JP2010112772A - Nuclear power plant and control method - Google Patents

Nuclear power plant and control method Download PDF

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JP2010112772A
JP2010112772A JP2008283833A JP2008283833A JP2010112772A JP 2010112772 A JP2010112772 A JP 2010112772A JP 2008283833 A JP2008283833 A JP 2008283833A JP 2008283833 A JP2008283833 A JP 2008283833A JP 2010112772 A JP2010112772 A JP 2010112772A
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steam
water
heat transfer
pool
pipe
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JP5235614B2 (en
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Tomohiko Ikegawa
Kazuaki Kito
Naoki Kumagai
和明 木藤
智彦 池側
直己 熊谷
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Hitachi-Ge Nuclear Energy Ltd
日立Geニュークリア・エナジー株式会社
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

<P>PROBLEM TO BE SOLVED: To realize a water pouring means which can supply cooling water into a reactor, without having to use high-pressure water storage tanks or pumps, even in a state where the pressure inside the reactor is high. <P>SOLUTION: A closed loop including the reactor and heat-transfer pipes is constituted to draw steam from the former into the latter. The heat-transfer pipes, with the steam stored inside them, are isolated from the reactor, to make the steam condense inside the heat-transfer pipes. Since the condensation of the steam lowers the pressure inside the heat-transfer pipes, low-pressure cooling water can be drawn from a pool installed outside the heat-transfer pipes. By redrawing the steam from the reactor, after storing the cooling water inside the heat-transfer pipes, the cooling water stored inside them can be supplied to the inside of the reactor. <P>COPYRIGHT: (C)2010,JPO&INPIT

Description

本発明は原子力プラントに係り、冷却材を原子炉又は蒸気発生器内に注水する安全系を持つ原子力プラントに関する。   The present invention relates to a nuclear power plant, and more particularly to a nuclear power plant having a safety system for injecting coolant into a nuclear reactor or a steam generator.
従来の原子力プラントにおいては、異常事象発生時に原子炉内で発生した熱を除去したり、原子炉内に冷却材を供給するために、主にポンプを用いた動的な安全系が用いられていた。   In a conventional nuclear power plant, a dynamic safety system mainly using a pump is used to remove heat generated in the reactor when an abnormal event occurs or to supply coolant to the reactor. It was.
ポンプを用いて原子炉内部に冷却水を供給できる従来の注水技術が特開2003−344576号公報に示されている。   Japanese Patent Application Laid-Open No. 2003-344576 discloses a conventional water injection technique that can supply cooling water into a nuclear reactor using a pump.
一方で、ポンプを用いず、重力や圧力などの静的な力を動力として作動する静的な安全系も存在する。   On the other hand, there is also a static safety system that operates using a static force such as gravity or pressure without using a pump.
ポンプを用いずに原子炉内部の圧力が高い状態でも冷却水を原子炉内部に供給できる従来の蓄圧注水技術が特開平4−328494号公報に示されている。   Japanese Patent Application Laid-Open No. 4-328494 discloses a conventional pressure-accumulating water injection technique that can supply cooling water into the reactor even when the pressure inside the reactor is high without using a pump.
特開2003−344576号公報JP 2003-344576 A 特開平4−328494号公報JP-A-4-328494
従来のポンプを用いた動的な安全系を用いれば、原子炉内部圧力に係わらず、異常事象発生時に冷却水を原子炉内部に供給可能であるが、ポンプは定期的な点検が不可欠である。ポンプの点検作業が不要となれば、定期点検期間の短縮が可能となる。これらの目的のため、近年はポンプを用いない安全設備が注目されている。   If a dynamic safety system using a conventional pump is used, cooling water can be supplied into the reactor when an abnormal event occurs, regardless of the pressure inside the reactor, but periodic inspection of the pump is essential. . If the pump inspection work becomes unnecessary, the periodic inspection period can be shortened. For these purposes, in recent years, safety equipment that does not use a pump has attracted attention.
原子炉内部圧力が大気圧程度の低圧になった後であれば、ポンプを用いなくても水圧を利用して容易に冷却水を原子炉内部に注水が可能であるが、原子炉内部圧力が高圧の状態でポンプを用いずに冷却水を注水するには上述の従来の蓄圧注水技術を用いる必要があった。蓄圧注水技術は、冷却水を貯水タンク内にあらかじめ高圧で貯蔵しておき、原子炉内部への注水が必要になった時にはタンク内の圧力を利用して原子炉内部に冷却水を注水する。蓄圧注水技術を利用するには高圧の貯水タンクが必要であるため、大きな水量を確保することは難しい。   Cooling water can be easily injected into the reactor using the water pressure without using a pump after the reactor internal pressure has reached a low pressure of about atmospheric pressure. In order to inject cooling water without using a pump in a high pressure state, it is necessary to use the above-described conventional pressure accumulation water injection technique. In the pressure accumulation water injection technology, cooling water is stored in a storage tank at a high pressure in advance, and when it is necessary to inject water into the reactor, the cooling water is injected into the reactor using the pressure in the tank. Since a high-pressure water storage tank is required to use the pressure accumulation water injection technology, it is difficult to secure a large amount of water.
