JPH03209193A - Vent device for nuclear reactor container - Google Patents

Vent device for nuclear reactor container

Info

Publication number
JPH03209193A
JPH03209193A JP2002479A JP247990A JPH03209193A JP H03209193 A JPH03209193 A JP H03209193A JP 2002479 A JP2002479 A JP 2002479A JP 247990 A JP247990 A JP 247990A JP H03209193 A JPH03209193 A JP H03209193A
Authority
JP
Japan
Prior art keywords
pipe
well
containment vessel
wet well
plant
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.)
Granted
Application number
JP2002479A
Other languages
Japanese (ja)
Other versions
JP2868819B2 (en
Inventor
Takashi Sato
崇 佐藤
Noriyoshi Okehara
桶原 準嘉
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 JP2002479A priority Critical patent/JP2868819B2/en
Publication of JPH03209193A publication Critical patent/JPH03209193A/en
Application granted granted Critical
Publication of JP2868819B2 publication Critical patent/JP2868819B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related 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 prevent environmental pollution due to fission products (FP) accumulated in a nuclear reactor by leading the gaseous atmosphere in the container of a plant, where an accident occurs, into pressure control water of a wet well. CONSTITUTION:After a serious accident occurs, blind flanges 27 and 127 are detached and a building connection pipe 28 is connected, and a wet well isolating valve, air operating valves 25 and 26, and air operating valves 124 and 125 of an adjacent plant are successively opened. The gaseous atmosphere in a dry well 4 of a nuclear reactor container 2 rises in pressure control water 6 of a wet well 5 through a vent tube 7 and has FP removed in a certain degree, and thereafter, it is led to the adjacent plant through pipes 11, 14, and 28 and is discharged into pressure control water 106 of a wet well 105 through a pipe 121. Thus, the gaseous atmosphere in the nuclear reactor container 2 of the plant where the accident occurs is discharged to the dry well 104 of the adjacent plant to prevent the damage of the container 2 due to an excessive pressure. The gaseous atmosphere is subjected to scrubbing by pressure control water 6 and 106 and FP pollution is very reduced.

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、原子炉発電所に用いられる原子炉格納容器ベ
ント装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor containment vessel venting device used in a nuclear power plant.

