JPH0862373A - Reactor containment heat removal device - Google Patents

Reactor containment heat removal device

Info

Publication number
JPH0862373A
JPH0862373A JP6199389A JP19938994A JPH0862373A JP H0862373 A JPH0862373 A JP H0862373A JP 6199389 A JP6199389 A JP 6199389A JP 19938994 A JP19938994 A JP 19938994A JP H0862373 A JPH0862373 A JP H0862373A
Authority
JP
Japan
Prior art keywords
reactor
water
pipe
heat exchanger
booster pump
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
JP6199389A
Other languages
Japanese (ja)
Inventor
Kouhei Hisamochi
康平 久持
Tomoyuki Matsumoto
知行 松本
Masaki Matsumoto
雅喜 松本
Kenichi Sato
憲一 佐藤
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 JP6199389A priority Critical patent/JPH0862373A/en
Publication of JPH0862373A publication Critical patent/JPH0862373A/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

(57)【要約】 【目的】原子炉の残留熱除去系が作動しない場合でも、
原子炉格納容器内に蓄積される崩壊熱の除去を可能にす
る。 【構成】原子炉圧力容器２に接続する再循環ループ５か
ら抽出炉水配管１１に流出する炉水を、吸込水昇圧ポン
プ１４により昇圧させ、再生熱交換器吸込水冷却部７及
び非再生熱交換器９で冷却し、ろ過脱塩器１０で浄化
し、再生熱交換器吸込水加熱部８で適温にした後、原子
炉圧力容器２への給水配管１５に送水し、原子炉圧力容
器２に戻す原子炉冷却材浄化系において、サプレッショ
ンプール４と抽出炉水配管１１とを連結する配管１６、
ろ過脱塩器バイパス配管１７、再生熱交換器吸込水加熱
部バイパス配管１８、配管１６に排出水昇圧ポンプ１
９、及び排出水昇圧ポンプ１９の両側に電動弁２０、２
１を、それぞれ設けている。 (57) [Summary] [Purpose] Even if the residual heat removal system of the reactor does not operate,
It enables removal of decay heat accumulated in the reactor containment vessel. [Structure] Reactor water flowing out from a recirculation loop 5 connected to a reactor pressure vessel 2 to an extraction reactor water pipe 11 is pressurized by a suction water booster pump 14, and a regenerative heat exchanger suction water cooling unit 7 and non-regenerative heat After cooling with the exchanger 9, purification with the filter demineralizer 10 and heating to the proper temperature in the regenerative heat exchanger suction water heating unit 8, the water is fed to the water supply pipe 15 to the reactor pressure vessel 2 and the reactor pressure vessel 2 16 for connecting the suppression pool 4 and the extraction reactor water pipe 11 in the reactor coolant purification system for returning to
Filter demineralizer bypass pipe 17, regeneration heat exchanger suction water heating part bypass pipe 18, drain water booster pump 1 in pipe 16.
9 and electric valves 20, 2 on both sides of the discharge water booster pump 19.
1 are provided respectively.

Description

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

【０００１】[0001]

【産業上の利用分野】本発明は原子炉格納容器除熱装置
に係り、特に沸騰水型原子炉における原子炉冷却材浄化
系を、非常時に原子炉格納容器の崩壊熱除去系として利
用する原子炉格納容器除熱装置に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor containment heat removal apparatus, and more particularly, to an atomic reactor utilizing a reactor coolant purification system in a boiling water reactor as a decay heat removal system for a reactor containment in an emergency. The present invention relates to a heat removal device for a containment vessel.

【０００２】[0002]

【従来の技術】原子炉冷却材浄化系は、原子炉の炉水の
浄化を目的としており、次のような機能を有する。すな
わち、原子炉の再循環ループから引き出された抽出炉水
が、吸込水冷却部と吸込水加熱部とを有する再生熱交換
器の吸込水冷却部、及び非再生熱交換器をそれぞれ通過
して冷却された後、ろ過脱塩器によって浄化され、次い
で、再生熱交換器の吸込水加熱部を通過して昇温された
後、原子炉格納容器へ外部から給水する給水配管に送水
され、原子炉圧力容器内へ戻される。また、再生熱交換
器及び非再生熱交換器の上流側か下流側かのいずれか
に、抽出炉水を送水するための吸込水昇圧ポンプが設置
される。（日本機械学会編、機械工学便覧、Ｂ６-１５
７参照）。2. Description of the Related Art A reactor coolant purification system is intended to purify reactor water and has the following functions. That is, the extraction reactor water drawn from the recirculation loop of the reactor, the suction water cooling unit of the regenerative heat exchanger having a suction water cooling unit and a suction water heating unit, and the non-regeneration heat exchanger respectively. After being cooled, it is purified by a filter demineralizer, then passed through the suction water heating part of the regenerative heat exchanger to be heated, and then sent to the water supply pipe for supplying water to the reactor containment vessel from the outside. Returned to the furnace pressure vessel. Further, a suction water booster pump for feeding the extraction reactor water is installed on either the upstream side or the downstream side of the regenerated heat exchanger and the non-regenerated heat exchanger. (Mechanical Engineering Handbook, edited by Japan Society of Mechanical Engineers, B6-15
7).

【０００３】冷却水昇圧ポンプは、再生熱交換器及び非
再生熱交換器の位置が、サプレッションプールよりも高
い場合には、再生熱交換器及び非再生熱交換器の上流側
に設置される。すなわち、再循環ループから吸込水昇圧
ポンプまでの揚程が、抽出炉水の円滑な流動に大きく寄
与するように、すなわち抽出炉水が原子炉冷却水浄化系
内の流動抵抗に打ち勝ち、抽出炉水の原子炉冷却水浄化
系内の通過ができるだけ円滑であるように、吸込水昇圧
ポンプは再循環ループに近い高さに設置され、サプレッ
ションプールよりも高い位置となる。The cooling water booster pump is installed upstream of the regenerative heat exchanger and the non-regenerative heat exchanger when the positions of the regenerative heat exchanger and the non-regenerative heat exchanger are higher than the suppression pool. That is, the pump head from the recirculation loop to the suction water booster pump should contribute greatly to the smooth flow of the extraction reactor water, that is, the extraction reactor water overcomes the flow resistance in the reactor cooling water purification system, In order to make the passage through the reactor cooling water purification system as smooth as possible, the suction water booster pump is installed at a height close to the recirculation loop and higher than the suppression pool.

【０００４】しかし、この場合、吸込水昇圧ポンプを通
過する抽出炉水は高温となるので、放射化されたクラッ
ドが吸込水昇圧ポンプやその付近の配管に付着しやすく
なり、吸込水昇圧ポンプの寿命が短縮する欠点も有す
る。In this case, however, the extraction reactor water passing through the suction water booster pump has a high temperature, so that the activated clad easily adheres to the suction water booster pump and the pipes in the vicinity thereof, so that the suction water booster pump It also has the drawback of shortening the life.

【０００５】一方、再生熱交換器及び非再生熱交換器の
位置が、サプレッションプールと同じ高さの場合には、
冷却水昇圧ポンプは、再生熱交換器及び非再生熱交換器
の下流側に設置される。この場合は、再循環ループと吸
込水昇圧ポンプとの間の揚程を大きくするため、再循環
ループから再生熱交換器の吸込水冷却部、及び非再生熱
交換器を通過して吸込水昇圧ポンプに至るまでの配管
は、下方に向かうように設置され、吸込水昇圧ポンプの
位置はサプレッションプールと同じ高さとなる。なお、
この場合は、吸込水昇圧ポンプは高温とならないので、
上述の場合と比較して損傷を受けにくい。On the other hand, when the positions of the regenerative heat exchanger and the non-regenerative heat exchanger are at the same height as the suppression pool,
The cooling water booster pump is installed downstream of the regenerated heat exchanger and the non-regenerated heat exchanger. In this case, in order to increase the head between the recirculation loop and the suction water booster pump, the suction water booster pump is passed from the recirculation loop through the suction water cooling section of the regenerative heat exchanger and the non-regeneration heat exchanger. The piping up to is installed so as to face downward, and the position of the suction water booster pump is at the same height as the suppression pool. In addition,
In this case, the suction water booster pump does not reach high temperature,
It is less susceptible to damage compared to the above cases.

【０００６】なお、原子炉の停止時でも、通常運転時と
同様に、原子炉の炉心では核分裂生成物の核変換により
崩壊熱が発生するので、崩壊熱を除去するための複数の
残留熱除去系が設けられる。すなわち、残留熱除去系
は、原子炉停止後に発生する燃料の崩壊熱を熱交換器を
用いて除去する系統であり、通常の原子炉の停止時で
は、燃料交換が可能なように、炉水を約５０℃以下の温
度に保持する機能を有する。(日本機械学会編、機械工
学便覧、Ｂ６-１５７、１６３参照)。Even when the nuclear reactor is shut down, as in the normal operation, decay heat is generated in the reactor core due to transmutation of fission products. Therefore, a plurality of residual heat removals for removing decay heat are performed. A system is provided. In other words, the residual heat removal system is a system that removes the decay heat of the fuel generated after the reactor shutdown using a heat exchanger. Has a function of maintaining the temperature at about 50 ° C. or lower. (See The Mechanical Engineering Handbook, edited by The Japan Society of Mechanical Engineers, B6-157, 163).

【０００７】しかし、原子炉の事故が発生し、残留熱除
去系の作動がすべて停止した場合には、崩壊熱により炉
心内の炉水の一部が蒸発し、炉心内の炉水は、炉水の蒸
発により発生する蒸気とともに、原子炉格納容器内の下
部に位置するサプレッションプールに排出される。However, when a nuclear reactor accident occurs and the operation of the residual heat removal system is completely stopped, a part of the reactor water in the core evaporates due to the decay heat, and the reactor water in the core becomes Together with the steam generated by the evaporation of water, it is discharged to the suppression pool located in the lower part of the containment vessel.

【０００８】また、残留熱除去系は、サプレッションプ
ールの冷却も行うようになっているが、残留熱除去系の
作動がすべて停止する事故時には、サプレッションプー
ルの水温が上昇し、発生する蒸気で原子炉格納容器内が
高圧となるので、原子炉格納容器を保護するためのベン
トが設置されている。The residual heat removal system also cools the suppression pool. However, in the event of an accident in which the operation of the residual heat removal system is completely stopped, the water temperature in the suppression pool rises and the generated steam is used for atomization. Since the pressure inside the reactor containment vessel is high, a vent is installed to protect the reactor containment vessel.