本発明では、高圧の貯水タンクやポンプを用いず、原子炉内部圧力が高い状態でも原子炉内部に冷却水を供給できる注水手段を実現することを目的とする。   An object of the present invention is to realize a water injection means that can supply cooling water to the inside of the reactor even when the pressure inside the reactor is high without using a high-pressure water storage tank or pump.
上記目的を達成するため本発明では、原子炉又は蒸気発生器から伝熱管内に蒸気を引き込み、前記伝熱管内に引き込んだ蒸気を貯めた状態で、前記伝熱管を原子炉又は蒸気発生器と隔離し、前記伝熱管内に引き込んだ蒸気を凝縮させ、前記伝熱管外部に設置したプールから前記伝熱管内に冷却水を引き込み、再度、前記原子炉又は前記蒸気発生器から伝熱管内に蒸気を引き込み、前記伝熱管内に引き込んだ冷却水を水頭により原子炉又は蒸気発生器に供給することを特徴とする。   In order to achieve the above object, in the present invention, steam is drawn into a heat transfer tube from a reactor or a steam generator, and the heat transfer tube is used as a reactor or a steam generator in a state where the steam drawn into the heat transfer tube is stored. Isolate, condense the steam drawn into the heat transfer tube, draw cooling water from the pool installed outside the heat transfer tube into the heat transfer tube, and again from the reactor or the steam generator into the heat transfer tube The cooling water drawn into the heat transfer tube is supplied to the nuclear reactor or the steam generator by the head.
本発明によれば、高圧の貯水タンクやポンプを用いずに、原子炉内部圧力が高い状態でも冷却水を原子炉に供給できる。高圧の貯水タンクが不要となり、ポンプが無いため定期点検期間が短縮できる。   According to the present invention, it is possible to supply cooling water to a nuclear reactor without using a high-pressure water storage tank or pump even when the reactor internal pressure is high. There is no need for a high-pressure water storage tank, and the periodic inspection period can be shortened because there is no pump.
原子炉又は蒸気発生器と、蒸気を凝縮させる伝熱管で閉ループを構成する。原子炉又は蒸気発生器から伝熱管内に蒸気を引き込んだ後、伝熱管内部に蒸気を貯めた状態で伝熱管部を原子炉又は蒸気発生器と隔離し、伝熱管内部の蒸気を凝縮させる。伝熱管内部では蒸気が凝縮することで圧力が低下するため、伝熱管の外側に設置したプールから低圧の冷却水を引き込むことができる。伝熱管内部に冷却水を貯めた後で、原子炉又は蒸気発生器から再び蒸気を引き込むことで、伝熱管内部に貯めた冷却水の水頭により、冷却水を原子炉又は蒸気発生器内に供給できる。   A closed loop is constituted by a nuclear reactor or a steam generator and a heat transfer tube for condensing steam. After the steam is drawn into the heat transfer tube from the reactor or the steam generator, the heat transfer tube portion is isolated from the reactor or the steam generator while the steam is stored in the heat transfer tube, and the steam inside the heat transfer tube is condensed. Since the pressure is reduced by condensing steam inside the heat transfer tube, low-pressure cooling water can be drawn from a pool installed outside the heat transfer tube. After storing the cooling water inside the heat transfer tube, supply the cooling water into the reactor or the steam generator by drawing the steam from the reactor or the steam generator and using the head of the cooling water stored inside the heat transfer tube. it can.
直接サイクル型原子力プラントの一つである沸騰水型軽水炉(BWR)に適用した場合の実施例を示す。なお実施例はこれに限定されるものではない。   An embodiment when applied to a boiling water light water reactor (BWR) which is one of direct cycle nuclear power plants will be described. However, the embodiment is not limited to this.
図1に第1実施例を示す。   FIG. 1 shows a first embodiment.
