JPH08194087A - Nuclear reactor facility - Google Patents

Nuclear reactor facility

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Publication number
JPH08194087A
JPH08194087A JP7006195A JP619595A JPH08194087A JP H08194087 A JPH08194087 A JP H08194087A JP 7006195 A JP7006195 A JP 7006195A JP 619595 A JP619595 A JP 619595A JP H08194087 A JPH08194087 A JP H08194087A
Authority
JP
Japan
Prior art keywords
cooling water
pressure vessel
open space
containment vessel
water
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
JP7006195A
Other languages
Japanese (ja)
Inventor
Akira Susuki
晃 須々木
Hiroaki Suzuki
洋明 鈴木
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 Ltd
Original Assignee
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 Ltd filed Critical Hitachi Ltd
Priority to JP7006195A priority Critical patent/JPH08194087A/en
Publication of JPH08194087A publication Critical patent/JPH08194087A/en
Pending legal-status Critical Current

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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
    • Y02E30/30—Nuclear fission reactors

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE: To provide a nuclear reactor facility in which water never permeates into apparatuses installed in an open space in the lower part of a pressure container at normal accident and in which places having probability of leakage of radioactive substances at arising of accident are hardly increased. CONSTITUTION: In a nuclear reactor facility which has a storage container 2 provided with a suppression pool 8 containing cooling water between a pressure container 1 and thereof and a cooling water circulating system 3 to lead the cooling water of the suppression pool 8 to the outside and return the cooling water to the storing container 2 after cooling; a water pouring tank 20 connected with the cooling water circulating system 3 and provided with a water supplying pump 19 is installed in the outside of the storage container 2 and at the same time a pipeline system of which one end is joined with an inner pipeline of the storage container 2 of the cooling water circulating system 3, whose the other end is joined with an open space immediate below the pressure container, and which has a control valve 11 in the middle is installed in the inside of the storage container 2. The water supplying pump 19 and the control valve 11 are so formed as to carry out water pouring work only at the time of occurrence of an incident that a core residue is discharged to the open space.

Description

【発明の詳細な説明】Detailed Description of the Invention

【０００１】[0001]

【産業上の利用分野】本発明は原子炉設備の改良に係
り、特に水にて冷却されるように形成されている原子炉
設備の改良に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to improvement of nuclear reactor equipment, and more particularly to improvement of nuclear reactor equipment formed so as to be cooled by water.

【０００２】[0002]

【従来の技術】核***原子炉においては、放射性および
他の核***生成物のために、いかなる条件下においても
充分に作動する安全設備が必要である。今、圧力容器内
の炉心燃料を冷却する安全設備が全て作動しない仮想的
な原子炉の苛酷事故を想定すると、溶融した炉心燃料が
圧力容器を貫通して落下し、圧力容器の下方にある開放
空間の床に滞留することになる。当然のことながらこの
溶融炉心は高温であることから周囲に及ぼす影響は大き
く、従来においては、この苛酷事故を終息させるため
に、冷却水をこの溶融炉心に注水することが行なわれる
ことになる。BACKGROUND OF THE INVENTION In nuclear fission reactors, radioactive and other fission products require safety equipment that operates well under any conditions. Now, assuming a hypothetical reactor severe accident in which all safety equipment for cooling the core fuel in the pressure vessel does not operate, the molten core fuel falls through the pressure vessel and opens below the pressure vessel. It will stay on the floor of the space. As a matter of course, since the melting core has a high temperature, it has a great influence on the surroundings, and conventionally, in order to end the severe accident, cooling water is injected into the melting core.

【０００３】溶融炉心に注水するこの種の技術として
は、例えば特開平１−２４５１９１号公報に開示されて
いるように、ベント管の冷却水通過経路を全て上部ドラ
イウェルから圧力容器下の開放空間を経由してウェット
ウェルヘ接続するもの、特開平２−２２２８７２号公報
に記載されているように圧力容器と放射線遮蔽壁の間に
注水することにより前記開放空間へ注水するもの、また
特開平２−２８１１９０号公報にあるようにサプレッシ
ョンプールの水を前記開放空間へ注水するものなどが挙
げられる。As a technique of this type for injecting water into the molten core, for example, as disclosed in Japanese Patent Laid-Open No. 1-245191, the cooling water passage of the vent pipe is entirely opened from the upper dry well to the open space under the pressure vessel. Connected to the wet well via the above-mentioned method, one described in Japanese Patent Application Laid-Open No. 2-222872 that pours water into the open space by pouring water between the pressure vessel and the radiation shielding wall, and Japanese Patent Application Laid-Open No. As described in Japanese Patent No. 281190, water in the suppression pool is poured into the open space.