【０００９】更に、残留熱除去系は、冷却材喪失事故時
には、サプレッションプール水をポンプにより炉内に注
水する低圧注水系として使用されるとともに、サプレッ
ションプール水を冷却しながら、原子炉格納容器内にス
プレーする機能も有している。Further, the residual heat removal system is used as a low-pressure water injection system for injecting the suppression pool water into the reactor by a pump in the event of loss of the coolant, and while cooling the suppression pool water, it is used in the reactor containment vessel. It also has the function of spraying.

【００１０】なお、特開昭６１−５７８９１号公報及び
特開昭６１−２３１４９２号公報には、関連技術が開示
されている。The related arts are disclosed in JP-A-61-57891 and JP-A-61-231492.

【００１１】特開昭６１−５７８９１号公報の場合は、
残留熱除去系における原子炉停止時の冷却モードの機能
を原子炉冷却材浄化系にもたせるものであり、通常運転
時では、サプレッションプールからの排出水を、原子炉
冷却材浄化系の吸込水昇圧ポンプにより、再生熱交換器
の吸込水冷却部、再生非熱交換器、ろ過脱塩装置、及び
再生熱交換器の吸込水加熱部を順次通過させた後、冷却
材再循環系の循環炉水に合流させ、原子炉圧力容器内に
流入させるようになっている。In the case of JP-A-61-57891,
The function of the cooling mode at the time of reactor shutdown in the residual heat removal system is also given to the reactor coolant purification system, and during normal operation, the discharge water from the suppression pool is boosted by the suction water booster of the reactor coolant purification system. After passing through the suction water cooling part of the regenerative heat exchanger, the regenerative non-heat exchanger, the filter desalting device, and the suction water heating part of the regenerative heat exchanger with the pump, the circulating reactor water of the coolant recirculation system And then flow into the reactor pressure vessel.

【００１２】一方、原子炉事故による原子炉停止時に
は、サプレッションプールからの排出水を、再生熱交換
器の吸込水冷却部、及びろ過脱塩装置を通して、冷却・
浄化し、再生熱交換器の吸込水加熱部のバイパスを通過
させた後、原子炉圧力容器内に戻す配管を介して原子炉
圧力容器内へ流入させるようになっており、また、原子
炉圧力容器内に戻す配管から分岐して設置された原子炉
圧力容器ヘッドスプレイ配管を介して、原子炉圧力容器
ヘッドから原子炉圧力容器内へ注水させることが可能な
構成になっている。On the other hand, when the reactor is shut down due to a reactor accident, the water discharged from the suppression pool is cooled and cooled through the suction water cooling section of the regenerative heat exchanger and the filter desalting device.
After purifying and passing through the bypass of the suction water heating part of the regenerative heat exchanger, it is made to flow into the reactor pressure vessel through the pipe returning to the inside of the reactor pressure vessel. Water is injected from the reactor pressure vessel head into the reactor pressure vessel through a reactor pressure vessel head spray pipe that is installed branching from a pipe returning to the inside of the vessel.

【００１３】また、特開昭６１−２３１４９２号公報の
場合は、原子炉冷却材浄化系の非再生熱交換器に、残留
熱除去系の熱交換器を兼用させたものであり、残留熱除
去系が２系統あり、その中の１系統には熱交換器を設置
しておらず、原子炉冷却材浄化系の非再生熱交換器を利
用して、通常運転時には原子炉圧力容器内の炉水を浄化
・冷却し、原子炉事故による原子炉停止時には、サプレ
ッションプールからの排出水を冷却するようになってい
る。Further, in the case of Japanese Patent Laid-Open No. 61-231492, the non-regenerative heat exchanger of the reactor coolant purification system is also used as the heat exchanger of the residual heat removal system. There are two systems, one of which does not have a heat exchanger installed, and the non-regenerative heat exchanger of the reactor coolant purification system is used to operate the reactor in the reactor pressure vessel during normal operation. It purifies and cools water, and cools the water discharged from the suppression pool when the reactor is shut down due to a reactor accident.

【００１４】[0014]

【発明が解決しようとする課題】しかし、特開昭６１−
５７８９１号公報の場合は、原子炉冷却材浄化系は、原
子炉の通常運転時、サプレッションプールからの排出水
を冷却・浄化するようになっており、再循環系の炉水の
浄化を目的としていない。また、原子炉の停止時におい
ても、サプレッションプールからの排出水は、ろ過脱塩
装置内を通過するようになっているので、ろ過脱塩装置
内の流路抵抗により、残留熱除去系としての効率は低下
することが予想される。However, JP-A-61-161
In the case of Japanese Patent No. 57891, the reactor coolant purification system is designed to cool and purify the discharge water from the suppression pool during normal operation of the reactor, and for the purpose of purifying the reactor water of the recirculation system. Not in. Further, even when the reactor is shut down, the discharge water from the suppression pool passes through the inside of the filter desalination apparatus, so that the residual heat removal system as a residual heat removal system is generated due to the flow path resistance inside the filter desalination apparatus. Efficiency is expected to decrease.

【００１５】一方、特開昭６１−２３１４９２号公報の
場合は、原子炉事故による原子炉停止時、サプレッショ
ンプールからの排出水の冷却に際して、この排出水を再
生熱交換器の吸込水冷却部を通過させておらず、また、
この排出水を流入させる箇所はサプレッションプールで
あり、原子炉圧力容器内に直接、注水する構成にはなっ
ていない。したがって、原子炉事故対策として、大きな
効果の期待できないことが懸念される。On the other hand, in the case of Japanese Patent Laid-Open No. 61-231492, at the time of reactor shutdown due to a reactor accident, when cooling the discharge water from the suppression pool, this discharge water is supplied to the suction water cooling section of the regenerative heat exchanger. I did not let it pass through,
The place where this discharged water flows is the suppression pool, and it is not designed to inject water directly into the reactor pressure vessel. Therefore, it is feared that a great effect cannot be expected as a countermeasure for a nuclear reactor accident.

【００１６】また、上述の２つの公知例とも、原子炉冷
却材浄化系を原子炉残留熱除去系へ確実に変更するため
のインターロックについては、開示されていない。Further, neither of the above-mentioned two known examples discloses an interlock for surely changing the reactor coolant purification system to the reactor residual heat removal system.

【００１７】本発明の目的は、原子炉冷却材浄化系の吸
込水昇圧ポンプが、再生熱交換器の吸込水冷却部、及び
非再生熱交換器の上流側及び下流側のいずれに設置され
た場合であっても、残留熱除去系の停止時において、原
子炉格納容器内に蓄積された崩壊熱の除去を確実に行う
ことができる手段を提供することである。An object of the present invention is to install a suction water booster pump for a reactor coolant purification system either on the suction water cooling section of a regenerative heat exchanger or on the upstream or downstream side of a non-regenerative heat exchanger. Even in such a case, it is an object of the present invention to provide a means capable of reliably removing the decay heat accumulated in the containment vessel when the residual heat removal system is stopped.

【００１８】[0018]

【課題を解決するための手段】上記目的は、次のように
して達成することができる。The above object can be achieved as follows.

【００１９】（１）原子炉格納容器内に発生した崩壊熱
を除去する残留熱除去系、並びに原子炉圧力容器に接続
する再循環ループ、再循環ループからの抽出炉水を昇圧
する吸込水昇圧ポンプ、抽出炉水の冷却部と加熱部とを
有する再生熱交換器、抽出炉水を冷却する非再生熱交換
器、抽出炉水を浄化するろ過脱塩器、抽出炉水を吸込水
昇圧ポンプに吸い込ませる抽出炉水配管、吸込水昇圧ポ
ンプと再生熱交換器の吸込水冷却部と非再生熱交換器と
ろ過脱塩器と再生熱交換器の吸込水加熱部とを順次接続
する配管、再生熱交換器の吸込水加熱部と原子炉格納容
器へ外部から給水する給水配管とを接続する配管、及び
抽出炉水配管に付設している抽出配管用電動弁からな
り、吸込水昇圧ポンプが原子炉格納容器内のサプレッシ
ョンプールよりも高く位置している状態の原子炉冷却材
浄化系を有する原子炉における原子炉格納容器除熱装置
において、抽出炉水配管における吸込水昇圧ポンプと抽
出配管用電動弁との間のいずれかの箇所とサプレッショ
ンプールとを接続する第１の配管、ろ過脱塩器をバイパ
スする第２の配管、及び再生熱交換器の吸込水加熱部を
バイパスする第３の配管を備え、第１の配管にサプレッ
ションプールからの排出水を昇圧する排出水昇圧ポン
プ、第１の配管における排出水昇圧ポンプの一方側に第
１の電動弁、他方側に第２の電動弁、第２の配管に第３
の電動弁、及び第３の配管に第４の電動弁をそれぞれ設
けていること。(1) A residual heat removal system for removing decay heat generated in the reactor containment vessel, a recirculation loop connected to the reactor pressure vessel, and suction water boosting for boosting extraction reactor water from the recirculation loop A pump, a regenerative heat exchanger having a cooling unit and a heating unit for the extraction reactor water, a non-regeneration heat exchanger for cooling the extraction reactor water, a filter desalting device for purifying the extraction reactor water, and a suction water booster pump for the extraction reactor water. Extraction reactor water piping to be sucked into, suction water booster pump, suction water cooling section of regenerative heat exchanger, non-regeneration heat exchanger, filtration desalinator, and piping for sequentially connecting suction water heating section of regenerative heat exchanger, The suction water booster pump consists of a pipe that connects the suction water heating part of the regenerative heat exchanger and the water supply pipe that supplies water to the reactor containment vessel from the outside, and the extraction pipe motor valve that is attached to the extraction reactor water pipe. Higher than the suppression pool in the containment vessel In a reactor containment heat removal apparatus in a reactor having a reactor coolant purification system in a state of being located, any place between the suction water booster pump and the extraction pipe electric valve in the extraction reactor water pipe and A first pipe connecting to the suppression pool, a second pipe bypassing the filter / desalting unit, and a third pipe bypassing the suction water heating unit of the regenerative heat exchanger are provided, and the first pool is the suppression pool. Discharge water booster pump for boosting the discharge water from the pump, a first electric valve on one side of the discharge water booster pump in the first pipe, a second electric valve on the other side, and a third pipe on the second pipe.
The fourth motorized valve is provided on the third motorized valve and the third motorized valve.