図1はBWRに適用した注水装置の構成を模式的に示したものである。原子炉圧力容器1の通常運転時水位よりも上の位置に蒸気引き込み管2を接続し、蒸気引き込み管の他方に上部ヘッダ3を介して多数の蒸気凝縮伝熱管4を接続する。蒸気凝縮伝熱管の下側は下部ヘッダ5でまとめ、凝縮水戻し管6を介して原子炉圧力容器内部の通常時運転時水位25aよりも下の位置に接続する。蒸気凝縮伝熱管は、伝熱管冷却プール7の中に設置されており、蒸気凝縮伝熱管の内部を流れる蒸気を伝熱管冷却プール内の水で冷却して凝縮させる。凝縮水戻し管上には、凝縮水制御弁8を設置する。通常運転中は凝縮水制御弁は閉めておき、蒸気凝縮伝熱管に原子炉圧力容器内部の蒸気が連続的に流れ込むのを防止する。蒸気凝縮管内部で凝縮した蒸気は、凝縮水戻し管又は蒸気凝縮伝熱管内部で水位を形成する。この凝縮水の水位が通常運転時の原子炉圧力容器内部の通常運転時水位25aよりも高ければ、凝縮水制御弁を開いたときに、水の自重を利用して凝縮水を原子炉圧力容器内部に供給できる。凝縮水の水位を原子炉圧力容器内部の通常運転時水位よりも高くするためには、伝熱管冷却プール内の通常運転時水位25bは原子炉圧力容器内部の通常運転時水位よりも高い位置にあることが望ましい。ここまでの構成は、一部のBWRで実績のある非常用復水器(IC)と同じである。   FIG. 1 schematically shows the structure of a water injection apparatus applied to BWR. A steam inlet pipe 2 is connected to a position above the water level during normal operation of the reactor pressure vessel 1, and a number of steam condensation heat transfer pipes 4 are connected to the other side of the steam inlet pipe via an upper header 3. The lower side of the steam condensing heat transfer tube is collected by the lower header 5 and connected via the condensed water return tube 6 to a position below the normal operation water level 25a inside the reactor pressure vessel. The steam condensation heat transfer tube is installed in the heat transfer tube cooling pool 7, and the steam flowing inside the steam condensation heat transfer tube is cooled and condensed with water in the heat transfer tube cooling pool. A condensed water control valve 8 is installed on the condensed water return pipe. During normal operation, the condensate control valve is closed to prevent the steam inside the reactor pressure vessel from continuously flowing into the steam condensation heat transfer tube. The steam condensed inside the steam condensation pipe forms a water level inside the condensed water return pipe or the steam condensation heat transfer pipe. If the water level of the condensed water is higher than the normal operation water level 25a inside the reactor pressure vessel during normal operation, the condensed water can be removed from the reactor pressure vessel by utilizing its own weight when the condensate control valve is opened. Can supply inside. In order to make the water level of the condensed water higher than the normal operation level in the reactor pressure vessel, the normal operation level 25b in the heat transfer tube cooling pool is higher than the normal operation level in the reactor pressure vessel. It is desirable to be. The configuration up to this point is the same as an emergency condenser (IC) that has been proven in some BWRs.
蒸気引き込み管上には蒸気引き込み制御弁9を、凝縮水戻し管上の凝縮水制御弁よりも上流側(蒸気凝縮伝熱管側)には、蒸気凝縮伝熱管から凝縮水戻し管方向への冷却水のみを流す凝縮水逆止弁10を設置する。制御弁に逆止弁を設けることで、手順が簡略化される。(なお、実施例3で説明するように必ずしも凝縮水逆止弁10は必要でない。)蒸気引き込み制御弁は通常運転中は開いていても閉じていても良いが、作動失敗を防止するには開いていた方が望ましい。また、蒸気引き込み制御弁よりも下流側で、凝縮水逆止弁よりも上流側の位置には、プール水引き込み管11と、水位測定用差圧計12を設置する。プール水引き込み管の他方は、伝熱管冷却プール内に開放される。給水プールを設ける場合と比較して、伝熱管内部へ供給する冷却水を伝熱管冷却プールから引き込む場合は、コンパクト化がはかれ、物量を小さくすることができる。プール水引き込み管上には、伝熱管冷却プールから蒸気凝縮伝熱管方向への冷却水のみを通す逆止弁であるプール水引き込み制御弁13を設置する。制御弁を逆止弁とすることで、手順の簡略化が図れる。水位測定差圧計は、蒸気凝縮伝熱管内の水位を計算して貯まった水量を評価する目的で設置するもので、水量を評価できれば光学的な水位計測手段や他の圧力又は差圧計測手段など、どのような方法を用いても良い。水位計測用差圧計の出力は、蒸気引き込み制御器14に取り込み、蒸気引き込み制御器は水位計測用差圧計の出力に基づいて蒸気引き込み制御弁を開閉制御する。尚、例えば停電時の非常時においては制御器による制御の他、人手により蒸気凝縮伝熱管内の水位を確認して蒸気引き込み制御弁を開閉制御することもできる。   The steam intake control valve 9 is provided on the steam intake pipe, and the cooling from the steam condensation heat transfer pipe to the condensed water return pipe is performed upstream of the condensed water control valve on the condensed water return pipe (steam condensation heat transfer pipe side). A condensed water check valve 10 for flowing only water is installed. Providing a check valve in the control valve simplifies the procedure. (Note that the condensate check valve 10 is not necessarily required as described in the third embodiment.) The steam intake control valve may be open or closed during normal operation, but to prevent operation failure. It is desirable to have it open. In addition, a pool water intake pipe 11 and a water level measurement differential pressure gauge 12 are installed downstream of the steam intake control valve and upstream of the condensed water check valve. The other of the pool water inlet pipes is opened into the heat transfer pipe cooling pool. Compared with the case where a water supply pool is provided, when the cooling water supplied to the inside of the heat transfer tube is drawn from the heat transfer tube cooling pool, the size can be reduced and the quantity can be reduced. On the pool water intake pipe, a pool water intake control valve 13 that is a check valve that allows only cooling water to flow from the heat transfer pipe cooling pool toward the steam condensation heat transfer pipe is installed. By making the control valve a check valve, the procedure can be simplified. A water level measurement differential pressure gauge is installed for the purpose of evaluating the amount of water stored by calculating the water level in the steam condensation heat transfer tube. If the water amount can be evaluated, an optical water level measurement means, other pressure or differential pressure measurement means, etc. Any method may be used. The output of the water level measuring differential pressure gauge is taken into the steam drawing controller 14, and the steam drawing controller controls the opening and closing of the steam drawing control valve based on the output of the water level measuring differential pressure gauge. For example, in the event of an emergency at the time of a power failure, in addition to the control by the controller, the water level in the steam condensation heat transfer tube can be manually checked to open / close the steam intake control valve.