【０００４】[0004]

【発明が解決しようとする課題】前記従来技術のうち、
特開平１−２４５１９１号公報および特開平２−２２２
８７２号公報に記載されている設備では、炉心が圧力容
器から溶融落下しない主蒸気管破断事故時においても圧
力容器下部開放空間に注水されるため、ここに設置され
ている制御棒駆動装置などが浸水のため、装置に悪影響
を与える恐れがあり、また、特開平２−２８１１９０号
公報の設備ではサプレッションプールと開放空間を連結
している弁が通常運転時に誤動作した場合などには、前
記同様の悪影響がある。Of the above-mentioned conventional techniques,
JP-A-1-245191 and JP-A-2-222
In the equipment described in Japanese Patent No. 872, since the core is injected into the open space below the pressure vessel even in the event of a main steam pipe breakage in which the core does not melt and fall from the pressure vessel, the control rod drive device installed here is Since there is a possibility that the device will be adversely affected due to water infiltration, and in the equipment of Japanese Patent Laid-Open No. 2-281190, when the valve connecting the suppression pool and the open space malfunctions during normal operation, the same as above. There is an adverse effect.

【０００５】さらに、安全設備の信頼性を増すために安
全設備を多重化することが考えられるが、例えば圧力容
器下部開放空間へ注水する配管を格納容器の外から新規
に設置することは格納容器の貫通部を増やすことにな
り、事故発生時に放射性物質の漏洩する可能性のある箇
所の増加となる点で好ましくない。Further, it is conceivable to multiplex the safety equipment in order to increase the reliability of the safety equipment. For example, it is necessary to newly install a pipe for injecting water into the open space below the pressure vessel from outside the containment vessel. It is not preferable because it increases the number of penetrations and increases the number of locations where radioactive material may leak when an accident occurs.

【０００６】本発明はこれに鑑みなされたもので、その
目的とするところは、通常事故時においては従来のよう
に圧力容器下部開放空間に設置されている制御棒駆動装
置などの装置が浸水することなく、かつ事故発生時に放
射性物質の漏洩する可能性のある箇所を増加させること
のないこの種の原子炉設備を提供するにある。The present invention has been made in view of the above circumstances, and an object thereof is to normally inject water into an apparatus such as a control rod drive apparatus installed in a lower open space of a pressure vessel at the time of an accident. It is an object of the present invention to provide a reactor facility of this type without increasing the number of locations where radioactive material may leak when an accident occurs.

【０００７】[0007]

【課題を解決するための手段】すなわち本発明は、内部
に原子炉炉心を内蔵する圧力容器と、この圧力容器を包
囲するとともに、圧力容器との間に冷却水を保有するサ
プレッションプールを備えた格納容器と、格納容器の外
部に配置され、前記サプレッションプールの冷却水を外
部に導きだし冷却後格納容器内に戻す冷却水循環系とを
備えている原子炉設備において、前記格納容器の外部
に、前記冷却水循環系に連結され、かつ給水ポンプを備
えた注水槽を設けるとともに、前記格納容器の内部に、
一方端が前記冷却水循環系の格納容器内配管に連結し、
他方端が圧力容器直下の開放空間と連通し、かつその途
中に制御弁を有する配管系を設け、前記給水ポンプおよ
び制御弁を、前記開放空間に炉心残骸が放出された事故
発生時にのみ注水作動するように形成し所期の目的を達
成するようにしたものである。That is, the present invention comprises a pressure vessel having a reactor core built therein, and a suppression pool surrounding the pressure vessel and holding cooling water between the pressure vessel and the pressure vessel. In a reactor vessel provided with a containment vessel and a cooling water circulation system which is arranged outside the containment vessel and guides the cooling water of the suppression pool to the outside and returns it to the inside of the containment vessel after cooling, outside the containment vessel, While being provided with a water injection tank connected to the cooling water circulation system and provided with a water supply pump, inside the containment vessel,
One end is connected to the piping inside the containment vessel of the cooling water circulation system,
The other end communicates with the open space directly below the pressure vessel, and a piping system with a control valve is installed in the middle, and the water supply pump and control valve are injected only when an accident occurs when core debris is discharged into the open space. It is designed to achieve the intended purpose.

【０００８】またこの場合、圧力容器下部の開放空間へ
の注水にスプレイヘッダを用いる構成となし、また、圧
力容器下部の開放空間への注水を感知器により自動的に
制御する構成とし、さらには圧力容器下部の開放空間へ
の注水が遠隔的に操作が可能な構成となし、また圧力容
器下部の開放空間への注水が環境温度に応答することに
よって行われる構成としたものである。また、感知器な
いし環境温度への応答する物体として、バイメタルない
し形状記憶合金を用いるようになしたものである。Further, in this case, the spray header is not used to inject water into the open space below the pressure vessel, and the water injection into the open space below the pressure vessel is automatically controlled by a sensor. Water is injected into the open space under the pressure vessel by remote control, and water is injected into the open space under the pressure vessel by responding to the ambient temperature. In addition, a bimetal or a shape memory alloy is used as a sensor or an object that responds to environmental temperature.

