貫通し、原子炉圧力容器下部のペ
デスタル領域に流出する恐れがある。また、このような
事故においては上述したように格納容器内の温度、圧力
を低減するため格納容器スプレィ冷却系が起動されるが
、ドライウェルヘスプレイされた冷却水の大部分はベン
ト管を経て圧力抑制室へ流入するため、ペデスタル領域
に流出した溶融炉心が十分に冷却されない恐れがある。
(Problem to be Solved by the Invention) In the case that a loss of coolant accident occurs in the nuclear couplant configured as described above, core cooling will become insufficient for a long period of time due to multiple failures in the emergency core cooling system. In such a case, the core may be damaged and melted, and the molten core may melt and penetrate the bottom of the reactor pressure vessel and flow into the pedestal area at the bottom of the reactor pressure vessel. In addition, in such an accident, as mentioned above, the containment vessel spray cooling system is activated to reduce the temperature and pressure inside the containment vessel, but most of the cooling water sprayed into the dry well passes through the vent pipe. Because the melt flows into the pressure suppression chamber, there is a risk that the molten core that has flowed into the pedestal area may not be sufficiently cooled.

この場合、高温の溶融炉心はペデスタルのコンクリート
を浸食するため、格納容器の健全性が維持できなくなる
恐れがある。
In this case, the high-temperature molten core would erode the concrete of the pedestal, which could make it impossible to maintain the integrity of the containment vessel.

その結果、格納容器の気密性が確保できなくなり、放射
性物質の環境への放出が生じる場合がある。
As a result, the airtightness of the containment vessel cannot be ensured, and radioactive materials may be released into the environment.

このように炉心溶融により格納容器の健全性が脅かされ
るようになる事故は設計基準事故を越えるものであり、
その発生確率は極めて小さいが、万一発生した場合には
環境に多大の被害を及ぼす結果となる。
Accidents such as this, in which the integrity of the containment vessel is threatened by core meltdown, exceed design basis accidents;
Although the probability of its occurrence is extremely small, if it were to occur it would result in great damage to the environment.

本発明は上記事情に鑑みてなさ゛れたもので、その目的
は炉心が溶融し、原子炉圧力容器が破損するような原子
炉の苛酷事故において、格納容器に流出した溶融炉心を
冷却する原子炉格納容器冷却装置を提供することにある
The present invention has been developed in view of the above-mentioned circumstances, and its purpose is to provide a nuclear reactor that cools the molten core that has leaked into the containment vessel in the event of a severe nuclear reactor accident in which the core melts and the reactor pressure vessel is damaged. An object of the present invention is to provide a containment vessel cooling device.

(課題を解決するための手段) 本発明は上記目的を達成するために、原子炉を収納した
原子炉圧力容器を格納する原子炉格納容器と前記格納容
器の圧力抑制室の冷却水を当該格納容器のドライウェル
上部に設定されたドライウェルスプレィヘッダーに供給
するように構成された原子炉格納容器冷却装置において
、前記ドライウェルスプレィヘッダーからの分岐管によ
って接続され、前記原子炉圧力容器と当該原子炉圧力容
器の周囲を囲む原子炉遮蔽壁との間隙部に格納容器注水
ヘッダーを配置し、さらに前記原子炉圧力容器の支持部
に前記注水ヘッダーからの冷却水を前記原子炉圧力容器
を支持するペデスタルによって■まれた空間部に導入す
る開口部を備えたことを特徴とするものである。
(Means for Solving the Problems) In order to achieve the above object, the present invention provides a reactor containment vessel that stores a reactor pressure vessel housing a nuclear reactor, and cooling water in a pressure suppression chamber of the containment vessel. In a reactor containment vessel cooling system configured to supply a dry well spray header set at the top of a dry well of a vessel, the reactor pressure vessel is connected by a branch pipe from the dry well spray header to the reactor pressure vessel and the atom. A containment vessel water injection header is disposed in a gap between a reactor shielding wall surrounding the reactor pressure vessel, and the cooling water from the water injection header is supplied to a supporting portion of the reactor pressure vessel to support the reactor pressure vessel. It is characterized by having an opening for introducing the space into the space defined by the pedestal.

(作 用) 本発明の原子炉格納容器冷却装置によれば、万一冷却喪
失事故のような原子カプラントの設計基準事故を越え、
炉心が損傷・溶融し圧力容器が破損するような苛酷事故
が発生した場合に、原子炉圧力容器下部のペデスタル領
域に落下した溶融炉心を冷却するため、ドライウェル上
部に設置されるドライウェルスプレイヘッダーからの分
岐管によって接続され、前記原子炉圧力容器と原子炉圧
力容器の周囲を囲む原子炉遮蔽壁との間隙部に配置され
た格納容器注水ヘッダーからの冷却水を前記原子炉容器
を支持するペデスタルによって囲まれた空間部に導入す
る開口部を通して、ペデスタル領域に流入されるので、
溶融炉心は効果的に冷却され、格納容器の健全性が保た
れる。
(Function) According to the reactor containment vessel cooling system of the present invention, in the event that a nuclear couplant design basis accident such as a loss of cooling accident is overcome,
A dry well spray header installed above the dry well to cool the molten core that has fallen into the pedestal area at the bottom of the reactor pressure vessel in the event of a severe accident in which the reactor core is damaged or melted and the pressure vessel is damaged. The reactor vessel is supported by cooling water from a containment vessel water injection header connected to the reactor vessel by a branch pipe from the reactor vessel and disposed in a gap between the reactor pressure vessel and a reactor shielding wall surrounding the reactor pressure vessel. It flows into the pedestal area through the opening that introduces it into the space surrounded by the pedestal.
The molten core is effectively cooled and the integrity of the containment vessel is maintained.