本実施例では、蒸気凝縮伝熱管と伝熱管冷却プールは原子炉格納容器壁面15の外側に設置したが、これらの機器を原子炉格納容器の内側に置くか、外側に置くかは任意である。また、蒸気引き込み管は原子炉圧力容器から蒸気を抜き取れる場所であれば必ずしも原子炉圧力容器に直接接続する必要は無く、例えば原子炉圧力容器に接続している主蒸気管16に接続しても良い。同様に、凝縮水戻し管6は例えば主給水管17に接続しても良い。   In this embodiment, the steam condensing heat transfer tube and the heat transfer tube cooling pool are installed outside the reactor containment wall 15, but it is optional to place these devices inside or outside the reactor containment vessel. . Further, the steam inlet pipe does not necessarily have to be directly connected to the reactor pressure vessel if it is a place where the steam can be extracted from the reactor pressure vessel. For example, it is connected to the main steam pipe 16 connected to the reactor pressure vessel. Also good. Similarly, the condensed water return pipe 6 may be connected to the main water supply pipe 17, for example.
次に、本実施例の運転手順について図2を用いて説明する。   Next, the operation procedure of the present embodiment will be described with reference to FIG.
原子炉で異常事象が発生し原子炉内部に冷却水を供給する必要が生じたときは、まず初めに時刻T1で凝縮水制御弁を開く。凝縮水制御弁を開くことで蒸気凝縮伝熱管内に貯まっていた凝縮水が原子炉圧力容器に流れ、同時に原子炉圧力容器から蒸気引き込み管を通して蒸気凝縮伝熱管に蒸気が流れ込む。この状態で時刻T2に蒸気引き込み制御弁を閉じると、原子炉圧力容器から凝縮水戻し管を通した冷却水流れも凝縮水逆止弁で遮断されるため、蒸気凝縮伝熱管は原子炉圧力容器から隔離される。蒸気凝縮伝熱管内部に貯まっている蒸気は、伝熱管冷却プールに熱を放出して凝縮を始める。蒸気が凝縮して飽和水になると、圧力7MPaで体積は1/20、大気圧では体積は1/1600にまで減少するため、蒸気凝縮伝熱管内部の圧力は急激に低下する。時刻T3で蒸気凝縮伝熱管内部の圧力が、伝熱管冷却プールの水圧よりも低くなると、伝熱管冷却プールに貯蔵されている冷却水がプール水引き込み管を通して蒸気凝縮伝熱管内部に流れ込む。プール水引き込み管をループ側(原子炉又は蒸気発生器と管の閉ループのうち蒸気引き込み管及び蒸気凝縮伝熱管及び凝縮水戻し管で作られるループ側で、蒸気引き込み制御弁から凝縮水戻り制御弁までの間)に接続する位置については、接続位置を高くするとプール水引き込み管から引き込んだ冷却水により伝熱管内部を冷却する効果が得られるが、逆に接続位置を低くした方が伝熱管冷却プールの水圧を大きく取れるので、より早いタイミングでプール水を蒸気凝縮伝熱管内に引き込むことが可能となる。プール水引き込み管のループ側の接続位置は、蒸気凝縮伝熱管の伝熱面積や伝熱管冷却プールの水深などを考慮して決定する必要がある。蒸気凝縮伝熱管内部に貯まった冷却水量は水位計測用差圧計で感知し、蒸気引き込み制御器に入力する。蒸気引き込み制御器で、貯まった冷却水量が十分かどうかを判定する。時刻T4で十分な水量が貯まったと判断すると、蒸気引き込み制御弁9を再度開く。蒸気引き込み制御弁を開くことで、蒸気凝縮伝熱管内部に貯まった冷却水の水頭圧で冷却水を原子炉圧力容器内部に供給できる。蒸気引き込み制御弁の開閉を繰り返せば、同様の手順で大量の冷却水を原子炉圧力容器内部に供給可能である。一度の操作で多くの冷却水を注水するためには、例えば蒸気凝縮伝熱管が接続する上部ヘッダや下部ヘッダを大きくすると有効である。   When an abnormal event occurs in the reactor and it becomes necessary to supply cooling water to the inside of the reactor, first, the condensed water control valve is opened at time T1. By opening the condensate control valve, the condensed water stored in the steam condensing heat transfer tube flows into the reactor pressure vessel, and at the same time, the steam flows from the reactor pressure vessel through the steam drawing tube into the steam condensing heat transfer tube. When the steam intake control valve is closed at time T2 in this state, the cooling water flow from the reactor pressure vessel through the condensed water return pipe is also shut off by the condensed water check valve. Isolated from. The steam stored in the steam condensation heat transfer tube releases heat to the heat transfer tube cooling pool and starts condensing. When the steam condenses into saturated water, the volume decreases to 1/20 at a pressure of 7 MPa and 1/1600 at atmospheric pressure, so the pressure inside the steam condensation heat transfer tube decreases rapidly. When the pressure inside the steam condensation heat transfer tube becomes lower than the water pressure in the heat transfer tube cooling pool at time T3, the cooling water stored in the heat transfer tube cooling pool flows into the steam condensation heat transfer tube through the pool water intake tube. Pool water inlet pipe is loop side (reactor or steam generator and pipe closed loop side made by steam inlet pipe, steam condensing heat transfer pipe and condensed water return pipe, steam inlet control valve to condensed water return control valve If the connection position is increased, the effect of cooling the inside of the heat transfer tube with the cooling water drawn from the pool water intake pipe can be obtained. Since the pool water pressure can be increased, the pool water can be drawn into the steam condensation heat transfer tube at an earlier timing. The connection position on the loop side of the pool water intake pipe needs to be determined in consideration of the heat transfer area of the steam condensation heat transfer pipe, the water depth of the heat transfer pipe cooling pool, and the like. The amount of cooling water stored inside the steam condensation heat transfer