【０００９】[0009]

【作用】すなわちこのように形成された原子炉安全設備
であると、原子炉で事故発生時に圧力容器下部の開放空
間への注水の有無は、安全設備に設置された制御機構に
より可能となるため、開放空間へ炉心が溶融落下したと
きのみこの空間へ注水が行われ、また、本発明による圧
力容器下部の開放空間への注設備は、従来よりある炉心
冷却系および格納容器内冷却系安全設備が保有している
冷却水源および注水ポンプとは独立した冷却水源および
注水ポンプに接続しているため、従来よりある安全設備
の冷却水源及び注水ポンプに不具合が在った場合でも独
立した設備により溶融炉心燃料への注水が可能となる。[Function] That is, in the case of the reactor safety equipment formed in this way, the presence or absence of water injection into the open space under the pressure vessel can be controlled by the control mechanism installed in the safety equipment when an accident occurs in the reactor. Water is injected into this space only when the core melts and drops into the open space.Furthermore, the facility for injecting water into the open space under the pressure vessel according to the present invention is the conventional safety system for the core cooling system and the containment vessel cooling system. Since it is connected to a cooling water source and water injection pump that are independent of the cooling water source and water injection pump owned by the company, even if there is a problem with the cooling water source and water injection pump of the conventional safety equipment, it will be melted by the independent equipment. Water can be injected into the core fuel.

【００１０】また、通常運転時に制御機構が万一誤動作
しても、開放空間に炉心残骸が放出された事故発生時に
のみポンプが注水作動するように形成されているので、
この注水ポンプが駆動しない限り、圧力容器下部へは注
水はされない。Further, even if the control mechanism malfunctions during normal operation, the pump is formed so as to perform water injection only when an accident occurs in which core debris is discharged into the open space.
Water is not injected into the lower part of the pressure vessel unless this water injection pump is driven.

【００１１】さらに、圧力容器下部の開放空間への注水
設備は、従来よりある炉心冷却系および格納容器内冷却
系安全設備と格納容器内部で結合（分岐）する構成とな
っているので、従来の原子炉格納容器と貫通部の数は等
しく、放射性物質漏洩の可能性は新規設備の設置にもか
かわらず増加することはないのである。Furthermore, since the water injection facility to the open space under the pressure vessel is constructed so as to be connected (branched) inside the containment vessel with the conventional core cooling system and containment vessel cooling system safety equipment, The number of reactor containment vessels and penetrations is the same, and the possibility of radioactive material leakage will not increase despite the installation of new equipment.

【００１２】[0012]

【実施例】以下図示した実施例に基づいて本発明を詳細
に説明する。図１にはその沸騰水型原子炉に適用した場
合の一実施例が示されている。図の中央には符号１とし
て炉心燃料を収納している圧力容器があり、そしてこの
圧力容器の外側には、この圧力容器を包囲するととも
に、圧力容器との間に冷却水を保有するサプレッション
プール８を備えた格納容器２がある。DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described in detail with reference to the illustrated embodiments. FIG. 1 shows an embodiment when applied to the boiling water reactor. At the center of the figure, there is a pressure vessel containing the core fuel as reference numeral 1, and on the outside of this pressure vessel, a suppression pool that surrounds this pressure vessel and holds cooling water between it and the pressure vessel. There is a containment vessel 2 equipped with 8.

【００１３】また、原子炉冷却材喪失事故発生時に原子
炉炉心及び格納容器内を冷却する安全設備配管３、格納
容器内で発生した熱を除去するための熱交換器４、安全
設備に冷却水を供給するポンプ５、格納容器内スプレイ
ヘッダ９が設けられている。Also, safety facility piping 3 for cooling the reactor core and the containment vessel when a reactor coolant loss accident occurs, a heat exchanger 4 for removing heat generated in the containment vessel, and cooling water for the safety facility. A pump 5 for supplying water and a spray header 9 in the storage container are provided.