(従来の技術) 原子力発電所に用いられる原子炉格納容器は、事故発生
時に,轟内に蓄積された核分裂生成物(以下FPという
)を環境に放出することを防yすることを目的として設
置されている.このような原子炉格納容器を有する原子
力発電所に於いて、現実的には起りにくいことであるが
,異常な事象が発生し原子炉圧力容器内への冷却水の補
給手段が完全に喪失してしまう事故やあるいは原子炉格
納容器から除熱機能が完全に喪失してしまう事故(以下
苛酷事故という)を想定し,それでも原子力発電所の安
全性が喪失しないように対策を実施することが考えられ
ている. これまでの確率論的安全評価の知見から、苛酷事故の流
れは、大きく以下の2つの場合に分けて考えることがで
きる. その1つは、最初に原子炉圧力容器への冷却水の補給手
段が完全に喪失する場合であり、このときによってまず
炉心溶融が発生し、溶融炉心が原子炉圧力容器を溶融貫
通した後ドライウェル内に放出される.その後、溶融炉
心の崩壊熱によって原子炉格納容器内が加圧されるとと
もに、溶融炉?とドライウェル床面を構成するコンクリ
ートとの間に起るコア・コンクリート反応から発生する
Co,,H■等の非凝縮性ガスにより原子炉格納容器は
過圧破損に至り、FPが環境に大量放出されることにな
る. 他の1つは、最初に原子炉格納容器からの除熱機能が完
全に喪失することにより,格納容器の過圧破損がまず起
る場合である。このことによりウェットウェル中の圧力
抑制水が減圧沸膳を起すため、これを水源とする原子炉
圧力容器八の冷却水の補給手段が機能喪失に至り、炉心
溶融が発生する。その後溶融炉心は原子炉圧力容器を貫
通しドライウェルに放出されるが,既に格納容器は過圧
破損しているため、FPが環境に大量放出されることに
なる. 以上のいずれの場合に於いても、原子炉格納容器の過圧
破損を防止することが、FPの環境への大量放出を防止
する上で重要であるため、そのための方法が検討されて
いる。原子炉格納容器の過圧破損を防止するためには、
原子炉格納容器が破損限界圧力に到達する前に、原子炉
格納容器内でのFPの減衰効果や圧力抑制水等によるF
Pの除去効果により放出FP量を低減した後、原子炉格
納容器内雰囲気ガスを環境へ放出(以下格納容器ベント
という)し、原子炉格納容器内の圧力上昇を抑えること
が必要となる.具体的には、事故発生プラントの原子炉
格納容器と隣接プラントの原子炉格納容器とを接続する
ことにより、事故発生プラント側の原子炉格納容器の圧
力上昇を緩和し、FPを格納容器内に長時間に亘り閉じ
込めておくことにより希ガスを含めた全FPを減衰させ
るとともに,事故発生プラントと隣接プラントの圧力抑
制水によりFPを除去し環境へ放出されるFP量を低減
する格納容器ベント装置が考えられている. (発明が解決しようとする課題) 上述の格納容器ベント装置において隣接プラントとの接
続方法に関しては、様々な接続方法が考えられているが
、単一故障基準および格納容器の隔離機能要求等に忠実
に設計を実施すると,弁および配管の物量が多くなり、
現行のプラント設計に大きな影響を与えることになる.
また,隣接プラントヘベントするため、事故プラントか
らFPが放出された場合、隣接プラントに汚染が生じる
という問題もある.したがって、現行プラント設計への
影響を最小にし、かつ隣接プラントの汚染を極力防止す
る方向で装置の設計を実施する必要がある. そこで、本発明は複数基立地する原子力発電所における
格納容器ベント装置に関して、単純な構成で隣接プラン
トと接続し隣接プラントの汚染を極力抑えた格納容器ベ
ント装置を提供することを目的とする. 〔発明の構威〕 (課題を解決するための手段) 上記目的を達成するため、本発明に於いては既設の設備
を最大限に利用し、隣接プラントへのベント先をウエッ
トウエル圧力抑制水中とした。
(Prior art) Reactor containment vessels used in nuclear power plants are installed for the purpose of preventing fission products (hereinafter referred to as FP) accumulated in the reactor from being released into the environment in the event of an accident. It has been done. Although this is unlikely to happen in a nuclear power plant with such a reactor containment vessel, an abnormal event may occur and the means of supplying cooling water to the reactor pressure vessel may be completely lost. It is a good idea to take measures to ensure that the safety of nuclear power plants is not lost even in the event of an accident in which the nuclear power plant loses its safety, or an accident in which the heat removal function is completely lost from the reactor containment vessel (hereinafter referred to as a "severe accident"). It is being done. Based on the knowledge of probabilistic safety evaluation to date, the flow of severe accidents can be broadly divided into the following two cases. One of these is the case where the means of supplying cooling water to the reactor pressure vessel is completely lost. At this time, a core meltdown occurs first, and after the molten core penetrates the reactor pressure vessel, it becomes dry. released into the well. After that, the inside of the reactor containment vessel is pressurized by the decay heat of the molten core, and the melting reactor? The reactor containment vessel suffered overpressure failure due to non-condensable gases such as Co, H, etc. generated from the core-concrete reaction between the core concrete and the concrete that constitutes the drywell floor, and a large amount of FP was released into the environment. It will be released. The other case is when overpressure failure of the reactor containment vessel first occurs due to the complete loss of the heat removal function from the reactor containment vessel. This causes the pressure suppression water in the wet well to boil under reduced pressure, which causes the cooling water replenishment means for the reactor pressure vessel 8, which uses this water as a water source, to lose its function, resulting in core meltdown. The molten core then penetrates the reactor pressure vessel and is released into the dry well, but since the containment vessel has already been damaged by overpressure, a large amount of FP will be released into the environment. In any of the above cases, it is important to prevent overpressure damage to the reactor containment vessel in order to prevent a large amount of FP from being released into the environment, and methods for this purpose are being studied. In order to prevent overpressure damage to the reactor containment vessel,
Before the reactor containment vessel reaches its failure limit pressure, the FP damping effect in the reactor containment vessel and pressure suppression water etc.
After reducing the amount of released FP due to the P removal effect, it is necessary to release the atmospheric gas inside the reactor containment vessel to the environment (hereinafter referred to as containment vessel venting) to suppress the pressure rise inside the reactor containment vessel. Specifically, by connecting the reactor containment vessel of the plant where the accident occurred and the reactor containment vessel of the adjacent plant, the pressure increase in the reactor containment vessel of the plant where the accident occurred will be alleviated, and the FP will be placed inside the containment vessel. Containment vessel venting system that attenuates all FPs, including rare gases, by keeping them confined for a long period of time, and removes FPs with pressure suppression water from the plant where the accident occurred and adjacent plants, reducing the amount of FPs released into the environment. is being considered. (Problem to be Solved by the Invention) Various connection methods have been considered for connecting the above-mentioned containment vessel vent system with adjacent plants, but it is difficult to find a method that adheres to the single failure standard and isolation function requirements of the containment vessel. If the design is carried out, the amount of valves and piping will increase,
This will have a major impact on current plant design.
Furthermore, since FP is vented to adjacent plants, there is also the problem that if FP is released from the accident plant, the adjacent plants will be contaminated. Therefore, it is necessary to design the equipment in a way that minimizes the impact on the current plant design and prevents contamination of adjacent plants as much as possible. Therefore, an object of the present invention is to provide a containment vessel venting system for a nuclear power plant where multiple bases are located, which has a simple configuration, is connected to an adjacent plant, and minimizes contamination of the adjacent plant. [Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention makes maximum use of the existing equipment and connects the vent to the adjacent plant to a wet well pressure suppression underwater And so.