tube is sensed by a differential pressure gauge for water level measurement and input to the steam pull-in controller. The steam intake controller determines whether the amount of stored cooling water is sufficient. When it is determined that a sufficient amount of water has accumulated at time T4, the steam intake control valve 9 is opened again. By opening the steam drawing control valve, the cooling water can be supplied into the reactor pressure vessel by the head pressure of the cooling water stored in the steam condensation heat transfer tube. By repeatedly opening and closing the steam intake control valve, a large amount of cooling water can be supplied into the reactor pressure vessel in the same procedure. In order to inject a large amount of cooling water in a single operation, it is effective to enlarge the upper header and the lower header to which the steam condensation heat transfer tube is connected, for example.
図3に第1実施例を用いる場合の凝縮水制御弁および蒸気引き込み制御弁の制御ロジックの一例を示す。   FIG. 3 shows an example of the control logic of the condensate control valve and the steam intake control valve when the first embodiment is used.
まず手順1で、実施例1の注水装置に装置作動信号が入力すると信号線26を介して、凝縮水制御弁8を開く。装置作動信号は、原子炉圧力容器内の水位,出力,圧力,温度や、原子炉格納容器内の圧力,温度などの異常を検知した場合や、運転員の手動によって、例えば制御室コンピュータ18から発せられる。次に手順2で、水位計測用差圧計の出力値を、差圧水量換算器19で蒸気凝縮伝熱管内部に貯まった冷却水量に変換する。圧力から冷却水量への変換は次のように単純な計算で実現できる。水位計測用差圧計で測定した差圧を冷却水の密度と重力加速度で割れば現在の蒸気凝縮伝熱管内の水位が求まる。各高さにおける蒸気凝縮伝熱管内の断面積は設計時に分かっているため、水位で断面積を積分すれば現在貯まっている冷却水量が求まる。冷却水の密度は圧力と温度に依存するため、より正確な制御が必要な場合は、冷却水の圧力と温度も測定して冷却水の密度を算出すれば良い。手順3で、差圧水量換算器で求めた蒸気凝縮伝熱管内の冷却水量が十分に小さければ、蒸気凝縮伝熱管内に貯めた冷却水の注水は終わったと判断し、蒸気引き込み制御弁を閉じることで蒸気凝縮伝熱管内にプール水を引き込む準備をする。逆に、冷却水量が十分に大きければ、蒸気凝縮伝熱管内に十分な冷却水が貯まったと判断し、蒸気引き込み制御弁を開くことで原子炉圧力容器内部への注水を開始する。その後は、手順2と手順3を繰り返すことで蒸気引き込み制御弁を開閉制御する。水位に基づいた開閉制御を行うことで、効率的で確実な注入が可能となる。   First, in step 1, when a device operation signal is input to the water injection apparatus of the first embodiment, the condensed water control valve 8 is opened via the signal line 26. The device operation signal is generated when an abnormality such as the water level, output, pressure, temperature in the reactor pressure vessel, pressure, temperature, etc. in the reactor containment vessel is detected or manually by the operator, for example, from the control room computer 18. Be emitted. Next, in step 2, the output value of the differential pressure gauge for water level measurement is converted by the differential pressure water amount converter 19 into the amount of cooling water stored inside the steam condensation heat transfer tube. The conversion from the pressure to the cooling water amount can be realized by a simple calculation as follows. Dividing the differential pressure measured by the differential pressure gauge for measuring the water level by the density of the cooling water and the acceleration of gravity gives the water level in the current steam condensation heat transfer tube. Since the cross-sectional area in the steam condensation heat transfer tube at each height is known at the time of design, the amount of cooling water currently stored can be obtained by integrating the cross-sectional area at the water level. Since the density of the cooling water depends on the pressure and temperature, when more accurate control is required, the density and the cooling water may be calculated by measuring the pressure and temperature of the cooling water. If the amount of cooling water in the steam condensing heat transfer tube obtained by the differential pressure water amount converter in step 3 is sufficiently small, it is determined that the cooling water stored in the steam condensing heat transfer tube has been injected, and the steam intake control valve is closed. This prepares to draw pool water into the steam condensation heat transfer tube. Conversely, if the amount of cooling water is sufficiently large, it is determined that sufficient cooling water has accumulated in the steam condensing heat transfer tube, and water injection into the reactor pressure vessel is started by opening the steam drawing control valve. Thereafter, procedure 2 and procedure 3 are repeated to open and close the steam intake control valve. By performing open / close control based on the water level, efficient and reliable injection is possible.