【００１４】さらに、この原子炉には本発明である圧力
容器下部開放空間１７へ注水する安全設備配管６、７、
圧力容器下部開放空間への注水の有無を決定する制御機
構として、弁１１、１２、安全設備とは独立した注水ポ
ンプ１９、注水源２０、安全設備とポンプ１９、注水源
２０とを隔離する弁１８が設置されている。Further, in this reactor, safety equipment pipes 6, 7 for injecting water into the pressure vessel lower open space 17 of the present invention,
Valves 11 and 12, a water injection pump 19 independent of the safety equipment, a water injection source 20, a valve for isolating the safety equipment and the pump 19, and a water injection source 20 as a control mechanism for determining the presence or absence of water injection into the lower open space of the pressure vessel. 18 are installed.

【００１５】原子炉の通常運転時には、弁１１、１２、
１８を閉じ、弁１０、１３を開いておく。原子炉圧力容
器内の冷却材喪失事故が発生した場合には、サプレッシ
ョンプールの水を圧力容器１内に注水するため、弁１
４、１５、１６を開いた状態にし、ポンプ５を駆動する
ことによって、炉心の冷却・事故の終息は達成される。During normal operation of the reactor, the valves 11, 12,
18 is closed and valves 10 and 13 are open. When a coolant loss accident in the reactor pressure vessel occurs, the valve 1 is used to inject water from the suppression pool into the pressure vessel 1.
By opening 4, 15, and 16 and driving the pump 5, the cooling of the core and the end of the accident are achieved.

【００１６】この場合炉心燃料の損傷は起こらないた
め、圧力容器下部の開放空間１７には注水する必要はな
いが、弁１１、１２が閉じていることでこれは達成され
る。これにより、圧力容器下部の開放空間１７に設置し
てある制御棒駆動機構などの機器が浸水することはな
い。In this case, since the core fuel is not damaged, it is not necessary to inject water into the open space 17 under the pressure vessel, but this is achieved by closing the valves 11 and 12. As a result, the devices such as the control rod drive mechanism installed in the open space 17 below the pressure vessel will not be flooded.

【００１７】圧力容器内の炉心燃料を冷却する安全設備
が作動しない仮想的な原子炉の苛酷事故（全ての安全設
備のポンプ５が駆動しない、熱交換器４が機能しない場
合がこれに該当する）の発生時には、圧力容器１内に注
水を行うことができずに炉心燃料は溶融し、圧力容器を
貫通して圧力容器下部の開放空間１７に滞留する。この
場合は、弁１１、１２、１８を開き、弁１０、１３、１
４、１５、１６を閉じる。A virtual nuclear reactor severe accident in which the safety equipment for cooling the core fuel in the pressure vessel does not operate (corresponding to cases where the pump 5 of all safety equipment does not operate and the heat exchanger 4 does not function). ), Water cannot be injected into the pressure vessel 1, the core fuel is melted, penetrates the pressure vessel, and stays in the open space 17 under the pressure vessel. In this case, open valves 11, 12, 18 and open valves 10, 13, 1
Close 4, 15, and 16.

【００１８】さらにポンプ１９を駆動することによって
滞留している溶融炉心を注水源２１より注水冷却するこ
とができる。さらに上記弁の閉鎖により、ポンプ５、熱
交換器４は安全設備配管３から隔離されるため、溶融炉
心冷却中に、復旧作業が可能となる。なお、ポンプ１
９、注水源２０には既存の消火系、復水補給系、純水補
給系の各設備を当てることが可能である。Further, by driving the pump 19, the accumulated molten core can be cooled by water injection from the water injection source 21. Further, by closing the valve, the pump 5 and the heat exchanger 4 are separated from the safety equipment pipe 3, so that the recovery work can be performed during the cooling of the melting core. In addition, pump 1
9. The existing water extinguishing system, condensate supply system, and pure water supply system can be applied to the water injection source 20.

【００１９】以上の操作により、炉心が溶融し圧力容器
を炉心が貫通して圧力容器下部の下方空間に落下した場
合にのみ、該当箇所へ注水することが可能になる。By the above operation, it becomes possible to inject water to the relevant location only when the core melts and the core penetrates the pressure vessel and falls into the space below the pressure vessel.

【００２０】本発明による圧力容器下部の開放空間への
注水設備は、図より分かるように従来からの安全設備配
管と格納容器内で分岐する構造となっている。そのた
め、従来の原子炉格納容器と貫通部の数は等しく、放射
性物質漏洩の可能性は新規設備の設置にもかかわらず増
加しない。As can be seen from the figure, the water injection equipment for the open space under the pressure vessel according to the present invention has a structure that branches off from the conventional safety equipment piping and the containment vessel. Therefore, the number of penetrations is the same as that of the conventional reactor containment vessel, and the possibility of radioactive material leakage does not increase despite the installation of new equipment.