具体的には、第1図に示すように、ドライウェル4及び
ウェットウェル5に各々開口部を有する不活性ガス系ド
ライウェル,ウェットウェル側排気配管9,11と、こ
れらの配管9,1lに設置されている空気作動による原
子炉格納容器第一隔離弁10,l2と、この各々の排気
配管上の原子炉格納容器第一隔離弁の下流を接続する連
結配管14と,ウェットウェル側排気配管11の第一隔
離弁12及び第二隔離弁13間の配管と直接大気放出口
20とを接続する放出配管17と隣接プラントの放出配
管17上に設置される放出弁18及びラプチャーディス
ク19と、ウェットウェルの圧力抑制水中に開口部を有
し原子炉格納容器貫通孔を介して前記不活性ガス系の連
結配管14上の合流点22に接続される凝縮配管21と
隣接プラントの凝縮配管2l上に設置される凝縮配管隔
離弁24と、この合流点と隣接プラントの当該部分とを
接続する建屋連結配管23と隣接プラントの配管23の
二次格納施設内部分に設置される第2の空気作動弁25
と、二次格納施設外に設置されるめくらフランジ27と
、前記放出配管17とドライウェル側排気配管9を接続
する連結配管14に設置される第1の空気作動弁26と
を有して成ることを特徴とする格納容器ベント装■を提
供する.(作 用) このように構威された格納容器ベント装竃を有する原子
炉格納容器においては、事故発生プラントの格納容器内
雰囲気ガスをウェットウェル気相部から事故の発生して
いない隣接プラントのウェットウェル圧力抑制水中に直
接導くことができ、その後隣接プラントの格納容器内圧
が上昇した場合には、格納容器内雰囲気ガスをウエット
ウェル気相部から大気放出口へ直接放出することができ
る。さらに、苛酷事故収束過程において事故発生プラン
トのウェットウェル水位が上昇した場合に於いても格納
容器内雰囲気ガスをドライウェルから隣接プラントのウ
ェットウェル圧力抑制水中に直接導くことができる機能
を有している.また,格納容器内雰囲気ガスを環境に放
出する配管と,事故発生プラントの格納器内雰囲気ガス
を隣接プラントの圧力抑制水中に導くための配管と、こ
れらの配管は格納容器を貫通するため格納容器隔離弁が
各々2弁は少なくとも必要となる.これらの必要最小限
の機器のみで本発明は構威されかつ上記の3つの機能を
全て満足している. (実施例) 以下、本発明の第l実施例を第1図を参照して説明する
。第1図において、二次格納施83,103内には原子
炉格納容器2,102が収容されており、この原子炉格
納容器2,102内には原子炉圧力容器1,101が配
設されている.この原子炉格納容器2,102は主に2
つに分割され、原子炉格納容器1,101を収容する空
間をドライウェル4,104とし、圧力抑制水6を収容
する部分をウェットウェル5,105としている。この
ドライウェル4,104とウェットウェル5,105と
はベント管7,107によって連通している。前記ウェ
ットウェル5,105の上部には事故時に開動作する真
空破壊弁8,108が配設されている。
Specifically, as shown in FIG. 1, inert gas dry well and wet well side exhaust pipes 9 and 11 having openings in the dry well 4 and wet well 5, respectively, and these pipes 9 and 1l are The installed air-operated reactor containment vessel first isolation valves 10 and 12, the connection pipe 14 that connects the downstream side of the reactor containment vessel first isolation valve on each exhaust pipe, and the wet well side exhaust pipe. A discharge pipe 17 that directly connects the pipe between the first isolation valve 12 and the second isolation valve 13 of 11 and the atmospheric discharge port 20, and a discharge valve 18 and a rupture disk 19 installed on the discharge pipe 17 of the adjacent plant; The condensing pipe 21 has an opening in the pressure suppression water of the wet well and is connected to the confluence 22 on the inert gas system connecting pipe 14 through the reactor containment vessel through-hole, and the condensing pipe 2l of the adjacent plant. A condensation pipe isolation valve 24 installed in the building connecting pipe 23 connecting this confluence point with the relevant part of the adjacent plant and a second air actuator installed in the secondary containment facility part of the pipe 23 of the adjacent plant valve 25
, a blind flange 27 installed outside the secondary containment facility, and a first air-operated valve 26 installed in the connection pipe 14 connecting the discharge pipe 17 and the dry well side exhaust pipe 9. To provide a containment vessel vent system featuring the following features. (Function) In a reactor containment vessel having a containment vessel venting apparatus configured in this way, atmospheric gas inside the containment vessel of the plant where the accident occurred is transferred from the gas phase of the wet well to the adjacent plant where the accident did not occur. It can be led directly into the wet well pressure suppression water, and then when the internal pressure of the containment vessel of an adjacent plant increases, the atmospheric gas inside the containment vessel can be directly released from the wet well gas phase portion to the atmosphere discharge port. Furthermore, even if the water level in the wet well of the plant where the accident occurred rises during the course of concluding a severe accident, it has a function that allows atmospheric gas within the containment vessel to be directly guided from the dry well into the pressure suppression water in the wet well of the adjacent plant. There is. In addition, there are piping for releasing the atmospheric gas inside the containment vessel into the environment, piping for guiding the atmospheric gas inside the containment vessel of the plant where the accident occurred into the pressure suppression water of the adjacent plant, and because these pipings penetrate the containment vessel, they are connected to the containment vessel. At least two isolation valves are required for each. The present invention can be constructed using only these minimum necessary devices and satisfies all three functions mentioned above. (Embodiment) Hereinafter, a first embodiment of the present invention will be described with reference to FIG. In FIG. 1, a reactor containment vessel 2, 102 is housed in a secondary containment facility 83, 103, and a reactor pressure vessel 1, 101 is disposed within this reactor containment vessel 2, 102. ing. This reactor containment vessel 2,102 is mainly 2
The space that accommodates the reactor containment vessel 1, 101 is a dry well 4, 104, and the space that accommodates the pressure suppression water 6 is a wet well 5, 105. The dry well 4, 104 and the wet well 5, 105 communicate with each other through a vent pipe 7, 107. A vacuum breaker valve 8, 108 that opens in the event of an accident is provided above the wet well 5, 105.