【００２０】（２）原子炉格納容器内に発生した崩壊熱
を除去する残留熱除去系、並びに原子炉圧力容器に接続
する再循環ループ、再循環ループからの抽出炉水を昇圧
する吸込水昇圧ポンプ、抽出炉水の冷却部と加熱部とを
有する再生熱交換器、抽出炉水を冷却する非再生熱交換
器、抽出炉水を浄化するろ過脱塩器、抽出炉水を再生熱
交換器の冷却部と非再生熱交換器とを通して吸込水昇圧
ポンプに吸い込ませる抽出炉水配管、吸込水昇圧ポンプ
とろ過脱塩器と再生熱交換器の吸込水加熱部とを接続す
る配管、再生熱交換器の吸込水加熱部と原子炉格納容器
へ外部から給水する給水配管とを接続する配管、及び抽
出配管に付設している抽出配管用電動弁からなり、吸込
水昇圧ポンプが原子炉格納容器内のサプレッションプー
ルと同じ高さに位置している状態の原子炉冷却材浄化系
を有する原子炉における原子炉格納容器除熱装置におい
て、抽出炉水配管における吸込水昇圧ポンプと非再生熱
交換器との間のいずれかの箇所とサプレッションプール
とを接続する第１の配管、ろ過脱塩器をバイパスする第
２の配管、及び再生熱交換器の吸込水加熱部をバイパス
する第３の配管、サプレッションプールからの排出水を
吸込水昇圧ポンプを介して非再生熱交換器に通す配管、
及び非再生熱交換器における吸込水排出側配管と、ろ過
脱塩器と再生熱交換器の加熱部とを接続する配管におけ
るろ過脱塩器の側の部分とを接続する配管を備え、第１
の配管に第１の電動弁と第２の電動弁、第２の配管に第
３の電動弁、及び第３の配管に第４の電動弁をそれぞれ
設けていること。(2) Residual heat removal system for removing decay heat generated in the reactor containment vessel, a recirculation loop connected to the reactor pressure vessel, and suction water boosting for boosting extraction reactor water from the recirculation loop A pump, a regenerative heat exchanger having a cooling unit and a heating unit for the extraction reactor water, a non-regeneration heat exchanger for cooling the extraction reactor water, a filter desalting device for purifying the extraction reactor water, a regeneration heat exchanger for the extraction reactor water. Extraction reactor water piping that is sucked into the suction water booster pump through the cooling unit and the non-regeneration heat exchanger, the piping that connects the suction water booster pump, the filter desalination unit, and the suction water heating unit of the regenerative heat exchanger, the regeneration heat The suction water booster pump consists of a pipe that connects the suction water heating part of the exchanger and the water supply pipe that supplies water to the reactor containment vessel from the outside, and an extraction pipe electric valve attached to the extraction pipe. Located at the same height as the suppression pool inside In a reactor containment vessel heat removal apparatus in a reactor having a reactor coolant purification system in an operating state, suppression and any place between the suction water booster pump and the non-regenerative heat exchanger in the extraction reactor water piping A first pipe for connecting to the pool, a second pipe for bypassing the filter / desalting device, a third pipe for bypassing the suction water heating part of the regenerative heat exchanger, and a suction water booster for the discharge water from the suppression pool. Piping to the non-regenerative heat exchanger through the pump,
And a pipe for connecting a suction water discharge side pipe in the non-regeneration heat exchanger and a part of the pipe connecting the filtration demineralizer and the heating part of the regenerative heat exchanger on the side of the filter demineralizer,
The first electric valve and the second electric valve are provided in the pipe, the third electric valve is provided in the second pipe, and the fourth electric valve is provided in the third pipe.

【００２１】（３）（１）において、残留熱除去系の故
障を指示する信号と原子炉冷却材浄化系の停止を指示す
る信号とが発信された非常時発生の際、遠隔操作により
自動的に、抽出配管用電動弁が閉に、第３の電動弁、及
び第４の電動弁が開にそれぞれ作動し、この作動の完了
信号により、第１の電動弁、及び第２の電動弁がそれぞ
れ開に作動し、この作動の完了信号により、吸込水昇圧
ポンプ及び排出水昇圧ポンプがそれぞれ起動し、原子炉
冷却材浄化系の機能が原子炉格納容器の崩壊熱除去系に
切り替わること。(3) In (1), when an emergency occurs in which a signal indicating a failure of the residual heat removal system and a signal indicating a stop of the reactor coolant purification system are transmitted, it is automatically operated by remote control. Then, the extraction pipe motor-operated valve is closed and the third motor-operated valve and the fourth motor-operated valve are opened, and the first motor-operated valve and the second motor-operated valve are activated by the completion signal of the operation. Each of them operates in the open state, and by the completion signal of this operation, the suction water booster pump and the discharge water booster pump are activated respectively, and the function of the reactor coolant purification system is switched to the decay heat removal system of the reactor containment vessel.

【００２２】（４）（２）において、残留熱除去系の故
障を指示する信号と原子炉冷却材浄化系の停止を指示す
る信号とが発信された非常時発生の際、遠隔操作により
自動的に、抽出配管用電動弁が閉に、第３の電動弁、及
び第４の電動弁が開にそれぞれ作動し、この作業の完了
信号により、第１の電動弁、及び第２の電動弁がそれぞ
れ開に作動し、この作動の完了信号により、吸込水昇圧
ポンプが起動し、原子炉冷却材浄化系の機能が原子炉格
納容器の崩壊熱除去系に切り替わること。(4) In (2), in the event of an emergency in which a signal indicating a failure of the residual heat removal system and a signal indicating a stop of the reactor coolant purification system are transmitted, it is automatically operated by remote control. Then, the extraction pipe electric valve is closed and the third electric valve and the fourth electric valve are opened, and the first electric valve and the second electric valve are activated by the completion signal of this work. Each of them operates in the open state, and the suction water booster pump is activated by the completion signal of this operation, and the function of the reactor coolant purification system is switched to the decay heat removal system of the reactor containment vessel.

【００２３】（５）（３）又は（４）において、非常時
発生の際、運転員手動スイッチＯＮの許可信号により、
運転員の判断で、原子炉冷却材浄化系の機能を原子炉格
納容器の崩壊熱除去系に切り替える手動スイッチを設け
ていること。(5) In (3) or (4), when an emergency occurs, the operator's manual switch ON permission signal causes
A manual switch that switches the function of the reactor coolant purification system to the decay heat removal system of the reactor containment vessel shall be provided at the operator's discretion.

【００２４】[0024]

【作用】原子炉冷却材浄化系の機能は、原子炉停止時に
は停止する。すなわち、この場合は、原子炉冷却材浄化
系の熱交換器、すなわち再生熱交換器及び非再生熱交換
器は使用されず、余分な設備となる。[Function] The function of the reactor coolant purification system is stopped when the reactor is stopped. That is, in this case, the heat exchanger of the reactor coolant purification system, that is, the regenerated heat exchanger and the non-regenerated heat exchanger, is not used and becomes an extra facility.

【００２５】本発明は、このように原子炉停止時に使用
されなくなる原子炉冷却材浄化系の熱交換器の有効利用
を図り、原子炉の残留熱除去系が故障などによって作動
しない場合に、原子炉冷却材浄化系を原子炉格納容器除
熱装置として機能させるものである。例えば、この原子
炉格納容器除熱装置を、既存の原子炉冷却材浄化系に適
用する場合は、原子炉冷却材浄化系の追加設備を設ける
ことで構成される。The present invention thus aims to effectively utilize the heat exchanger of the reactor coolant purification system which is not used when the reactor is shut down, and when the residual heat removal system of the reactor does not operate due to a failure, etc. The reactor coolant purification system functions as a heat removal device for the reactor containment vessel. For example, in the case of applying this reactor containment vessel heat removal apparatus to an existing reactor coolant purification system, it is configured by providing additional equipment for the reactor coolant purification system.

【００２６】追加設備は、原子炉冷却材浄化系の構成に
よって異なり、再生熱交換器の吸込水冷却部、及び非再
生熱交換器のサプレッションプールに対する相対高さに
より分類される。すなわち、再生熱交換器の吸込水冷却
部、及び非再生熱交換器が、サプレッションプールより
も高い位置に設けられている場合は、原子炉冷却材浄化
系の吸込水昇圧ポンプは、再生熱交換器の吸込水冷却
部、及び非再生熱交換器の上流側に設置される。The additional equipment depends on the structure of the reactor coolant purification system and is classified by the relative height of the suction water cooling part of the regenerative heat exchanger and the suppression pool of the non-regenerative heat exchanger. That is, when the suction water cooling part of the regenerative heat exchanger and the non-regeneration heat exchanger are provided at a position higher than the suppression pool, the suction water booster pump of the reactor coolant purification system is regenerated heat exchange. It is installed on the upstream side of the suction water cooling section of the reactor and the non-regenerative heat exchanger.

【００２７】一方、再生熱交換器の吸込水冷却部、及び
非再生熱交換器が、サプレッションプールと同じ高さに
設置されている場合は、原子炉冷却材浄化系の吸込水昇
圧ポンプは、再生熱交換器の吸込水冷却部、及び非再生
熱交換器の下流側に設置される。On the other hand, when the suction water cooling section of the regenerative heat exchanger and the non-regeneration heat exchanger are installed at the same height as the suppression pool, the suction water booster pump of the reactor coolant purification system is It is installed downstream of the suction water cooling part of the regenerative heat exchanger and the non-regenerative heat exchanger.

【００２８】また、吸込水昇圧ポンプが再生熱交換器の
吸込水冷却部、及び非再生熱交換器の上流側と下流側と
のいずれに設置されるかの位置関係によって、サプレッ
ションプールの排出水を送り込む形態、再生熱交換器と
非再生熱交換器の利用方法、及びインターロックを異に
する。Further, depending on the positional relationship of whether the suction water booster pump is installed in the suction water cooling section of the regenerative heat exchanger or on the upstream side or the downstream side of the non-regeneration heat exchanger, the discharge water of the suppression pool is discharged. The method of feeding the heat exchanger, the method of using the regenerated heat exchanger and the non-regenerated heat exchanger, and the interlock are different.

【００２９】まず、吸込水昇圧ポンプが、再生熱交換器
の吸込水冷却部、及び非再生熱交換器の上流側に設置さ
れている場合の作用について説明する。First, the operation when the suction water booster pump is installed on the suction water cooling section of the regenerative heat exchanger and on the upstream side of the non-regeneration heat exchanger will be described.