【００２１】図２に本発明を沸騰水型原子炉に適用した
別の実施例を示す。この例では、溶融した炉心燃料への
注水にスプレイヘッダ９を用いた例である。公開文献
（Pro-ceeding of the International Seminar on The
Physics of Vapor ExplosionsPage.182〜183）からの知
見によれば、溶融金属に水をかける場合、高圧スプレイ
を用いることによって水蒸気爆発はより起こりにくくな
ると考えられる。よってこの発明によれば、仮想苛酷事
故時に注水する場合、水蒸気爆発による格納容器の損傷
の可能性をより少なくできる。FIG. 2 shows another embodiment in which the present invention is applied to a boiling water reactor. In this example, the spray header 9 is used to inject water into the molten core fuel. Published literature (Pro-ceeding of the International Seminar on The
According to the findings from Physics of Vapor Explosions Page.182-183), steam explosion is considered to be less likely to occur by using high pressure spray when water is poured onto molten metal. Therefore, according to the present invention, when water is injected in a virtual severe accident, the possibility of damage to the containment vessel due to a steam explosion can be further reduced.

【００２２】図３に本発明を沸騰水型原子炉に適用した
別の実施例を示す。これは圧力容器下部の開放空間１７
に感知器２１を備えたものである。これにより溶融した
炉心燃料が開放空間に滞留したことを検知しその信号を
もとに、弁１１、１２、１８を開き、弁１０、１３、１
４、１５、１６を閉じ、さらにポンプ１９を駆動するこ
とを自動的に制御することができる。これにより苛酷事
故発生時に、運転員の操作負担が軽減できる。FIG. 3 shows another embodiment in which the present invention is applied to a boiling water reactor. This is the open space 17 under the pressure vessel
It is equipped with a sensor 21. As a result, it is detected that the molten core fuel has accumulated in the open space, and based on the signal, the valves 11, 12, 18 are opened, and the valves 10, 13, 1 are opened.
It is possible to automatically control the driving of the pump 19 by closing 4, 15, 16 further. This can reduce the operational burden on the operator when a severe accident occurs.

【００２３】図４に本発明を沸騰水型原子炉に適用した
別の実施例を示す。これは圧力容器下部の開放空間１７
への注水を遠隔操作制御器２２によって操作可能とした
ものである。これにより図３に示した感知器が壊れるよ
うな更に苛酷な場合においても、運転員の判断により、
注水が行うことができる。FIG. 4 shows another embodiment in which the present invention is applied to a boiling water reactor. This is the open space 17 under the pressure vessel
It is possible to control the water injection to the remote control controller 22. Even if the sensor shown in Fig. 3 breaks down due to this, the operator judges
Water injection can be done.

【００２４】本発明の別の実施例として、圧力容器下部
の開放空間１７への注水を環境温度に応答することによ
って行うようにすることもできる。図３において、圧力
容器下部の開放空間１７は通常運転時や、苛酷事故以外
の事故時に比してはるかに高温となる。そのため、ある
一定温度以上になると本発明である一連の操作をするよ
うに感知器を設定することによって、自動的にこの事故
における操作を行うことができる。As another embodiment of the present invention, water can be injected into the open space 17 under the pressure vessel by responding to the ambient temperature. In FIG. 3, the open space 17 under the pressure vessel has a much higher temperature than during normal operation or during an accident other than a severe accident. Therefore, the operation in this accident can be automatically performed by setting the sensor so as to perform a series of operations according to the present invention when a certain temperature or higher is reached.

【００２５】本発明の別の実施例として、感知器ないし
環境温度への応答する物体として、バイメタルないし形
状記憶合金を用いる構成とすることができる、この実施
例によれば、電気駆動の感知器を用いる場合に比べて電
池などの駆動源が不要となり、感知器の故障の確率も低
減できる。In another embodiment of the present invention, a bimetal or shape memory alloy may be used as a sensor or an object responsive to ambient temperature. According to this embodiment, an electrically driven sensor is used. As compared with the case of using, a driving source such as a battery is not required, and the probability of sensor failure can be reduced.

【００２６】図５に本発明の沸騰水型原子炉に適用した
別の実施例を示す。これは、弁１１、１２に溶融弁を用
いたものである。通常の弁をこの安全設備に用いる場合
は、溶融炉心燃料による弁の破損を防ぐために、圧力容
器下部の開放空間１７とは別の箇所に設置することが望
ましい。しかし、溶融弁は溶融炉心燃料が発生する熱に
より自動的に開く構造をとっているので、弁１１、１２
は圧力容器下部の開放空間１７内に置く必要がある。本
発明によれば、感知器の役割を溶融弁が果たすので感知
器が不要となり、圧力容器下部の開放空間１７への注水
ルートが受動的に確保される。FIG. 5 shows another embodiment applied to the boiling water reactor of the present invention. This uses a melting valve for the valves 11 and 12. When a normal valve is used for this safety equipment, it is desirable to install it in a position different from the open space 17 under the pressure vessel in order to prevent the valve from being damaged by the molten core fuel. However, since the melting valve has a structure that automatically opens by the heat generated by the molten core fuel, the valves 11, 12
Must be placed in the open space 17 under the pressure vessel. According to the present invention, since the melting valve plays the role of the sensor, the sensor is not necessary, and the water injection route to the open space 17 under the pressure vessel is passively secured.