本実施例では上述のような注水手段が確保できるが、注水は必要なく、原子炉内部で発生した熱を除去するだけで良い場合は、蒸気引き込み制御弁の制御をせず、蒸気引き込み制御弁を開状態で固定すれば従来から実績のあるICとして利用できる。また、プール水引き込み管から凝縮水戻し管を通して原子炉圧力容器に接続する構成は、プール水の水頭圧を利用して原子炉圧力容器内部に冷却材を注水する重力落下式注水設備(GDCS)と同じである。よって、原子炉内部の圧力が大気圧近くまで減少した後は、伝熱管冷却プールの水圧のみで連続的に原子炉圧力容器内部に注水できる。すなわち、本実施例は高圧時の注水機能,高圧時のICの除熱機能,低圧時のGDCSの連続注水機能を1つの設備で実現可能である。   In this embodiment, the water injection means as described above can be secured, but when the water injection is not necessary and it is only necessary to remove the heat generated inside the nuclear reactor, the steam intake control valve is not controlled. Can be used as an IC with a proven track record. In addition, the configuration of connecting from the pool water intake pipe to the reactor pressure vessel through the condensed water return tube is a gravity drop type water injection system (GDCS) that injects coolant into the reactor pressure vessel using the head pressure of the pool water. Is the same. Therefore, after the pressure inside the reactor has decreased to near atmospheric pressure, water can be continuously poured into the reactor pressure vessel only by the water pressure in the heat transfer tube cooling pool. That is, in this embodiment, the water injection function at high pressure, the IC heat removal function at high pressure, and the continuous water injection function of GDCS at low pressure can be realized with one facility.
図4に第2実施例を示す。   FIG. 4 shows a second embodiment.
本実施例は第1実施例とは、プール水引き込み管が接続するプールが異なる。凝縮水制御弁および蒸気引き込み制御弁の制御ロジックは第1実施例と同じである。   This embodiment differs from the first embodiment in the pool to which the pool water inlet pipe is connected. The control logic of the condensate control valve and the steam intake control valve is the same as in the first embodiment.
本実施例では、プール水引き込み管は伝熱管冷却プールとは別の冷却水供給プール20に接続する。第1実施例の構成は必要なプールが1つであるため単純であり、設備の物量を小さくできるメリットがあるが、原子炉圧力容器に冷却水を供給して行くに従って伝熱管冷却プールの水量が減少していくため、大量の冷却水を注水すると蒸気凝縮伝熱管の冷却に支障がでる可能性がある。第2実施例では注水する冷却水と蒸気凝縮伝熱管を冷却する水は別であるため、このような心配がない。また第2実施例の構成を取り、冷却水供給プールを伝熱管冷却プールよりも上方に設置すれば、プールの水圧を大きく取れるため、第1実施例よりも迅速にプール水を蒸気凝縮伝熱管内に取り込めるようになる。そのため、冷却水供給プールは伝熱管冷却プールよりも上方に設置した方が、第2実施例のメリットを増大できる。第1実施例の説明で記載したとおり伝熱管冷却プールの通常運転時水位は原子炉圧力容器内部の通常運転時水位よりも高くする方が望ましいため、冷却水供給プールの通常運転時水位25cも原子炉圧力容器内部の通常運転時水位よりも高い方が良い。本実施例では、冷却水供給プールは原子炉格納容器内部に設置した例を示したが、冷却水供給プールを原子炉圧力容器外部に設置しても良い。   In this embodiment, the pool water inlet pipe is connected to a cooling water supply pool 20 that is different from the heat transfer pipe cooling pool. The configuration of the first embodiment is simple because only one pool is required, and there is an advantage that the amount of equipment can be reduced. However, as the cooling water is supplied to the reactor pressure vessel, the amount of water in the heat transfer tube cooling pool is increased. Therefore, if a large amount of cooling water is injected, cooling of the steam condensation heat transfer tubes may be hindered. In the second embodiment, since the cooling water to be injected and the water to cool the steam condensation heat transfer tube are different, there is no such concern. Moreover, if the structure of 2nd Example is taken and a cooling water supply pool is installed upwards rather than a heat exchanger tube cooling pool, since the water pressure of a pool can be taken large, steam condensation heat transfer from pool water is quicker than 1st Example. It can be taken into the tube. Therefore, the merit of the second embodiment can be increased if the cooling water supply pool is installed above the heat transfer tube cooling pool. As described in the description of the first embodiment, since the water level during normal operation of the heat transfer tube cooling pool is preferably higher than the water level during normal operation inside the reactor pressure vessel, the water level 25c during normal operation of the cooling water supply pool is also It should be higher than the water level during normal operation inside the reactor pressure vessel. In this embodiment, the cooling water supply pool is installed inside the reactor containment vessel, but the cooling water supply pool may be installed outside the reactor pressure vessel.