前記ドライウェル4,104には不活性ガス系ドライウ
ェル側排気配管(以下ドライウェル側排気配管と呼ぶ)
9,1.09がドライウェル第1隔離井10を介して接
続されている。また前記ウェットウェル6,106の気
相部には不活性ガス系ウエットウエル側排気配管(以下
ウエットウェル側排気配管と呼ぶ) 11,111がウ
ェットウェル第1隔離弁12,112および第2隔離弁
13,113を介して接続されており、他端は前記二次
格納施設内に開放されている。前記ウェットウェル6,
106の圧力抑制水6,106中に一端を開放した凝縮
配管21,121は凝縮配管隔離弁24, 124を介
してドライウェル側排気配管9 ,109に接続されて
いる。このドライウエル側排気配管9,109と前記ウ
ェットウェル側排気配管11,111の第l隔離弁12
,112と第2隔離弁13,113との間は第1の空気
作動弁26 , 126を介して連結配管14,114
によって連結されている。この連結配管14,114は
さらに放出弁18,118、ラプチャーディスク19,
119を介して大気放出口である排気塔20,120へ
気体を導ひく放出配管17,117に接続されている.
そして,各プラントの前記ドライウェル側排気配管9,
109の他配管との接続部22,122は第2の空気作
動弁25,125およびめくらフランジ27, 127
を介して建屋この合流点28によって接続されている.
以上の構成において.苛酷事故が原子炉格納容器2内で
発生し格納容器が加圧されている状態を想定して実施例
の作用を説明する.苛酷事故発生後,格納容器ベントを
実施することが判断されると、まずめくらフランジ27
.127を取り外し建屋連轄配管28を接続する.原子
炉格納容器圧力高あるいは原子炉格納容器内放射能高の
原子炉格納容器隔離信号により図中の隔離弁,空気作動
弁はすべて閉止される.このため、ウェットウェル第1
隔離弁12、第1・第2空気作動弁26, 25、隣接
プラントの第2・第1空気作動弁125, 124を順
次手動操作により開弁ずる.これにより原子炉格納容器
2のドライウェル4中の雰囲気ガスは、ベント管7を介
してウェットウェル5の圧力抑制水6中を上昇しFPが
ある程度除去された後(以後スクラビングという)、不
活性ガス系ウエットウエル側排気配管l1.連結配管l
4及び建屋達終配管28を介して隣接プラントに導かれ
凝縮配管121を経てウェットウェル105の圧力抑制
水106中に直接放出される。この放出された事故プラ
ントの格納容器内雰囲気ガスは再度スクラビングを受け
隣接プラントのウェットウェル105の気相部に移行す
る.このため、気相部の圧力が上昇し真空破壊弁108
が作動するため、ウェットウェル気相部に蓄積した雰囲
気ガスはドライウェル104に流入する.このようにし
て、事故発生プラントの格納容器内雰囲気ガスが、隣接
プラントのドライウエルに放出されることにより事故発
生プラントの格納容器内圧の上昇は緩和され、事故発生
プラントの格納容器の過圧破損が防止される。また、こ
のとき事故発生プラントの格納容器内雰囲気ガスが高濃
度のFPを含んでいたとしても、事故の起つたていない
隣接プラントのドライウェル104に放出される雰囲気
ガスは、圧力抑制水6,106により2度スクラビング
を受けるため、雰囲気ガス中の粒子状FP濃度は低く、
隣接プラントのドライウエル104内のFPによる汚染
を極めて低く抑えることができる.そして十分な時間を
経た後,隣接プラントの格納容器内圧が上昇しベント圧
力以上に達した場合には,不活性ガス系のウエットウエ
ル側排気配管111に配設されたウエットウエル第1隔
離弁112を開弁じ,ウェット側排気配管111から分
岐し大気放出口(排気塔) 120に開弄される耐圧の
強化された放出配管117に配設された放出弁118を
開弁ずる.放出配管117上のラプチャーディスク11
9は格納容器ベント圧力以上で破損するように設計され
ているため、ウェットウェル105の気相部と大気放出
口120が連絡され、ドライウェル104の雰囲気ガス
はベント管107より圧力抑制水106中でさらにスク
ラビングを受けた後ウエットウエル気相部から大気放出
口(排気塔)120へ直接放出される.この場合環境に
放出されるFPはドライウエル104内で長時間滞留し
て十分減衰していること及び圧力抑制水106によりさ
らにスクラビングを受けるため,その量は極めて低く抑
えることができる. また、苛酷事故の収束の過程で事故発生プラントのウェ
ットウェル水位が上昇しウェットウェル側排気配管1l
が水没し格納容器のベントが実施できなくなる場合があ
る.このような場合には、ウェットウェル第1隔離弁1
2を閉止しドライウエル第1隔離弁10を開弁ずること
により、事故発生プラントの格納容器内雰囲気ガスをド
ライウエル側排気配管9より隣接プラントのウエットウ
エル圧力抑制水中に直接導くことができる。尚、建屋こ
の合流点28については、経済性及びプラント設計八の
影響を考慮して土中埋設方式も含めて適切な方法で設置
されるものとする。
The dry well 4, 104 has an inert gas dry well side exhaust pipe (hereinafter referred to as dry well side exhaust pipe).
9, 1.09 are connected via a dry well first isolation well 10. Further, in the gas phase portion of the wet well 6, 106, an inert gas-based wet well side exhaust pipe (hereinafter referred to as wet well side exhaust pipe) 11, 111 is connected to a wet well first isolation valve 12, 112 and a second isolation valve. 13 and 113, and the other end is open into the secondary storage facility. the wet well 6,
The condensing pipes 21, 121 with one end open in the pressure suppression water 6, 106 are connected to the dry well side exhaust pipes 9, 109 via condensing pipe isolation valves 24, 124. The first isolation valve 12 of the dry well side exhaust pipe 9, 109 and the wet well side exhaust pipe 11, 111
, 112 and the second isolation valves 13, 113 are connected via the first air-operated valves 26, 126 to the connecting pipes 14, 114.
connected by. The connecting pipes 14, 114 further include discharge valves 18, 118, rupture disks 19,
119 to exhaust pipes 17 and 117 that lead gas to exhaust towers 20 and 120, which are air discharge ports.
The dry well side exhaust pipe 9 of each plant,
Connection parts 22, 122 with other piping of 109 are second air operated valves 25, 125 and blind flanges 27, 127.
The buildings are connected by this junction 28.
In the above configuration. The operation of the embodiment will be explained assuming that a severe accident occurs in the reactor containment vessel 2 and the containment vessel is pressurized. After a severe accident occurs, when it is decided to vent the containment vessel, the blind flange 27