(実施例) 本発明の一実施例を図面について説明する。(Example) An embodiment of the present invention will be described with reference to the drawings.

第1図は本発明の一実施例の概略構成図である。FIG. 1 is a schematic diagram of an embodiment of the present invention.

なお、既に説明した第2図の従来例と同一部分には同一
符号を付して説明する。
Note that the same parts as those of the conventional example shown in FIG. 2, which have already been explained, will be described with the same reference numerals.

図において原子炉格納容器1内には、炉心(図示せず)
を収納する原子炉圧力容器2が格納されるドライウェル
3と、原子炉圧力容器2を支持するペデスタル4と、ペ
デスタル4の周囲を囲み冷却水を貯蔵する圧力抑制室5
が配設されており、ドライウェル3と圧力抑制室5とは
圧力抑制室5の水中まで伸びたベント管6によって連通
されている。ドライウェル3の上部には圧力抑制室5内
の冷却水をポンプ7によってドライウェル3内に注水す
るドライウェルスプレィヘッダー・8が設置されており
、冷却材喪失事故時の格納容器内の温度、圧力を低減す
ることにより格納容器1の健全性を保ち、格納容器1内
に浮遊する放射性物質が格納容器1外へ漏洩するのを押
えるような格納容器スプレィ冷却系が備えられている。
In the figure, inside the reactor containment vessel 1 is a reactor core (not shown).
A dry well 3 in which the reactor pressure vessel 2 is stored, a pedestal 4 that supports the reactor pressure vessel 2, and a pressure suppression chamber 5 that surrounds the pedestal 4 and stores cooling water.
The dry well 3 and the pressure suppression chamber 5 are communicated with each other by a vent pipe 6 extending into the water of the pressure suppression chamber 5. A dry well spray header 8 is installed at the top of the dry well 3 to inject cooling water from the pressure suppression chamber 5 into the dry well 3 using a pump 7. A containment vessel spray cooling system is provided that maintains the integrity of the containment vessel 1 by reducing the pressure and prevents radioactive materials floating within the containment vessel 1 from leaking out of the containment vessel 1.

また、圧力抑制室5内の冷却水を原子炉へ注水する非常
用炉心冷却系(図示せず)が多重に設置されている。
In addition, multiple emergency core cooling systems (not shown) are installed for injecting cooling water in the pressure suppression chamber 5 into the reactor.

さらに、原子炉圧力容器2と原子炉圧力容器の周囲を囲
む原子炉遮蔽壁9との間隙部に格納容器注水ヘッダー1
0が設置され、注水ヘッダー10は原子炉を格納するド
ライウェルの上部に設置されるドライウェルスプレィヘ
ッダー8からの分岐管11によって接続されている。ま
た、原子炉圧力容器2の支持部には、格納容器注水ヘッ
ダー10からの冷却水をペデスタル4によって囲まれた
原子炉圧力容器下部の空間部に導入する開口部12が設
けられている。
Furthermore, a containment vessel water injection header 1 is installed in the gap between the reactor pressure vessel 2 and the reactor shielding wall 9 surrounding the reactor pressure vessel.
0 is installed, and the water injection header 10 is connected by a branch pipe 11 from a dry well spray header 8 installed above the dry well housing the nuclear reactor. Further, the support portion of the reactor pressure vessel 2 is provided with an opening 12 through which cooling water from the containment vessel water injection header 10 is introduced into a space below the reactor pressure vessel surrounded by the pedestal 4.