【００３０】この場合、本発明では、通常運転時には、
再循環ループからの抽出炉水は、再生熱交換器の吸込水
冷却部、非再生熱交換器、ろ過脱塩器、及び再生熱交換
器の吸込水加熱部を順次通過して浄化され、かつ適度な
温度に保持された状態で、原子炉圧力容器内に給水する
給水配管に送水され、原子炉圧力容器内に戻されるよう
にしている。すなわち、このように、吸込水昇圧ポンプ
を、再生熱交換器の吸込水冷却部、及び非再生熱交換器
の上流側に設置するので、吸込水昇圧ポンプにおける吸
込水の吸込効率向上を図ることができる。In this case, according to the present invention, during normal operation,
The extraction reactor water from the recirculation loop is sequentially purified by passing through the suction water cooling section of the regenerative heat exchanger, the non-regeneration heat exchanger, the filter desalting unit, and the suction water heating section of the regenerative heat exchanger, and While being kept at an appropriate temperature, water is supplied to a water supply pipe for supplying water into the reactor pressure vessel and returned to the inside of the reactor pressure vessel. That is, since the suction water booster pump is installed in the suction water cooling section of the regenerative heat exchanger and the upstream side of the non-regeneration heat exchanger in this way, it is possible to improve the suction efficiency of the suction water in the suction water booster pump. You can

【００３１】一方、非常時では、サプレッションプール
からの排出水は、ろ過脱塩器、及び再生熱交換器の吸込
水加熱部をバイパスして、再生熱交換器の吸込水冷却
部、及び非再生熱交換器のみを通過することにより、大
きく冷却された状態で、原子炉圧力容器内に給水する給
水配管を介して原子炉圧力容器内に注水されるようにし
ている。したがって、原子炉圧力容器内に発生した崩壊
熱を有効に除去することができる。On the other hand, in an emergency, the discharge water from the suppression pool bypasses the suction dewatering unit and the suction water heating unit of the regenerating heat exchanger, and the suction water cooling unit of the regenerating heat exchanger and the non-regenerating unit. By passing only the heat exchanger, water is poured into the reactor pressure vessel through a water supply pipe for supplying water into the reactor pressure vessel in a greatly cooled state. Therefore, the decay heat generated in the reactor pressure vessel can be effectively removed.

【００３２】しかし、上述のように、吸込水昇圧ポンプ
を再生熱交換器の吸込水冷却部、及び非再生熱交換器の
上流側に設置する場合は、吸込水昇圧ポンプを通過する
抽出炉水が高温となり、放射化されたクラッドが吸込水
昇圧ポンプやその付近の配管に付着しやすくなるので、
吸込水昇圧ポンプの寿命が短縮される欠点を有する。However, as described above, when the suction water booster pump is installed in the suction water cooling section of the regenerative heat exchanger and upstream of the non-regenerative heat exchanger, the extraction reactor water passing through the suction water booster pump is used. Becomes hot and the activated clad easily adheres to the suction water booster pump and the pipes in the vicinity,
It has a drawback that the life of the suction water booster pump is shortened.

【００３３】次に、吸込水昇圧ポンプの位置がサプレッ
ションプールと同じ高さの場合について説明する。この
場合は、吸込水昇圧ポンプを、再生熱交換器、及び非再
生熱交換器の下流側に設置する。したがって、吸込水昇
圧ポンプを通過する抽出炉水は高温とならないので、吸
込水昇圧ポンプの損傷が少なく、また、サプレッション
プールの排出水を昇圧する排出水昇圧ポンプの設置を必
要としない。Next, the case where the position of the suction water booster pump is at the same height as the suppression pool will be described. In this case, the suction water booster pump is installed downstream of the regenerative heat exchanger and the non-regenerative heat exchanger. Therefore, since the extraction reactor water that passes through the suction water booster pump does not reach a high temperature, damage to the suction water booster pump is small, and it is not necessary to install a discharge water booster pump that boosts the discharge water of the suppression pool.

【００３４】この場合、本発明では、再循環ループから
の抽出炉水は、通常運転時には、再生熱交換器の吸込水
冷却部、及び非再生熱交換器を自然落下の状態で冷却さ
れながら通過して、吸込水昇圧ポンプの位置まで流下
し、次いで、吸込水昇圧ポンプにより、ろ過脱塩器、及
び再生熱交換器の吸込水加熱部を通って、浄化され、か
つ適度な温度に保持された状態で、原子炉圧力容器内に
給水する給水配管に送水され、原子炉圧力容器内に戻さ
れるようにしている。In this case, in the present invention, the extraction reactor water from the recirculation loop passes through the suction water cooling section of the regenerative heat exchanger and the non-regenerative heat exchanger while being cooled in a natural fall state during normal operation. Then, it is made to flow down to the position of the suction water booster pump, and then it is purified by the suction water booster pump, passes through the suction water heating part of the recycle heat exchanger, and is maintained at an appropriate temperature. In this state, water is supplied to a water supply pipe for supplying water into the reactor pressure vessel and returned to the inside of the reactor pressure vessel.

【００３５】一方、非常時には、サプレッションプール
からの排出水は、吸込水昇圧ポンプにより、非再生熱交
換器を通って、大きく冷却された後、原子炉圧力容器内
に給水する給水配管を介して原子炉圧力容器内に注水さ
れるようにしている。したがって、原子炉圧力容器内に
発生した崩壊熱を有効に除去することができる。すなわ
ち、この場合、サプレッションプールからの排出水は、
ろ過脱塩器、及び再生熱交換器の吸込水加熱部を通過し
ないので、サプレッションプールからの排出水の流動抵
抗は少なく、崩壊熱の除去効果が大きい。On the other hand, in an emergency, the discharge water from the suppression pool passes through the non-regeneration heat exchanger by the suction water booster pump, is greatly cooled, and then is supplied through the water supply pipe for supplying water into the reactor pressure vessel. Water is poured into the reactor pressure vessel. Therefore, the decay heat generated in the reactor pressure vessel can be effectively removed. That is, in this case, the discharge water from the suppression pool is
Since it does not pass through the filtration desalination unit and the suction water heating unit of the regenerative heat exchanger, the flow resistance of the discharge water from the suppression pool is small and the effect of removing decay heat is large.

【００３６】原子炉冷却材浄化系の原子炉原子炉格納容
器除熱装置への変換を必要とする事態としては、残留熱
除去系の故障による事故があげられるが、この場合、本
発明では次の変換方法を使用している。A situation that requires conversion of the reactor coolant purification system into a reactor containment vessel heat removal device is an accident due to a failure of the residual heat removal system. Using the conversion method of.

【００３７】各所の配管に付設している電動弁を適宜、
開閉することにより、非常時モードのラインを確保し、
この開閉作業の完了指示信号により、サプレッションプ
ールと原子炉冷却材浄化系を結ぶ配管上にある２つの電
動弁を開にし、その後、原子炉冷却材浄化系の吸込水昇
圧ポンプを起動させている。これによって、サプレッシ
ョンプールからの排出水が冷却され、この冷却された排
出水が、原子炉原子炉格納容器内に注水される。すなわ
ち、通常運転時には原子炉冷却材浄化系である系統が、
非常時には原子炉格納容器除熱装置に変換されることに
なる。Electric valves attached to pipes at various places are appropriately
By opening and closing, secure the emergency mode line,
By the completion instruction signal of this opening / closing work, the two electric valves on the pipe connecting the suppression pool and the reactor coolant purification system are opened, and then the suction water booster pump of the reactor coolant purification system is started. . As a result, the discharge water from the suppression pool is cooled, and the cooled discharge water is injected into the reactor containment vessel. That is, the system that is the reactor coolant purification system during normal operation is
In an emergency, it will be converted to a heat removal device for the PCV.

【００３８】排出水昇圧ポンプを設置している場合は、
吸込水昇圧ポンプと同時に、排出水昇圧ポンプを起動さ
せている。なお、電動弁の開閉は、事故時に行われる可
能性が高いので、電動弁は、遠隔操作により自動的に作
動するようにしている。If a discharge water booster pump is installed,
The discharge water booster pump is started at the same time as the suction water booster pump. Since it is highly likely that the motor-operated valve will be opened and closed in the event of an accident, the motor-operated valve is automatically operated by remote control.

【００３９】上述のような、本発明における設備を、既
設のプラントでは追加し、新設のプラントでは最初から
取り入れることにより、残留熱除去系が故障した場合、
サプレッションプールからの排出水を冷却し、この冷却
した排出水を原子炉格納容器内に注水するので、原子炉
格納容器内の崩壊熱の除去を効果的に行うことができ
る。In the case where the residual heat removal system fails by adding the above-mentioned equipment in the present invention to the existing plant and incorporating it from the beginning in the new plant,
Since the discharged water from the suppression pool is cooled and the cooled discharged water is injected into the reactor containment vessel, the decay heat in the reactor containment vessel can be effectively removed.

【００４０】すなわち、本発明における設備を、上述の
ように追加又は取り入れることにより、余分な設備を有
効利用することができ、軽微な改善で残留熱除去系の多
重性を１つ多く持つことが可能となる。すなわち、既設
の原子力プラントでは、原子炉冷却材浄化系の熱交換器
の容量は小さいが、少しでも崩壊熱を除去し、事故の拡
大を遅らせることができる。That is, by adding or incorporating the equipment according to the present invention as described above, it is possible to effectively use the extra equipment, and it is possible to improve the residual heat removal system by one more by a slight improvement. It will be possible. That is, in the existing nuclear power plant, although the capacity of the heat exchanger of the reactor coolant purification system is small, it is possible to remove decay heat as much as possible and delay the expansion of the accident.

【００４１】また、原子炉の停止後、長時間経過した時
点で残留熱除去系が故障した場合には、崩壊熱レベルが
下がるので、崩壊熱を十分に除去することができ、残留
熱除去系の代替を務めることが可能となる。Further, if the residual heat removal system fails after a long time has elapsed after the reactor is shut down, the decay heat level is lowered, so that the decay heat can be sufficiently removed. It becomes possible to serve as an alternative.

【００４２】更に、原子炉冷却材浄化系の熱交換器を利
用し、冷却水を炉心や原子炉格納容器へ供給できるよう
になるので、既設や新設の原子力プラントにおいて容易
に残留熱除去系を多重化することができ、低コストで安
全性の高い沸騰水型原子炉を提供することができる。Furthermore, since the cooling water can be supplied to the core and the reactor containment vessel by utilizing the heat exchanger of the reactor coolant purification system, the residual heat removal system can be easily installed in the existing or newly installed nuclear power plant. It is possible to provide a boiling water nuclear reactor that can be multiplexed and that is low in cost and high in safety.