.. 127 and connect the building connecting pipe 28. All the isolation valves and air-operated valves in the figure are closed by the reactor containment isolation signal due to high pressure in the reactor containment vessel or high radioactivity in the reactor containment vessel. For this reason, the first wet well
The isolation valve 12, the first and second air-operated valves 26 and 25, and the second and first air-operated valves 125 and 124 of the adjacent plant are sequentially opened manually. As a result, the atmospheric gas in the dry well 4 of the reactor containment vessel 2 rises through the vent pipe 7 into the pressure suppression water 6 of the wet well 5, and after a certain amount of FP is removed (hereinafter referred to as scrubbing), it becomes inert. Gas system wet well side exhaust piping l1. Connecting pipe l
4 and the building end pipe 28 to an adjacent plant, and is directly discharged into the pressure suppression water 106 of the wet well 105 via the condensation pipe 121. This released atmospheric gas in the containment vessel of the accident plant is scrubbed again and transferred to the gas phase of the wet well 105 of the adjacent plant. Therefore, the pressure in the gas phase increases and the vacuum breaker valve 108
is activated, the atmospheric gas accumulated in the wet well gas phase flows into the dry well 104. In this way, the atmospheric gas in the containment vessel of the plant where the accident occurred is released into the dry well of the adjacent plant, which alleviates the increase in the internal pressure of the containment vessel of the plant where the accident occurred, causing overpressure damage to the containment vessel of the plant where the accident occurred. is prevented. Furthermore, even if the atmospheric gas in the containment vessel of the plant where the accident occurred contains a high concentration of FP, the atmospheric gas released into the dry well 104 of the adjacent plant where the accident did not occur will be the pressure suppression water 6, 106, the particulate FP concentration in the atmospheric gas is low.
Contamination by FP in the dry well 104 of the adjacent plant can be kept to an extremely low level. After a sufficient period of time, if the internal pressure of the containment vessel of the adjacent plant rises and reaches the vent pressure or higher, the wet well first isolation valve 112 installed in the inert gas system wet well side exhaust pipe 111 Then, open the discharge valve 118 installed in the pressure-reinforced discharge pipe 117 that branches from the wet side exhaust pipe 111 and opens to the atmosphere discharge port (exhaust tower) 120. Rupture disk 11 on discharge pipe 117
9 is designed to be damaged at pressure exceeding the containment vessel vent pressure, so the gas phase part of the wet well 105 and the atmosphere discharge port 120 are connected, and the atmospheric gas of the dry well 104 is discharged from the vent pipe 107 into the pressure suppression water 106. After further scrubbing, the gas is directly discharged from the wet well gas phase to the atmospheric discharge port (exhaust tower) 120. In this case, the amount of FP released into the environment can be kept extremely low because it remains in the dry well 104 for a long time and is sufficiently attenuated, and is further scrubbed by the pressure suppression water 106. In addition, during the process of resolving the severe accident, the water level of the wet well in the plant where the accident occurred rose and the wet well side exhaust pipe 1L
may become submerged, making it impossible to vent the containment vessel. In such a case, wetwell first isolation valve 1
2 and open the dry well first isolation valve 10, the atmospheric gas in the containment vessel of the plant where the accident occurred can be directly guided from the dry well side exhaust pipe 9 into the wet well pressure suppression water of the adjacent plant. The building junction 28 will be installed using an appropriate method, including underground burial, taking into account economic efficiency and plant design.