【００２７】以上説明してきたように、本発明である
と、原子炉で事故発生時に圧力容器下部の開放空間への
注水の有無を開放空間へ炉心が溶融落下したときのみ注
水され、苛酷事故以外の事故においてのこの箇所にある
制御棒駆動機構などの装置の浸水を防ぐことができるの
で、これらの装置の復旧が容易であり、従来の苛酷事故
対応設備のない原子炉に比して、苛酷事故時の安全性は
向上し、従来技術による圧力容器下部の開放空間への注
水設備に比較して機器の保守性が向上する効果がある。As described above, according to the present invention, when an accident occurs in a nuclear reactor, whether or not water is injected into the open space under the pressure vessel is injected only when the core melts and drops into the open space, except for severe accidents. In this accident, it is possible to prevent flooding of devices such as the control rod drive mechanism in this part, so it is easy to restore these devices, and compared to the conventional reactors that do not have severe accident response equipment, The safety at the time of an accident is improved, and the maintainability of the equipment is improved as compared with the conventional water injection facility into the open space under the pressure vessel.

【００２８】また、溶融落下した燃料を高圧スプレイを
用いて冷却することにより、水蒸気爆発の可能性をより
低減できるので、原子炉の過酷事故時の安全性をより向
上でき、さらに感知器により自動的に事故時に溶融炉心
に注水が行われ、運転員の操作数を低減できるので、事
故終息のための操作性が向上する。また、圧力容器下部
の開放空間においた感知器が壊れるようなさらに過酷な
場合においても、運転員の判断により注水が行うことが
できるので、原子炉の事故終息性を保持する効果があ
る。Further, by cooling the melted and dropped fuel by using a high pressure spray, the possibility of a steam explosion can be further reduced, so that the safety at the time of a severe accident of the reactor can be further improved, and further the automatic detection by the sensor is possible. Since water is injected into the molten core during an accident, the number of operations by the operator can be reduced, and the operability for ending the accident is improved. Further, even in a more severe case where the sensor in the open space below the pressure vessel is broken, water can be injected at the operator's discretion, which has the effect of maintaining the accident termination of the reactor.

【００２９】また、環境温度により応答するようにした
ことで自動的に事故時に溶融炉心に注水が行われ、運転
員の操作数を低減できるので、事故終息のための操作性
が向上する。また、感知器ないし環境温度への応答する
物体として、バイメタルないし形状記憶合金を用いてい
ることにより、感知器の簡素化、故障の確率が低減でき
るので、原子炉の安全設備の信頼性を向上する効果があ
る。Further, since the reaction is performed depending on the ambient temperature, water is automatically injected into the molten core at the time of an accident, and the number of operations of the operator can be reduced, so that the operability for ending the accident is improved. Also, by using a bimetal or shape memory alloy as a sensor or an object that responds to ambient temperature, the sensor can be simplified and the probability of failure can be reduced, improving the reliability of safety equipment of the reactor. Has the effect of

【００３０】さらに、圧力容器下部の開放空間への注水
設備に温度を検知し開口する弁を用いるようにしたの
で、感知器が不要となり、圧力容器下部の開放空間への
注水ルートが受動的に確保され、事故終息のための操作
性が向上する。Further, since the valve for detecting and opening the temperature is used in the water injection equipment to the open space under the pressure vessel, a sensor is not required, and the water injection route to the open space under the pressure vessel is passive. It is ensured and the operability for ending the accident is improved.

【００３１】[0031]

【発明の効果】以上説明してきたように本発明によれ
ば、圧力容器下部の開放空間に炉心残骸が放出された事
故発生時にのみ注水が行われるので、通常事故時におい
ては従来のように圧力容器下部の開放空間圧力容器下部
開放空間に設置されている制御棒駆動装置などの装置が
浸水することなく、かつこのような構成にするにも事故
発生時に放射性物質の漏洩する可能性のある箇所を増加
させることのないこの種の原子炉安全設備を得ることが
できる。As described above, according to the present invention, water is injected only when an accident occurs in which the core debris is discharged into the open space below the pressure vessel, so that in the case of a normal accident, the pressure is reduced as in the conventional case. Open space under the container Pressure where the control rod drive and other devices installed in the open space under the container are not submerged, and even with such a structure, there is a possibility that radioactive materials may leak when an accident occurs. This type of reactor safety equipment can be obtained without increasing the

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

【図１】本発明の原子炉設備の一実施例を示す縦断側面
図である。FIG. 1 is a vertical sectional side view showing an embodiment of a nuclear reactor facility of the present invention.