【００４３】[0043]

【実施例】本発明の第１実施例を、図１を用いて説明す
る。図１は本実施例の原子炉格納容器除熱装置の系統図
であり、沸騰水型原子炉において、原子炉冷却材浄化系
を利用して、原子炉格納容器内に発生した崩壊熱を確実
に除去する機能を示している。EXAMPLE A first example of the present invention will be described with reference to FIG. FIG. 1 is a system diagram of the reactor containment heat removal apparatus of the present embodiment. In a boiling water reactor, the decay heat generated in the reactor containment vessel is ensured by using the reactor coolant purification system. Shows the function to be removed.

【００４４】沸騰水型原子炉の原子炉格納容器１には、
原子炉圧力容器２が内蔵され、原子炉格納容器１内の上
部はドライウェル３、下部はサプレッションプール４と
なっている。また、原子炉圧力容器２内の炉水の一部
を、原子炉圧力容器２の下部から外部に流出させ、その
後、それよりも上部から原子炉圧力容器２内に流入させ
る再循環ループ５が設けられている。なお、残留熱除去
系の記載は、省略している。In the reactor containment vessel 1 of the boiling water reactor,
The reactor pressure vessel 2 is built in, and the upper part of the reactor containment vessel 1 is a dry well 3 and the lower part is a suppression pool 4. Further, there is a recirculation loop 5 that causes a part of the reactor water in the reactor pressure vessel 2 to flow out from the lower portion of the reactor pressure vessel 2 to the outside and then to flow into the reactor pressure vessel 2 from above. It is provided. The description of the residual heat removal system is omitted.

【００４５】原子炉冷却材浄化系は、通常運転時、再循
環ループ５から炉水を一部抽出して、冷却・浄化した後
に、原子炉圧力容器２内に戻すものであり、次のような
構成になっている。再循環ループ５からの抽出炉水を、
抽出炉水配管１１及び配管１２に流して、再生熱交換器
吸込水冷却部７及び非再生熱交換器９を通して冷却した
後、ろ過脱塩器１０を通して浄化し、次いで再生熱交換
器吸込水加熱部８を通して適温にした後、給水配管１３
内に送水し、原子炉圧力容器２内に戻すようになってい
る。すなわち、再生熱交換器６には、吸込水を冷却する
再生熱交換器吸込水冷却部７と、吸込水を加熱する再生
熱交換器吸込水加熱部８とを有している。During normal operation, the reactor coolant purification system extracts a part of the reactor water from the recirculation loop 5, cools and purifies it, and then returns it to the reactor pressure vessel 2. It has a simple structure. Extractor water from the recirculation loop 5
After flowing through the extraction reactor water pipe 11 and the pipe 12 and cooling through the regenerator heat exchanger suction water cooling unit 7 and the non-regenerator heat exchanger 9, it is purified through the filter desalting unit 10 and then regenerator heat exchanger suction water heating After making the temperature appropriate through the section 8, the water supply pipe 13
Water is supplied into the reactor pressure vessel 2 and returned into the reactor pressure vessel 2. That is, the regenerative heat exchanger 6 has a regenerative heat exchanger suction water cooling unit 7 that cools the suction water, and a regenerative heat exchanger suction water heating unit 8 that heats the suction water.

【００４６】このような構成になる原子炉冷却材浄化系
において、原子炉プラントの構成上、再生熱交換器吸込
水冷却部７及び非再生熱交換器９を、サプレッションプ
ール４よりも高い位置に設けている場合があるが、本実
施例は、そのような場合に対して、本発明の原子炉格納
容器除熱装置を適用した例である。すなわち、本実施例
は、吸込水昇圧ポンプ１４を、通常運転時における抽出
炉水の流れ方向からみて、再生熱交換器吸込水冷却部７
及び非再生熱交換器９の上流側に設置した場合である。In the reactor coolant purifying system having such a structure, the regenerator heat exchanger suction water cooling unit 7 and the non-regenerator heat exchanger 9 are located higher than the suppression pool 4 due to the structure of the reactor plant. Although it may be provided, this embodiment is an example in which the reactor containment heat removal apparatus of the present invention is applied to such a case. That is, in the present embodiment, the suction water booster pump 14 is viewed from the flow direction of the extraction reactor water during normal operation, and the suction heat water cooling unit 7 for the regenerative heat exchanger is
And the case where it is installed on the upstream side of the non-regenerative heat exchanger 9.

【００４７】本実施例では、上述の原子炉冷却材浄化系
に、次の設備を追加することにより、原子炉格納容器除
熱装置を構成させ、残留熱除去系の事故時において原子
炉格納容器１内に発生する崩壊熱を除去している。In the present embodiment, a reactor containment vessel heat removal apparatus is constructed by adding the following equipment to the above-mentioned reactor coolant purification system, and the reactor containment vessel is contained in the event of an accident in the residual heat removal system. The decay heat generated in 1 is removed.

【００４８】すなわち、抽出炉水配管１１とサプレッシ
ョンプール４とを接続する配管１６を設け、配管１６に
排出水昇圧ポンプ１９を付設し、配管１６における排出
水昇圧ポンプ１９の一方側に電動弁２０、他方側に電動
弁２１を、それぞれ取り付け、高圧系の原子炉冷却材浄
化系と低圧系のサプレッションプール４とが隔離できる
ようにしている。That is, a pipe 16 for connecting the extraction reactor water pipe 11 and the suppression pool 4 is provided, an exhaust water booster pump 19 is attached to the pipe 16, and the motor-operated valve 20 is provided on one side of the exhaust water booster pump 19 in the pipe 16. The electric valves 21 are attached to the other side so that the high pressure system reactor coolant purification system and the low pressure system suppression pool 4 can be isolated from each other.

【００４９】また、ろ過脱塩器バイパス配管１７及び再
生熱交換器吸込水加熱部バイパス配管１８を設け、前者
には電動弁２２、後者には電動弁２３を付設している。
更に、ろ過脱塩器１０と再生熱交換器吸込水加熱部８と
を接続する配管１２部には、電動弁２４を付設してい
る。Further, a filter desalting device bypass pipe 17 and a regenerative heat exchanger suction water heating part bypass pipe 18 are provided, an electric valve 22 is attached to the former, and an electric valve 23 is attached to the latter.
Further, a motor-operated valve 24 is attached to a pipe 12 portion connecting the filter desalting device 10 and the regenerative heat exchanger suction water heating portion 8.

【００５０】以上のような構成において、非常時には、
電動弁１５及び２４を閉じ、電動弁２０〜２３を開き、
排出水昇圧ポンプ１９及び吸込水昇圧ポンプ１４を起動
させている。それによって、サプレッションプール４か
らの排出水を、排出水昇圧ポンプ１９により昇圧し、吸
込水昇圧ポンプ１４へ送った後、再生熱交換器吸込水冷
却部７と非再生熱交換器９とを通過させ、冷却してい
る。次いで、ろ過脱塩器バイパス配管１７、及び再生熱
交換器吸込水加熱部バイパス配管１８を通過させた後に
給水配管１３へ送り、原子炉圧力容器２内に注水して、
炉心を冷却し、崩壊熱を除去している。そして、原子炉
圧力容器２から流出する冷却材とともに、原子炉格納容
器１内を冷却し、更に、サプレッションプール４へ戻る
ようにしている。In the above structure, in an emergency,
Close the motor operated valves 15 and 24, open the motor operated valves 20-23,
The discharge water booster pump 19 and the suction water booster pump 14 are activated. As a result, the discharge water from the suppression pool 4 is boosted by the discharge water booster pump 19, sent to the suction water booster pump 14, and then passes through the regenerative heat exchanger suction water cooling unit 7 and the non-regenerative heat exchanger 9. Let it cool. Then, after passing through the filter demineralizer bypass pipe 17 and the regenerative heat exchanger suction water heating part bypass pipe 18, it is sent to the water supply pipe 13 to inject water into the reactor pressure vessel 2.
The core is cooled to remove decay heat. Then, the inside of the reactor containment vessel 1 is cooled together with the coolant flowing out from the reactor pressure vessel 2, and is further returned to the suppression pool 4.

【００５１】この場合、サプレッションプール４からの
排出水は、ろ過脱塩器１０及び再生熱交換器吸込水加熱
部８を通過しないので、その分だけ流動抵抗が減少す
る。すなわち、原子炉圧力容器２内への注水量が多くな
るので、崩壊熱を除去に大きな効果を得られる。In this case, the discharge water from the suppression pool 4 does not pass through the filter desalting unit 10 and the regenerated heat exchanger suction water heating unit 8, so that the flow resistance is reduced accordingly. That is, since the amount of water injected into the reactor pressure vessel 2 is large, a great effect can be obtained in removing the decay heat.

【００５２】また、本実施例では、原子炉冷却材浄化系
を確実に原子炉原子炉格納容器除熱装置に変換するた
め、インターロックにも特徴を持たせている。Further, in this embodiment, the interlock is also characterized in order to reliably convert the reactor coolant purification system into the reactor containment vessel heat removal device.

【００５３】原子炉プラントでは、ドライウェル圧力高
信号や温度高信号により、残留熱除去系の起動信号が出
る。しかし、その後もドライウェル圧力高信号や温度高
信号が出る場合は、残留熱除去系は起動していないこと
になる。この場合、本実施例では、停止している原子炉
冷却材浄化系を原子炉原子炉格納容器除熱装置に変換す
るための信号を出し、この信号により、自動的に変換作
業を開始させている。In the nuclear reactor plant, the start signal of the residual heat removal system is output by the dry well pressure high signal and the high temperature signal. However, if a high drywell pressure signal or a high temperature signal is output after that, it means that the residual heat removal system has not been activated. In this case, in this embodiment, a signal for converting the stopped reactor coolant purification system to the reactor reactor containment heat removal device is issued, and the conversion work is automatically started by this signal. There is.