図5に第3実施例を示す。   FIG. 5 shows a third embodiment.
本実施例は第1実施例とは、凝縮水戻し管上の弁構成が異なる。凝縮水戻し管上には凝縮水制御弁のみが必須であり、凝縮水逆止弁は無くても良い。第3実施例は第1実施例に比較して凝縮水戻し管上の弁構成を単純化できるメリットがある。   This embodiment differs from the first embodiment in the valve configuration on the condensed water return pipe. Only the condensed water control valve is essential on the condensed water return pipe, and the condensed water check valve may not be provided. 3rd Example has the merit which can simplify the valve structure on a condensed-water return pipe | tube compared with 1st Example.
図6に第3実施例を用いる場合の凝縮水制御弁および蒸気引き込み制御弁の制御ロジックの一例を示す。   FIG. 6 shows an example of the control logic of the condensate control valve and the steam intake control valve when the third embodiment is used.
まず手順1で、注水装置に装置作動信号が入力すると、凝縮水制御弁を開く。装置作動信号は、原子炉圧力容器内の水位,出力,圧力,温度や、原子炉格納容器内の圧力,温度などの異常を検知した場合や、運転員の手動によって例えば制御室コンピュータ18から発せられる。次に手順2で、水位計測用差圧計の出力値を、差圧水量換算器19で蒸気凝縮伝熱管内部に貯まった冷却水量に変換する。圧力から冷却水量への変換は次のように単純な計算で実現できる。水位計測用差圧計で測定した差圧を冷却水の密度と重力加速度で割れば現在の蒸気凝縮伝熱管内の水位が求まる。各高さにおける蒸気凝縮伝熱管内の断面積は設計時に分かっているため、水位で断面積を積分すれば現在貯まっている冷却水量が求まる。冷却水の密度は圧力と温度に依存するため、より正確な制御が必要な場合は、冷却水の圧力と温度も測定して冷却水の密度を算出すれば良い。手順3で、差圧水量換算器で求めた蒸気凝縮伝熱管内の冷却水量が十分に小さければ、蒸気凝縮伝熱管内に貯めた冷却水の注水は終わったと判断し、凝縮水制御弁と蒸気引き込み制御弁の両方を閉じることで蒸気凝縮伝熱管内にプール水を引き込む準備をする。逆に、冷却水量が十分に大きければ、蒸気凝縮伝熱管内に十分な冷却水が貯まったと判断し、凝縮水制御弁と蒸気引き込み制御弁の両方を開くことで原子炉圧力容器内部への注水を開始する。その後は、手順2と手順3を繰り返すことで凝縮水制御弁と蒸気引き込み制御弁を開閉制御する。これにより、原子炉又は蒸気発生器に効率的で確実な注入が可能となる。   First, in step 1, when a device operation signal is input to the water injection device, the condensate control valve is opened. The device operation signal is generated from the control room computer 18 when an abnormality such as the water level, output, pressure, temperature in the reactor pressure vessel, pressure, temperature, etc. in the reactor containment vessel is detected, or manually by the operator. It is done. Next, in step 2, the output value of the differential pressure gauge for water level measurement is converted by the differential pressure water amount converter 19 into the amount of cooling water stored inside the steam condensation heat transfer tube. The conversion from the pressure to the cooling water amount can be realized by a simple calculation as follows. Dividing the differential pressure measured by the differential pressure gauge for measuring the water level by the density of the cooling water and the acceleration of gravity gives the water level in the current steam condensation heat transfer tube. Since the cross-sectional area in the steam condensation heat transfer tube at each height is known at the time of design, the amount of cooling water currently stored can be obtained by integrating the cross-sectional area at the water level. Since the density of the cooling water depends on the pressure and temperature, when more accurate control is required, the density and the cooling water may be calculated by measuring the pressure and temperature of the cooling water. If the amount of cooling water in the steam condensing heat transfer tube obtained by the differential pressure water amount converter in step 3 is sufficiently small, it is determined that the cooling water stored in the steam condensing heat transfer tube has been injected, and the condensate control valve and steam Prepare to draw pool water into the steam condensing heat transfer tube by closing both draw-in control valves. Conversely, if the amount of cooling water is sufficiently large, it is determined that sufficient cooling water has accumulated in the steam condensing heat transfer tube, and both the condensate control valve and the steam pull-in control valve are opened to inject water into the reactor pressure vessel. To start. After that, the condensate control valve and the steam intake control valve are controlled to open and close by repeating steps 2 and 3. This enables efficient and reliable injection into the nuclear reactor or steam generator.