【図２】本発明の原子炉設備の他の実施例を示す縦断側
面図である。FIG. 2 is a vertical sectional side view showing another embodiment of the nuclear reactor equipment of the present invention.

【図３】本発明の原子炉設備の他の実施例を示す縦断側
面図である。FIG. 3 is a vertical sectional side view showing another embodiment of the nuclear reactor equipment of the present invention.

【図４】本発明の原子炉設備の他の実施例を示す縦断側
面図である。FIG. 4 is a vertical sectional side view showing another embodiment of the nuclear reactor equipment of the present invention.

【図５】本発明の原子炉設備の他の実施例を示す縦断側
面図である。FIG. 5 is a vertical sectional side view showing another embodiment of the nuclear reactor equipment of the present invention.

【符号の説明】[Explanation of symbols]

１…圧力容器、２…格納容器、３…安全設備配管、４…
熱交換器、５…ポンプ、６，７…圧力容器下部開放空間
注水用配管、８…サプレッションプール、９…スプレイ
ヘッダ、１０〜１６…弁、１７…圧力容器下部開放空
間、１８…弁、１９…ポンプ、２０…注水源、２１…感
知器、２２…遠隔操作制御器。1 ... Pressure vessel, 2 ... Containment vessel, 3 ... Safety equipment piping, 4 ...
Heat exchanger, 5 ... Pump, 6, 7 ... Pressure vessel lower open space water injection pipe, 8 ... Suppression pool, 9 ... Spray header, 10-16 ... Valve, 17 ... Pressure vessel lower open space, 18 ... Valve, 19 ... pump, 20 ... water injection source, 21 ... sensor, 22 ... remote control.

Claims (9)