次に第2の実施例に関して第2図に基づき説明する.ま
ず、第2図において、第1図と同一部分には同一符号を
付しその部分の構成の説明は省略する。本実施例は新た
に設置する事故発生プラントの格納容器雰囲気ガスを他
プラントの圧力抑制水中に導く配管の原子炉格納容器貫
通孔が、ウエットウェル側に存在せずドライウエル側に
のみ存在するプラントに適用されるものである。第1の
実施例と異なる点は、事故プラントの格納容器雰囲気ガ
スを他プラントの圧力抑制水106に導く凝縮配管31
,131が,ドライウエル4,104を経由してベント
管30,130に挿入もしくは結合される点にある.こ
の場合においても事故発生プラントの格納容器内雰囲気
ガスは隣接プラントの圧力抑制水6,106中に直接導
かれ実施例1と同様の機能が期待される。
Next, the second embodiment will be explained based on FIG. 2. First, in FIG. 2, parts that are the same as those in FIG. This example describes a plant in which the reactor containment vessel through-hole for piping that guides the containment vessel atmospheric gas of the newly installed accident plant into the pressure suppression water of another plant does not exist on the wet well side but only on the dry well side. This applies to The difference from the first embodiment is that a condensing pipe 31 leads the containment vessel atmospheric gas of the accident plant to pressure suppression water 106 of another plant.
, 131 are inserted into or connected to the vent pipes 30, 130 via the dry wells 4, 104. Even in this case, the atmospheric gas in the containment vessel of the plant where the accident occurred is directly led into the pressure suppression water 6, 106 of the adjacent plant, and the same function as in the first embodiment is expected.