【００５４】まず、通常運転時には開の電動弁１５が閉
になっていることの確認信号により、ろ過脱塩器バイパ
ス配管１７の電動弁２２と再生熱交換器吸込水加熱部バ
イパス配管１８の電動弁２３とが開、ろ過脱塩器１０と
再生熱交換器吸込水加熱部８との接続部の配管１２の電
動弁２４が閉になる。このような電動弁の開閉により、
原子炉冷却材浄化系の熱交換器利用ライン確保の信号が
出る。First, in normal operation, the motor-operated valve 22 of the filter desalting device bypass pipe 17 and the motor-operated valve 18 of the regenerative heat exchanger suction water heating section bypass pipe 18 are activated by a confirmation signal that the motor-operated valve 15 that is open is closed. The valve 23 is opened, and the electric valve 24 of the pipe 12 at the connecting portion between the filter desalting device 10 and the regenerative heat exchanger suction water heating part 8 is closed. By opening and closing such a motorized valve,
A signal is issued to secure a line to use the heat exchanger of the reactor coolant purification system.

【００５５】この信号により、電動弁２０、２１が開に
なり、サプレッションプール４と原子炉冷却材浄化系が
連結される。すなわち、電動弁２０、２１の開信号によ
り、排出水昇圧ポンプ１９及び吸込水昇圧ポンプ１４の
起動信号が発せられ、原子炉系冷却材浄化系が原子炉格
納容器除熱装置として機能するようにしている。By this signal, the motor-operated valves 20 and 21 are opened, and the suppression pool 4 and the reactor coolant purification system are connected. That is, the opening signals of the motor-operated valves 20 and 21 generate the activation signals of the discharge water booster pump 19 and the suction water booster pump 14 so that the reactor system coolant purification system functions as a reactor containment heat removal apparatus. ing.

【００５６】本発明の第２実施例を、図２を用いて説明
する。図２は本実施例の原子炉格納容器除熱装置の系統
図である。本実施例は、原子力プラントの構成上、再生
熱交換器吸込水冷却部７及び非再生熱交換器９を、サプ
レッションプール４と同じ高さの位置に設けている原子
炉冷却材浄化系に、本発明の原子炉格納容器除熱装置を
適用した場合である。すなわち、本実施例は、吸込水昇
圧ポンプ１４を、通常運転時における抽出炉水の流れ方
向からみて、再生熱交換器吸込水冷却部７及び非再生熱
交換器９の下流側に設置した場合である。The second embodiment of the present invention will be described with reference to FIG. FIG. 2 is a system diagram of the reactor containment heat removal apparatus of this embodiment. In the present embodiment, due to the structure of the nuclear power plant, a regenerative heat exchanger suction water cooling unit 7 and a non-regenerative heat exchanger 9 are provided in a reactor coolant purification system in which the suppression pool 4 is provided at the same height as the suppression pool 4. This is a case where the heat removal device for a containment vessel of the present invention is applied. That is, in the present embodiment, when the suction water booster pump 14 is installed on the downstream side of the regenerative heat exchanger suction water cooling unit 7 and the non-regeneration heat exchanger 9 as viewed from the flow direction of the extraction reactor water during normal operation. Is.

【００５７】この場合は、電動弁２０、２１の間に排出
水昇圧ポンプ１９（図１参照）を設ける必要はなく、非
常時には吸込水昇圧ポンプ１４だけで、サプレッション
プール４からの排出水を、十分に原子力圧力容器２へ送
ることができる。In this case, it is not necessary to provide the discharge water booster pump 19 (see FIG. 1) between the motor-operated valves 20 and 21, and in an emergency, only the suction water booster pump 14 can discharge the discharge water from the suppression pool 4. It can be sufficiently sent to the nuclear pressure vessel 2.

【００５８】すなわち、通常運転時には、再循環ループ
５からの抽出炉水は、自然落下の形で、再生熱交換器吸
込水冷却部７及び非再生熱交換器９を通って冷却され、
吸込水昇圧ポンプ１４まで流下する。その後、抽出炉水
は吸込水昇圧ポンプ１４により昇圧され、ろ過脱塩器１
０及び再生熱交換器吸込加熱部８を経て、給水配管１３
に送水され、原子炉圧力容器２内に注水されるようにし
ている。That is, during normal operation, the extraction reactor water from the recirculation loop 5 is cooled in the form of a spontaneous fall through the regenerated heat exchanger suction water cooling section 7 and the non-regenerated heat exchanger 9,
It flows down to the suction water booster pump 14. After that, the extraction reactor water is boosted by the suction water booster pump 14, and the filtration desalination device 1
0 and the regenerative heat exchanger suction heating section 8 and then the water supply pipe 13
To be supplied to the reactor pressure vessel 2.

【００５９】一方、非常時には、サプレッションプール
４からの排出水を、吸込水昇圧ポンプ１４により、非再
生熱交換器９の上流側に送った後、非再生熱交換器９を
通過させて冷却している。その後、配管２６により、ろ
過脱塩器１２の下流側に送り、再生熱交換器吸込水加熱
部バイパス配管１８を通して給水配管１３へ送水し、原
子炉圧力容器２内に注水して炉心を冷却している。そし
て、原子炉圧力容器２から流出する冷却材とともに、原
子炉格納容器１内を冷却し、サプレッションプール４へ
戻るようにしている。On the other hand, in an emergency, the discharge water from the suppression pool 4 is sent to the upstream side of the non-regenerative heat exchanger 9 by the suction water booster pump 14 and then passed through the non-regenerative heat exchanger 9 to be cooled. ing. After that, it is sent to the downstream side of the filter demineralizer 12 through the pipe 26, is fed to the water supply pipe 13 through the regenerative heat exchanger suction water heating part bypass pipe 18, and is injected into the reactor pressure vessel 2 to cool the core. ing. Then, the inside of the reactor containment vessel 1 is cooled together with the coolant flowing out from the reactor pressure vessel 2 and returned to the suppression pool 4.

【００６０】また、本実施例でも、上述の実施例と同様
に、原子炉冷却材浄化系を、確実に原子炉格納容器除熱
装置に変換するため、インターロックにも特徴を持たせ
ている。Also in this embodiment, as in the above-mentioned embodiment, the interlock is also characterized in order to reliably convert the reactor coolant purification system into the reactor containment vessel heat removal device. .

【００６１】すなわち、通常運転時開の電動弁１５が閉
であることの確認信号により、再生熱交換器吸込水加熱
部バイパス配管１８上の電動弁２３、吸込水昇圧ポンプ
１４から非再生熱交換器９の上流側に連結された配管２
５上の電動弁２９、及び非再生熱交換器９の下流側と、
ろ過脱塩器１０と再生熱交換器吸込水加熱部８とを連結
する配管におけるろ過脱塩器１０側の部分とを連結する
配管２６上の電動弁３０が開、ろ過脱塩器１０の両側の
電動弁２８、３１、再生熱交換器吸込水加熱部８の上流
側の電動弁２４、非再生熱交換器９と吸込水昇圧ポンプ
１４との間の電動弁２７が閉になる。That is, in response to a confirmation signal that the motor-operated valve 15 that is open during normal operation is closed, the non-regenerative heat exchange is performed from the motor-operated valve 23 and the suction-water booster pump 14 on the bypass pipe 18 of the regenerative heat exchanger suction water heating unit. Pipe 2 connected to the upstream side of container 9
5 on the downstream side of the motor-operated valve 29 and the non-regenerative heat exchanger 9,
The motor-operated valve 30 on the pipe 26 connecting the part connecting the filter desalting device 10 and the regenerated heat exchanger suction water heating part 8 to the part on the filter desalting device 10 side is opened, and both sides of the filter desalting device 10 are opened. The motor-operated valves 28 and 31, the motor-operated valve 24 on the upstream side of the regenerated heat exchanger suction water heating unit 8, and the motor-operated valve 27 between the non-regenerative heat exchanger 9 and the suction water booster pump 14 are closed.

【００６２】このような電動弁の開閉の完了により、原
子炉冷却材浄化系における熱交換器利用ラインが確保さ
れた信号が出る。この熱交換器利用ライン確保の信号に
より電動弁２０、２１が開放され、サプレッションプー
ル４と原子炉冷却材浄化系とが連結される。次いで、吸
込水昇圧ポンプ１４が起動し、原子炉冷却材浄化系が原
子炉格納容器除熱装置として機能することになる。Upon completion of the opening and closing of such a motor-operated valve, a signal indicating that the heat exchanger utilization line in the reactor coolant purification system is secured is output. The motor-operated valves 20 and 21 are opened by the signal to secure the heat exchanger utilization line, and the suppression pool 4 and the reactor coolant purification system are connected. Next, the suction water boosting pump 14 is activated, and the reactor coolant purification system functions as a reactor containment heat removal apparatus.

【００６３】本発明の第３実施例を、図３を用いて説明
する。図３は本実施例の原子炉格納容器除熱装置の系統
図である。本実施例は、第２実施例と同様に、原子炉冷
却材浄化系の吸込水昇圧ポンプ１４を、抽出炉水の流れ
方向からみて、再生熱交換器吸込水冷却部７及び非再生
熱交換器９の下流側に設置した場合である。また、イン
ターロックについても、第２実施例と同様である。A third embodiment of the present invention will be described with reference to FIG. FIG. 3 is a system diagram of the reactor containment heat removal apparatus of this embodiment. In this embodiment, as in the second embodiment, the suction water booster pump 14 of the reactor coolant purification system is viewed from the flow direction of the extraction reactor water, and the regeneration heat exchanger suction water cooling unit 7 and the non-regeneration heat exchange are performed. This is the case where it is installed on the downstream side of the container 9. The interlock is also the same as in the second embodiment.

【００６４】本実施例が、第２実施例と比較して異なる
点は、非常時において、サプレッションプール４からの
排出水を非再生熱交換器９を通過させて冷却する場合、
第２実施例では、その排出水を非再生熱交換器９の上側
から下側に向かって通過させていたのに対し、本実施例
では、下側から上側に向かって通過させていることであ
る。本実施例と第２実施例とのどちらを選択するかにつ
いては、既設の原子力プラントへ適用する場合では、適
用しやすさが一つの選定基準となる。This embodiment is different from the second embodiment in that, in an emergency, when the discharged water from the suppression pool 4 is passed through the non-regenerative heat exchanger 9 to be cooled,
In the second embodiment, the discharged water is passed from the upper side to the lower side of the non-regenerated heat exchanger 9, whereas in the present embodiment, the discharged water is passed from the lower side to the upper side. is there. Regarding the choice between the present embodiment and the second embodiment, the ease of application is one selection criterion when applied to an existing nuclear power plant.