【特許請求の範囲】[Claims] 【請求項１】 内部に原子炉炉心を内蔵する圧力容器
と、該圧力容器を包囲するとともに、圧力容器との間に
冷却水を保有するサプレッションプールを備えた格納容
器と、該格納容器の外部に配置され、前記サプレッショ
ンプールの冷却水を外部に導きだし冷却後格納容器内に
戻す冷却水循環系とを備えている原子炉設備において、 前記格納容器の外部に、前記冷却水循環系に連結され、
かつ給水ポンプを備えた注水槽を設けるとともに、前記
格納容器の内部に、一方端が前記冷却水循環系の格納容
器内配管に連結され、かつ他方端が圧力容器直下の開放
空間と連通し、かつその途中に制御弁を有する配管系を
設け、前記給水ポンプおよび制御弁を、前記開放空間に
炉心残骸が放出された事故発生時にのみ注水作動するよ
うに形成したことを特徴とする原子炉設備。1. A pressure vessel having a reactor core built therein, a containment vessel surrounding the pressure vessel and having a suppression pool for holding cooling water between the pressure vessel, and an exterior of the containment vessel. In the reactor equipment provided with a cooling water circulation system that is arranged in a cooling water circulation system that guides the cooling water of the suppression pool to the outside and returns the cooling water to the inside of the containment vessel after cooling, outside the containment vessel, is connected to the cooling water circulation system,
Also, while providing a water injection tank equipped with a water supply pump, inside the containment vessel, one end is connected to the containment vessel piping of the cooling water circulation system, and the other end communicates with the open space immediately below the pressure vessel, and A reactor system characterized in that a piping system having a control valve is provided on the way, and the water supply pump and the control valve are formed so as to perform a water injection operation only when an accident occurs in which core debris is discharged into the open space. 【請求項２】 内部に原子炉炉心を内蔵する圧力容器
と、該圧力容器を包囲するとともに、圧力容器との間に
冷却水を保有するサプレッションプールを備えた格納容
器と、該格納容器の外部に配置され、前記サプレッショ
ンプールの冷却水を外部に導きだし冷却後格納容器内に
戻す冷却水循環系とを備えている原子炉設備において、 前記格納容器の外部に、前記冷却水循環系に連結され、
かつ給水ポンプを備えた注水槽を設けるとともに、前記
格納容器の内部に、一方端が前記冷却水循環系の格納容
器内配管に連結され、他方端が圧力容器直下の開放空間
と連通し、かつその途中に制御弁を有する配管系を設
け、さらに前記給水ポンプおよび制御弁を前記開放空間
に炉心残骸が放出された事故発生時にのみ注水作動する
ように制御する制御装置を設けたことを特徴とする原子
炉設備。2. A pressure vessel having a reactor core inside, a containment vessel surrounding the pressure vessel and having a suppression pool for holding cooling water between the pressure vessel, and an outside of the containment vessel. In the reactor equipment provided with a cooling water circulation system that is arranged in a cooling water circulation system that guides the cooling water of the suppression pool to the outside and returns the cooling water to the inside of the containment vessel after cooling, outside the containment vessel, is connected to the cooling water circulation system,
Also, while providing a water injection tank equipped with a water supply pump, inside the containment vessel, one end is connected to a pipe inside the containment vessel of the cooling water circulation system, the other end communicates with an open space immediately below the pressure vessel, and A pipe system having a control valve is provided on the way, and a control device is further provided for controlling the water supply pump and the control valve so as to perform a water injection operation only when an accident occurs in which core debris is discharged into the open space. Reactor equipment. 【請求項３】 前記格納容器の内部に設けられている配
管系の開放空間側端部に、スプレイヘッダを設けてなる
請求項１若しくは２記載の原子炉設備。3. The nuclear reactor facility according to claim 1, wherein a spray header is provided at an end of the piping system provided inside the containment vessel on the open space side. 【請求項４】 前記圧力容器下部の開放空間に温度を感
知する感知器を設け、該感知器の感知信号により前記給
水ポンプの始動および制御弁の開口制御を自動的に制御
してなる請求項１若しくは２記載の原子炉設備。4. A sensor for sensing temperature is provided in an open space below the pressure vessel, and a start signal of the water supply pump and an opening control of a control valve are automatically controlled by a sensing signal of the sensor. The nuclear reactor facility according to 1 or 2. 【請求項５】 前記感知器の温度に応答する物体とし
て、バイメタル若しくは形状記憶合金を用いてなる請求
項４記載の原子炉設備。5. The nuclear reactor facility according to claim 4, wherein a bimetal or a shape memory alloy is used as the object responsive to the temperature of the sensor. 【請求項６】 前記給水ポンプおよび前記制御弁の制御
を、遠隔的に操作が可能なように形成してなる請求項１
若しくは２記載の原子炉設備。6. The control of the water supply pump and the control valve is formed so as to be remotely operable.
Alternatively, the nuclear reactor facility described in 2. 【請求項７】 前記圧力容器下部の開放空間への注水が
環境温度に応答することによって行われる請求項１若し
くは２記載の原子炉設備。7. The nuclear reactor facility according to claim 1, wherein water is injected into the open space below the pressure vessel in response to an ambient temperature. 【請求項８】 環境温度へ応答する物体としてバイメタ
ル若しくは形状記憶合金を用いてなる請求項７記載の原
子炉設備。8. The nuclear reactor facility according to claim 7, wherein a bimetal or a shape memory alloy is used as an object that responds to ambient temperature. 【請求項９】 前記格納容器の内部に設けられている配
管系の制御弁に、温度を検知し開口する弁を用いてなる
請求項１若しくは２記載の原子炉設備。9. The reactor facility according to claim 1, wherein a valve for detecting a temperature and opening the valve is used as a control valve for a piping system provided inside the containment vessel.
JP7006195A 1995-01-19 1995-01-19 Nuclear reactor facility Pending JPH08194087A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7006195A JPH08194087A (en) 1995-01-19 1995-01-19 Nuclear reactor facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7006195A JPH08194087A (en) 1995-01-19 1995-01-19 Nuclear reactor facility

Publications (1)

Publication Number Publication Date
JPH08194087A true JPH08194087A (en) 1996-07-30

Family

ID=11631771

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7006195A Pending JPH08194087A (en) 1995-01-19 1995-01-19 Nuclear reactor facility

Country Status (1)

Country Link
JP (1) JPH08194087A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20030040918A (en) * 2001-11-17 2003-05-23 한국수력원자력 주식회사 System for emergency cooling of reactor
WO2011099200A1 (en) * 2010-02-09 2011-08-18 三菱重工業株式会社 Foundation for a building in a nuclear facility and nuclear facility

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20030040918A (en) * 2001-11-17 2003-05-23 한국수력원자력 주식회사 System for emergency cooling of reactor
WO2011099200A1 (en) * 2010-02-09 2011-08-18 三菱重工業株式会社 Foundation for a building in a nuclear facility and nuclear facility
JP2011163927A (en) * 2010-02-09 2011-08-25 Mitsubishi Heavy Ind Ltd Basic slab of building of nuclear plant, and nuclear plant
CN102656643A (en) * 2010-02-09 2012-09-05 三菱重工业株式会社 Basic slab of building of nuclear plant, and nuclear plant

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