〔発明の効果〕〔Effect of the invention〕

このような原子炉格納容器を有する原子力発電プラント
に於いて、苛酷事故が発生し原子炉格納容器内の圧力が
上昇しFPが格納容器内に放出される場合,隣接プラン
トの原子炉格納容器の自由空間体積を当該プラントの原
子炉格納容器の内圧上昇の緩和に利用し希ガスを含む全
てのFPの減衰を行うことができる。また、FPを含む
ガスは事故発生プラントと隣接プラントの圧力抑制水に
よるスクラビングを受けるため、環境へ放出されるFP
量は極めて低く抑えることができる.この結果苛酷事故
時に、格納容器の過圧破損を防止するとともに、FPの
環境への大量放出を防止することが可能となる。このよ
うな効果を必要最小限の弁及び配管構成で達成しかつ隣
接プラントのドライウエル内の汚染を極力低く抑えるこ
とを可能とする格納容器ベント設備を提供することがで
きる。このことは格納容器ベント設備の経済性及び隣接
プラントの財産保護の観点から非常に有益な効果をもた
らす.
In a nuclear power plant with such a reactor containment vessel, if a severe accident occurs and the pressure inside the reactor containment increases and FP is released into the containment vessel, the reactor containment vessel of an adjacent plant may be affected. The free space volume can be used to alleviate the increase in internal pressure in the reactor containment vessel of the plant, and all FPs including rare gases can be attenuated. In addition, gas containing FP is scrubbed by pressure suppression water from the plant where the accident occurred and adjacent plants, so FP is released into the environment.
The amount can be kept extremely low. As a result, in the event of a severe accident, it is possible to prevent overpressure damage to the containment vessel and to prevent a large amount of FP from being released into the environment. It is possible to provide a containment vessel venting facility that achieves such effects with the minimum required valve and piping configuration, and that makes it possible to suppress contamination in the dry well of an adjacent plant to the lowest possible level. This has a very beneficial effect from the viewpoint of economic efficiency of the containment vent equipment and property protection of adjacent plants.