【００６５】本発明の第４実施例を、図４を用いて説明
する。図４は、本発明の第２実施例における起動の手順
及び条件を表すインターロックのブロック線図である。
すなわち、本発明における起動の手順及び条件を表すイ
ンターロックを、本発明の第２実施例を例にとり説明す
る。なお、図４における符号は、図２におけるものと同
一である。A fourth embodiment of the present invention will be described with reference to FIG. FIG. 4 is a block diagram of an interlock representing the starting procedure and conditions in the second embodiment of the present invention.
That is, the interlock representing the starting procedure and conditions in the present invention will be described by taking the second embodiment of the present invention as an example. The reference numerals in FIG. 4 are the same as those in FIG.

【００６６】原子炉冷却材浄化系は、原子炉の通常運転
時には冷却水を浄化・冷却し、非常時には電動弁１５
（図２参照）が閉じられ、冷却材浄化系としての機能は
停止する。The reactor coolant purification system purifies and cools the cooling water during normal operation of the reactor, and the motor-operated valve 15 in an emergency.
(See FIG. 2) is closed and the function as the coolant purification system is stopped.

【００６７】原子炉冷却材浄化系の原子炉格納容器除熱
装置への変換には、通常運転時の手順とは異なった操作
を行うが、これには誤操作を生じないようなインターロ
ックが必要である。すなわち、残留熱除去系が故障して
動いていないことを確実に判断した上で、原子炉冷却材
浄化系の原子炉格納容器除熱装置への変換を決定する必
要がある。このため、本実施例では、許可信号を出すま
での部分と、自動的に変換する部分との繋ぎ目で運転員
の介入ができるような、インターロックにしている。The conversion of the reactor coolant purification system to the reactor containment vessel heat removal device is performed by an operation different from the procedure during normal operation, but this requires an interlock so as not to cause an erroneous operation. Is. That is, it is necessary to make a sure decision that the residual heat removal system has failed and is not operating, and then determine the conversion of the reactor coolant purification system to the reactor containment heat removal device. For this reason, in the present embodiment, the interlock is made so that the operator can intervene at the joint between the part until the permission signal is output and the part for automatically converting.

【００６８】原子炉の停止や事故の非常時には、原子炉
冷却材浄化系は停止し、弁１５が閉となり、原子炉冷却
材浄化系隔離信号が発生する。この場合、残留熱除去系
が故障していて作動しないときには、格納容器圧力高信
号及び格納容器温度高信号のうちの少なくともいずれか
の信号が出されるため、この２つの信号のＯＲ回路、及
びこのＯＲ回路と原子炉冷却材浄化系隔離信号とにより
構成されるＡＮＤ回路により、原子炉冷却材浄化系を原
子炉格納容器除熱装置として、手動スイッチにより起動
させる手動スイッチ許可信号が出される。In the event of a reactor shutdown or an emergency, the reactor coolant purification system is stopped, the valve 15 is closed, and a reactor coolant purification system isolation signal is generated. In this case, when the residual heat removal system is out of order and does not operate, at least one of the high containment vessel pressure signal and the high containment vessel temperature signal is output. An AND circuit composed of an OR circuit and a reactor coolant purification system isolation signal outputs a manual switch permission signal for activating the reactor coolant purification system as a reactor containment vessel heat removal device by a manual switch.

【００６９】運転員はこの手動スイッチ許可信号を確認
した上で、原子炉の状況に応じて手動スイッチＯＮの判
断をする。このような判断の基準は、残留熱除去系が機
能しておらず、原子炉格納容器除熱装置の起動を必要と
していることである。すなわち、運転員の判断により手
動スイッチがＯＮされた場合には、電動弁２０、２１の
開、電動弁２３、２４、２７〜３１の閉を自動的に行わ
せ、電動弁の開閉操作がすべて終わった時点で吸込水昇
圧ポンプ１４（図２参照）を起動させている。After confirming the manual switch permission signal, the operator determines whether the manual switch is ON according to the situation of the nuclear reactor. The criterion for such a determination is that the residual heat removal system is not functioning and the reactor containment heat removal device needs to be started. That is, when the manual switch is turned on by the operator's judgment, the motor-operated valves 20 and 21 are automatically opened and the motor-operated valves 23, 24, and 27 to 31 are automatically closed so that all the motor-operated valves are opened and closed. The suction water booster pump 14 (see FIG. 2) is started at the time of completion.

【００７０】[0070]

【発明の効果】本発明によれば、通常運転時には原子炉
冷却材浄化系として機能していた系統が、非常時には原
子炉格納容器除熱装置として機能できるようになる。す
なわち、原子炉冷却材浄化系は非常時には使用されなく
なり、この系統の熱交換器は余分な設備となるが、本発
明の設備を追加することにより、この余分な設備を有効
利用することができ、軽微な改善で残留熱除去系の多重
性を１つ多く持つことができるようになる。既設の原子
力プラントでは原子炉冷却材浄化系の熱交換器の容量は
小さいが、少しでも崩壊熱を除去し、事故の拡大を遅ら
せる効果を有する。According to the present invention, the system functioning as the reactor coolant purification system during normal operation can now function as the reactor containment vessel heat removal device in an emergency. That is, the reactor coolant purification system will not be used in an emergency, and the heat exchanger of this system will be an extra facility, but by adding the facility of the present invention, this extra facility can be effectively used. With a slight improvement, it is possible to increase the multiplicity of the residual heat removal system by one. Although the capacity of the heat exchanger of the reactor coolant purification system is small in the existing nuclear power plant, it has the effect of removing decay heat as much as possible and delaying the expansion of the accident.

【００７１】また、原子炉の停止後、長時間経過した時
点で残留熱除去系が故障した場合には、崩壊熱レベルが
下がっているため、十分に崩壊熱を除去することがで
き、残留熱除去系の代替を務めることが可能となる。Further, when the residual heat removal system fails at a long time after the reactor is shut down, the decay heat level is lowered, so that the decay heat can be sufficiently removed and the residual heat is removed. It becomes possible to act as a substitute for the removal system.

【００７２】更に、原子炉冷却材浄化系の熱交換器を利
用し、冷却水を炉心や原子炉格納容器へ供給できるよう
になるため、既設や新設の原子力プラントにおいて容易
に残留熱除去系を多重化することができ、低コストで安
全性の高い沸騰水型原子炉を提供することができる。Furthermore, since the cooling water can be supplied to the core and the reactor containment vessel by using the heat exchanger of the reactor coolant purification system, the residual heat removal system can be easily installed in the existing or new nuclear power plant. It is possible to provide a boiling water nuclear reactor that can be multiplexed and that is low in cost and high in safety.

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

【図１】本発明の原子炉格納容器除熱装置における第１
実施例の系統図である。FIG. 1 is a first example of a heat removal device for a containment vessel of the present invention.
It is a systematic diagram of an Example.

【図２】本発明の原子炉格納容器除熱装置における第２
実施例の系統図である。FIG. 2 is a second view of the heat removal device for a containment vessel of the present invention.
It is a systematic diagram of an Example.

【図３】本発明の原子炉格納容器除熱装置における第３
実施例の系統図である。FIG. 3 is a third view of a heat removal device for a PCV of the present invention.
It is a systematic diagram of an Example.

【図４】図２の原子炉格納容器除熱装置の起動の手順及
び条件を表すインターロックのブロック線図である。FIG. 4 is a block diagram of an interlock showing the procedure and conditions for starting the heat removal device for the PCV of FIG.

【符号の説明】[Explanation of symbols]

１…原子炉格納容器、２…原子炉圧力容器、３…ドライ
ウェル、４…サプレッションプール、５…再循環ルー
プ、６…再生熱交換器、７…再生熱交換器吸込水冷却
部、８…再生熱交換器吸込水加熱部、９…非再生熱交換
器、１０…ろ過脱塩器、１１…抽水炉水配管、１２、１
６、２５、２６…配管、１３…給水配管、１４…吸込水
昇圧ポンプ、１５、２０〜２４、２７〜３１…電動弁、
１７…ろ過脱塩器バイパス配管、１８…再生熱交換器吸
込水加熱部バイパス配管、１９…排出水昇圧ポンプ。DESCRIPTION OF SYMBOLS 1 ... Reactor containment vessel, 2 ... Reactor pressure vessel, 3 ... Dry well, 4 ... Suppression pool, 5 ... Recirculation loop, 6 ... Regenerative heat exchanger, 7 ... Regenerative heat exchanger suction water cooling section, 8 ... Regeneration heat exchanger Suction water heating part, 9 ... Non-regeneration heat exchanger, 10 ... Filtration demineralizer, 11 ... Water extraction reactor water pipe, 12, 1
6, 25, 26 ... Piping, 13 ... Water supply piping, 14 ... Suction water booster pump, 15, 20-24, 27-31 ... Motorized valve,
17 ... Filter desalting device bypass pipe, 18 ... Regeneration heat exchanger suction water heating part bypass pipe, 19 ... Discharge water booster pump.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 佐藤 憲一 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Kenichi Sato 3-1-1, Saiwaicho, Hitachi-shi, Ibaraki Hitachi Ltd. Hitachi factory

Claims (5)