このように構成された格納容器冷却装置を有する原子カ
プラントにおいて、万一非常用炉心冷却系の多重故障に
より炉心冷却が長時間にわたって不十分となる事故が発
生し、炉心が損傷・溶融し、原子炉圧力容器2の底部が
溶融貫通し、原子炉圧力容器下部のペデスタル領域に流
出するような苛酷事故が発生した場合には、格納容器1
内の温度、圧力を低減するため格納容器スプレィ冷却系
が起動され、ドライウェルスプレィヘッダー8からドラ
イウェル3への冷却水の注水が行われるとともに、格納
容器注水ヘッダー10からの冷却水が、原子炉圧力容器
2と原子炉圧力容器の周囲を囲む原子炉遮蔽壁9との間
隙部へ注水され、原子炉容器の支持部に設けられた開口
部12を経てペデスタル領域に流入する。従って、ペデ
スタル領域に流出した炉心は冷却水によって直接効果的
に冷却され、ペデスタルのコンクリート侵食が防止され
、格納容器の健全性を保つことができ、原子炉格納容器
が破損し、放射性物質が直接環境へ放出されるという事
態に至ることなく事故を終結させることができる。
In a nuclear couplant with a containment vessel cooling system configured in this way, in the unlikely event that an accident occurs in which core cooling becomes insufficient for a long period of time due to multiple failures in the emergency core cooling system, the core may be damaged or melted, and the nuclear In the event of a severe accident in which the bottom of the reactor pressure vessel 2 melts and penetrates and leaks into the pedestal area at the bottom of the reactor pressure vessel, the containment vessel 1
In order to reduce the temperature and pressure inside the containment vessel, the containment vessel spray cooling system is activated, cooling water is injected from the dry well spray header 8 to the dry well 3, and cooling water from the containment vessel water injection header 10 is Water is injected into the gap between the reactor pressure vessel 2 and the reactor shielding wall 9 surrounding the reactor pressure vessel, and flows into the pedestal area through an opening 12 provided in the support of the reactor vessel. Therefore, the reactor core spilled into the pedestal area is directly and effectively cooled by the cooling water, preventing concrete erosion of the pedestal and maintaining the integrity of the containment vessel. Accidents can be brought to a close without resulting in release into the environment.

〔発明の効果〕〔Effect of the invention〕

以上述べたように、本発明の原子炉格納容器冷却装置に
よれば、炉心溶融後圧力容器破損に至るような苛酷事故
に対して、原子炉格納容器の健全性を保つことができ、
原子炉の安全性を向上させることができる。
As described above, according to the reactor containment cooling system of the present invention, the integrity of the reactor containment vessel can be maintained against severe accidents that lead to pressure vessel failure after core meltdown.
The safety of nuclear reactors can be improved.

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

第1図は本発明の一実施例の概略構成図、第2図は従来
の原子炉格納容器冷却装置の概略構成図である。 1・・・原子炉格納容器  2・・・原子炉圧力容器3
・・・ドライウェル   4・・・ペデスタル5・・・
圧力抑制室    6・・・ベント管7・・・ポンプ 8・・・ドライウェルスプレィヘッダー9・・・原子炉
遮蔽壁 lO・・・格納容器注水ヘッダー 11・・・分岐管     12・・・開口部(873
3)  代理人 弁理士 猪 股 祥 晃(ほか1名)
FIG. 1 is a schematic configuration diagram of an embodiment of the present invention, and FIG. 2 is a schematic configuration diagram of a conventional reactor containment vessel cooling system. 1... Reactor containment vessel 2... Reactor pressure vessel 3
...Drywell 4...Pedestal 5...
Pressure suppression chamber 6... Vent pipe 7... Pump 8... Dry well spray header 9... Reactor shielding wall lO... Containment vessel water injection header 11... Branch pipe 12... Opening (873
3) Agent: Yoshiaki Inomata, patent attorney (and one other person)

Claims (1)

【特許請求の範囲】[Claims] (1)原子炉を収納した原子炉圧力容器を格納する原子
炉格納容器と前記格納容器の圧力抑制室の冷却水を当該
格納容器のドライウェル上部に設定されたドライウェル
スプレイヘッダーに供給するように構成された原子炉格
納容器冷却装置において、前記ドライウェルスプレイヘ
ッダーからの分岐管によって接続され、前記原子炉圧力
容器と当該原子炉圧力容器の周囲を囲む原子炉遮蔽壁と
の間隙部に格納容器注水ヘッダーを配置し、さらに前記
原子炉圧力容器の支持部に前記注水ヘッダーからの冷却
水を前記原子炉圧力容器を支持するペデスタルによって
囲まれた空間部に導入する開口部を備えたことを特徴と
する原子炉格納容器冷却装置。
(1) Supply cooling water from the reactor containment vessel that houses the reactor pressure vessel housing the reactor and the pressure suppression chamber of the containment vessel to the dry well spray header set at the top of the dry well of the containment vessel. In the reactor containment vessel cooling system configured as above, the reactor containment vessel cooling system is connected by a branch pipe from the dry well spray header and is stored in a gap between the reactor pressure vessel and a reactor shielding wall surrounding the reactor pressure vessel. A vessel water injection header is disposed, and an opening is further provided in the support portion of the reactor pressure vessel for introducing cooling water from the water injection header into a space surrounded by a pedestal supporting the reactor pressure vessel. Features: Reactor containment vessel cooling system.
JP1039304A 1989-02-21 1989-02-21 Cooling arrangement of reactor container Pending JPH02222872A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1039304A JPH02222872A (en) 1989-02-21 1989-02-21 Cooling arrangement of reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1039304A JPH02222872A (en) 1989-02-21 1989-02-21 Cooling arrangement of reactor container

Publications (1)

Publication Number Publication Date
JPH02222872A true JPH02222872A (en) 1990-09-05

Family

ID=12549380

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1039304A Pending JPH02222872A (en) 1989-02-21 1989-02-21 Cooling arrangement of reactor container

Country Status (1)

Country Link
JP (1) JPH02222872A (en)

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