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

Claims (1)

【特許請求の範囲】[Claims] 複数プラントが立地する原子力発電所に於いて、原子炉
圧力容器と、この原子炉圧力容器を格納する原子炉格納
容器と、この原子炉格納容器をとり囲む二次格納施設と
、前記原子炉格納容器の内部上部に形成され原子炉圧力
容器を収容するドライウェルと原子炉圧力容器下方に収
容された圧力抑制水を内包するウェットウェルと、前記
ドライウェル及びウェットウェルに各々開口部を有する
ドライウェル側排気管及びウェットウェル側排気配管と
、この各々の排気配管に設置されるドライウェル第1隔
離弁およびウェットウェル第1隔離弁と、ドライウェル
及びウェットウェル側排気配管の各々第1隔離弁の下流
側を接続する連結配管と、ウェットウェル側排気配管と
ウェットウェル第1隔離弁及びこのウェットウェル第1
隔離弁の下流に配設された第2隔離弁間の配管と大気放
出口とを接続する放出配管と、この放出配管に設置され
た放出弁及びラプチャーディスクと、前記ウェットウェ
ル内に収容された圧力抑制水中に開口部を有し原子炉格
納容器貫通孔を介して前記ドライウェル側排気配管に接
続される凝縮配管と、この凝縮配管に設置される凝縮配
管隔離弁と、この合流点と隣接プラントの当該部分とを
接続する建屋連絡配管と、この建屋連絡配管の二次格納
施設内部分に設置される第2の空気作動弁と、この二次
格納施設外に設置されるめくらフランジと、前記放出配
管とドライウェル側排気配管を接続する連結配管設置さ
れる第1の空気作動弁とを有して成ることを特徴とする
原子炉格納容器ベント装置。
In a nuclear power plant where multiple plants are located, a reactor pressure vessel, a reactor containment vessel that stores this reactor pressure vessel, a secondary containment facility surrounding this reactor containment vessel, and the reactor containment vessel A dry well formed in the upper part of the interior of the container and accommodating the reactor pressure vessel, a wet well containing pressure suppression water housed below the reactor pressure vessel, and a dry well having an opening in each of the dry well and the wet well. A side exhaust pipe and a wet well side exhaust pipe, a dry well first isolation valve and a wet well first isolation valve installed in each of these exhaust pipes, and a first isolation valve of each of the dry well and wet well side exhaust pipes. The connection pipe connecting the downstream side, the wet well side exhaust pipe, the first wet well isolation valve, and the first wet well
A discharge pipe that connects the pipe between the second isolation valves arranged downstream of the isolation valve and the atmospheric discharge port, a discharge valve and a rupture disk installed in the discharge pipe, and a rupture disk housed in the wet well. A condensing pipe that has an opening in the pressure suppression water and is connected to the dry well side exhaust pipe via a reactor containment vessel through hole, a condensing pipe isolation valve installed in this condensing pipe, and adjacent to this confluence point. A building connecting pipe that connects the relevant part of the plant, a second air-operated valve installed in a part of the building connecting pipe inside the secondary containment facility, and a blind flange installed outside the secondary containment facility; A nuclear reactor containment vessel venting device comprising: a first air-operated valve installed in a connecting pipe connecting the discharge pipe and the dry well side exhaust pipe.
JP2002479A 1990-01-11 1990-01-11 Reactor containment venting equipment Expired - Fee Related JP2868819B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2002479A JP2868819B2 (en) 1990-01-11 1990-01-11 Reactor containment venting equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2002479A JP2868819B2 (en) 1990-01-11 1990-01-11 Reactor containment venting equipment

Publications (2)

Publication Number Publication Date
JPH03209193A true JPH03209193A (en) 1991-09-12
JP2868819B2 JP2868819B2 (en) 1999-03-10

Family

ID=11530481

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2002479A Expired - Fee Related JP2868819B2 (en) 1990-01-11 1990-01-11 Reactor containment venting equipment

Country Status (1)

Country Link
JP (1) JP2868819B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1122743A1 (en) * 2000-01-24 2001-08-08 General Electric Company Systems and methods for maintaining integrity of a primary containment vessel in a nuclear reactor
CN101777392B (en) 2009-11-17 2012-10-10 华北电力大学 A Supercritical CO2 Nuclear Power Plant Accident Buffer Removal Device

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1122743A1 (en) * 2000-01-24 2001-08-08 General Electric Company Systems and methods for maintaining integrity of a primary containment vessel in a nuclear reactor
CN101777392B (en) 2009-11-17 2012-10-10 华北电力大学 A Supercritical CO2 Nuclear Power Plant Accident Buffer Removal Device

Also Published As

Publication number Publication date
JP2868819B2 (en) 1999-03-10

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