【特許請求の範囲】[Claims] 【請求項１】 原子炉格納容器内に発生した崩壊熱を除
去する残留熱除去系、並びに前記原子炉圧力容器に接続
する再循環ループ、前記再循環ループからの抽出炉水を
昇圧する吸込水昇圧ポンプ、前記抽出炉水の冷却部と加
熱部とを有する再生熱交換器、前記抽出炉水を冷却する
非再生熱交換器、前記抽出炉水を浄化するろ過脱塩器、
前記抽出炉水を前記吸込水昇圧ポンプに吸い込ませる抽
出炉水配管、前記吸込水昇圧ポンプと前記再生熱交換器
の吸込水冷却部と前記非再生熱交換器と前記ろ過脱塩器
と前記再生熱交換器の吸込水加熱部とを順次接続する配
管、前記再生熱交換器の吸込水加熱部と前記原子炉格納
容器へ外部から給水する給水配管とを接続する配管、及
び前記抽出炉水配管に付設している抽出配管用電動弁か
らなり、前記吸込水昇圧ポンプが前記原子炉格納容器内
のサプレッションプールよりも高く位置している状態の
原子炉冷却材浄化系を有する原子炉における原子炉格納
容器除熱装置において、前記抽出炉水配管における前記
吸込水昇圧ポンプと前記抽出配管用電動弁との間のいず
れかの箇所と前記サプレッションプールとを接続する第
１の配管、前記ろ過脱塩器をバイパスする第２の配管、
及び前記再生熱交換器の吸込水加熱部をバイパスする第
３の配管を備え、前記第１の配管に前記サプレッション
プールからの排出水を昇圧する排出水昇圧ポンプ、前記
第１の配管における前記排出水昇圧ポンプの一方側に第
１の電動弁、他方側に第２の電動弁、前記第２の配管に
第３の電動弁、及び前記第３の配管に第４の電動弁をそ
れぞれ設けていることを特徴とする原子炉格納容器除熱
装置。1. A residual heat removal system for removing decay heat generated in a reactor containment vessel, a recirculation loop connected to the reactor pressure vessel, and suction water for pressurizing extraction reactor water from the recirculation loop. Booster pump, a regenerative heat exchanger having a cooling unit and a heating unit of the extraction reactor water, a non-regeneration heat exchanger that cools the extraction reactor water, a filter demineralizer that purifies the extraction reactor water,
Extraction reactor water piping for sucking the extraction reactor water into the suction water booster pump, the suction water booster pump, the suction water cooling section of the regenerative heat exchanger, the non-regenerated heat exchanger, the filtration desalination unit, and the regeneration A pipe for sequentially connecting the suction water heating unit of the heat exchanger, a pipe for connecting the suction water heating unit of the regenerative heat exchanger and a water supply pipe for externally supplying water to the reactor containment vessel, and the extraction reactor water pipe A nuclear reactor having a reactor coolant purification system in which the suction water booster pump is located higher than the suppression pool in the reactor containment vessel In the containment vessel heat removal apparatus, a first pipe connecting the suppression pool to any part of the extraction reactor water pipe between the suction water booster pump and the electric motor for extraction pipe, and the filter. Second pipe which bypasses the desalter,
And a third pipe that bypasses the suction water heating unit of the regenerative heat exchanger, wherein the first pipe has a discharge water booster pump that pressurizes the discharge water from the suppression pool, and the discharge in the first pipe. A first electric valve is provided on one side of the water booster pump, a second electric valve is provided on the other side, a third electric valve is provided on the second pipe, and a fourth electric valve is provided on the third pipe. Reactor containment vessel heat removal device. 【請求項２】 原子炉格納容器内に発生した崩壊熱を除
去する残留熱除去系、並びに前記原子炉圧力容器に接続
する再循環ループ、前記再循環ループからの抽出炉水を
昇圧する吸込水昇圧ポンプ、前記抽出炉水の冷却部と加
熱部とを有する再生熱交換器、前記抽出炉水を冷却する
非再生熱交換器、前記抽出炉水を浄化するろ過脱塩器、
前記抽出炉水を前記再生熱交換器の冷却部と前記非再生
熱交換器とを通して前記吸込水昇圧ポンプに吸い込ませ
る抽出炉水配管、前記吸込水昇圧ポンプと前記ろ過脱塩
器と前記再生熱交換器の吸込水加熱部とを接続する配
管、前記再生熱交換器の吸込水加熱部と前記原子炉格納
容器へ外部から給水する給水配管とを接続する配管、及
び前記抽出配管に付設している抽出配管用電動弁からな
り、前記吸込水昇圧ポンプが前記サプレッションプール
と同じ高さに位置している状態の原子炉冷却材浄化系を
有する原子炉における原子炉格納容器除熱装置におい
て、前記抽出炉水配管における前記吸込水昇圧ポンプと
前記非再生熱交換器との間のいずれかの箇所と前記サプ
レッションプールとを接続する第１の配管、前記ろ過脱
塩器をバイパスする第２の配管、及び前記再生熱交換器
の吸込水加熱部をバイパスする第３の配管、前記サプレ
ッションプールからの排出水を前記吸込水昇圧ポンプを
介して前記非再生熱交換器に通す配管、及び前記非再生
熱交換器における吸込水排出側配管と、前記ろ過脱塩器
と前記再生熱交換器の吸込水加熱部とを接続する配管に
おける前記ろ過脱塩器の側の部分とを接続する配管を備
え、前記第１の配管に第１の電動弁と第２の電動弁、前
記第２の配管に第３の電動弁、及び前記第３の配管に第
４の電動弁をそれぞれ設けていることを特徴とする原子
炉格納容器除熱装置。2. A residual heat removal system for removing decay heat generated in a reactor containment vessel, a recirculation loop connected to the reactor pressure vessel, and suction water for pressurizing extraction reactor water from the recirculation loop. Booster pump, a regenerative heat exchanger having a cooling unit and a heating unit of the extraction reactor water, a non-regeneration heat exchanger that cools the extraction reactor water, a filter demineralizer that purifies the extraction reactor water,
Extraction reactor water piping for sucking the extraction reactor water through the cooling section of the regenerative heat exchanger and the non-regeneration heat exchanger into the suction water booster pump, the suction water booster pump, the filtration desalination unit, and the regenerative heat A pipe connecting the suction water heating part of the exchanger, a pipe connecting the suction water heating part of the regenerative heat exchanger and a water supply pipe for supplying water to the reactor containment vessel from the outside, and attached to the extraction pipe. In a reactor containment heat removal apparatus in a reactor having a reactor coolant purification system in which the suction water booster pump is located at the same height as the suppression pool, A first pipe that connects the suppression pool to any portion between the suction water booster pump and the non-regenerative heat exchanger in the extraction reactor water pipe, and a first pipe that bypasses the filtration demineralizer And a third pipe that bypasses the suction water heating unit of the regenerative heat exchanger, a pipe that allows the discharge water from the suppression pool to pass through the non-regeneration heat exchanger via the suction water booster pump, and A pipe connecting the suction water discharge side pipe in the non-regeneration heat exchanger and a part of the pipe connecting the filtration desalination unit and the suction water heating unit of the regeneration heat exchanger on the side of the filtration deionization unit. A first electric valve and a second electric valve on the first pipe, a third electric valve on the second pipe, and a fourth electric valve on the third pipe. A heat removal device for a reactor containment vessel. 【請求項３】 前記残留熱除去系の故障を指示する信号
と前記原子炉冷却材浄化系の停止を指示する信号とが発
信された非常時において、遠隔操作により自動的に、前
記抽出配管用電動弁が閉に、前記第３の電動弁、及び前
記第４の電動弁が開にそれぞれ作動し、この作動の完了
信号により、前記第１の電動弁、及び前記第２の電動弁
がそれぞれ開に作動し、この作動の完了信号により、前
記吸込水昇圧ポンプ及び前記排出水昇圧ポンプがそれぞ
れ起動し、前記原子炉冷却材浄化系の機能が原子炉格納
容器の崩壊熱除去系に切り替わる請求項１記載の原子炉
格納容器除熱装置。3. The extraction pipe for the extraction pipe is automatically operated by remote control in an emergency when a signal indicating a failure of the residual heat removal system and a signal indicating a stop of the reactor coolant purification system are transmitted. The electrically operated valve is operated to be closed, the third electrically operated valve and the fourth electrically operated valve are operated to open, and the first electrically operated valve and the second electrically operated valve are respectively activated by a completion signal of the operation. An open operation, and upon completion of this operation, the suction water booster pump and the discharge water booster pump are each activated, and the function of the reactor coolant purification system is switched to the decay heat removal system of the reactor containment vessel. Item 2. A heat removal device for a reactor containment vessel according to Item 1. 【請求項４】 前記残留熱除去系の故障を指示する信号
と前記原子炉冷却材浄化系の停止を指示する信号とが発
信された非常時において、遠隔操作により自動的に、前
記抽出配管用電動弁が閉に、前記第３の電動弁、及び前
記第４の電動弁が開にそれぞれ作動し、この作業の完了
信号により、前記第１の電動弁、及び前記第２の電動弁
がそれぞれ開に作動し、この作動の完了信号により、前
記吸込水昇圧ポンプが起動し、前記原子炉冷却材浄化系
の機能が原子炉格納容器の崩壊熱除去系に切り替わる請
求項２記載の原子炉格納容器除熱装置。4. The extraction pipe for the extraction pipe is automatically operated by remote control in an emergency when a signal indicating a failure of the residual heat removal system and a signal indicating a stop of the reactor coolant purification system are transmitted. The motor-operated valve is closed and the third motor-operated valve and the fourth motor-operated valve are respectively operated to open, and the first motor-operated valve and the second motor-operated valve are respectively operated by a completion signal of this work. The reactor containment system according to claim 2, wherein the reactor is opened and the suction water booster pump is started in response to the completion signal of the operation, and the function of the reactor coolant purification system is switched to the decay heat removal system of the reactor containment vessel. Container heat removal device. 【請求項５】 前記非常時において、運転員手動スイッ
チＯＮの許可信号により、運転員の判断で、前記原子炉
冷却材浄化系の機能を原子炉格納容器の崩壊熱除去系に
切り替える手動スイッチを設けている請求項３又は請求
項４記載の原子炉格納容器除熱装置。5. A manual switch for switching the function of the reactor coolant purification system to the decay heat removal system of the reactor containment vessel at the operator's discretion in response to the operator manual switch ON permission signal in the emergency. The reactor containment vessel heat removal apparatus according to claim 3 or 4, which is provided.
JP6199389A 1994-08-24 1994-08-24 Reactor containment heat removal device Pending JPH0862373A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6199389A JPH0862373A (en) 1994-08-24 1994-08-24 Reactor containment heat removal device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6199389A JPH0862373A (en) 1994-08-24 1994-08-24 Reactor containment heat removal device

Publications (1)

Publication Number Publication Date
JPH0862373A true JPH0862373A (en) 1996-03-08

Family

ID=16406967

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6199389A Pending JPH0862373A (en) 1994-08-24 1994-08-24 Reactor containment heat removal device

Country Status (1)

Country Link
JP (1) JPH0862373A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104409115A (en) * 2014-12-17 2015-03-11 中国科学院合肥物质科学研究院 Complex device for auxiliary heating and waste heat discharging of pool-type liquid heavy metal cooled reactor
EP3067896A4 (en) * 2013-11-07 2017-06-21 Hitachi-GE Nuclear Energy, Ltd. Cooling system for nuclear reactor suppression pool

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3067896A4 (en) * 2013-11-07 2017-06-21 Hitachi-GE Nuclear Energy, Ltd. Cooling system for nuclear reactor suppression pool
CN104409115A (en) * 2014-12-17 2015-03-11 中国科学院合肥物质科学研究院 Complex device for auxiliary heating and waste heat discharging of pool-type liquid heavy metal cooled reactor

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