プール水引き込み管を接続する冷却材を貯蔵しているプールは、第1実施例と同じく伝熱管冷却プールとしても良いし、第2実施例と同じく伝熱管冷却プールとは別の冷却水供給プールとしても良い。   The pool that stores the coolant that connects the pool water inlet pipe may be a heat transfer tube cooling pool as in the first embodiment, or a cooling water supply pool that is different from the heat transfer tube cooling pool as in the second embodiment. It is also good.
図7に第4実施例を示す。   FIG. 7 shows a fourth embodiment.
本実施例は第1実施例とは、プール水引き込み制御弁13の種類と制御が異なる。凝縮水制御弁および蒸気引き込み制御弁の制御ロジックは第1実施例と同じである。プール水引き込み制御弁は開閉制御のできる弁とする。また、プール水引き込み制御弁の上流側と下流側の圧力差を、プール水引き込み制御弁差圧計21で計測する。プール水引き込み制御弁差圧計で計測した差圧を、プール水引き込み制御器22に入力する。プール水引き込み制御器は入力した差圧に基づいてプール水引き込み制御弁を開閉制御する。第4実施例は第1実施例と比較して、制御によって原子炉圧力容器内部の蒸気が伝熱管冷却プールに流出する可能性を確実に排除できるメリットがある。   This embodiment is different from the first embodiment in the type and control of the pool water draw-in control valve 13. The control logic of the condensate control valve and the steam intake control valve is the same as in the first embodiment. The pool water draw-in control valve is a valve that can be opened and closed. Further, the pressure difference between the upstream side and the downstream side of the pool water draw-in control valve is measured by the pool water draw-in control valve differential pressure gauge 21. The differential pressure measured by the pool water draw-in control valve differential pressure gauge is input to the pool water draw-in controller 22. The pool water draw-in controller controls opening and closing of the pool water draw-in control valve based on the input differential pressure. Compared with the first embodiment, the fourth embodiment has an advantage that the possibility of the steam inside the reactor pressure vessel flowing out to the heat transfer tube cooling pool can be reliably excluded by the control.
図8に第4実施例を用いる場合のプール水引き込み制御弁の制御ロジックの一例を示す。
まず手順1で、注水装置に装置作動信号が入力すると、制御を開始する。装置作動信号は、原子炉圧力容器内の水位,出力,圧力,温度や、原子炉格納容器内の圧力,温度などの異常を検知した場合や、運転員の手動によって例えば制御室コンピュータ18から発せられる。次に手順2で、プール水引き込み制御弁差圧計の計測値をプール水引き込み制御器に入力する。差圧計の測定値は例えば、プール水側の圧力が蒸気凝縮伝熱管側の圧力よりも高ければ正の値、逆にプール水側の圧力が蒸気凝縮伝熱管側の圧力よりも低ければ負の値とする。手順3で、差圧が正であればプール水引き込み制御弁を開き、差圧が負であればプール水引き込み制御弁を閉じる。その後は、手順2と手順3を繰り返すことでプール水引き込み制御弁を開閉制御する。
FIG. 8 shows an example of the control logic of the pool water draw-in control valve when the fourth embodiment is used.
First, in step 1, when a device operation signal is input to the water injection device, control is started. The device operation signal is generated from the control room computer 18 when an abnormality such as the water level, output, pressure, temperature in the reactor pressure vessel, pressure, temperature, etc. in the reactor containment vessel is detected, or manually by the operator. It is done. Next, in step 2, the measured value of the pool water pull-in control valve differential pressure gauge is input to the pool water pull-in controller. The measured value of the differential pressure gauge is, for example, a positive value if the pressure on the pool water side is higher than the pressure on the steam condensation heat transfer tube side, and negative if the pressure on the pool water side is lower than the pressure on the steam condensation heat transfer tube side. Value. In step 3, if the differential pressure is positive, the pool water draw-in control valve is opened, and if the differential pressure is negative, the pool water draw-in control valve is closed. Thereafter, the procedure 2 and 3 are repeated to control the opening and closing of the pool water intake control valve.
プール水引き込み管を接続する冷却材を貯蔵しているプールは、第1実施例と同じく伝熱管冷却プールとしても良いし、第2実施例と同じく伝熱管冷却プールとは別の冷却水供給プールとしても良い。凝縮水制御弁の構成は第1実施例と同じく、開閉制御できる弁と逆止弁の組み合わせでも良いし、第3実施例と同じく開閉制御できる弁1弁のみでも良い。   The pool that stores the coolant that connects the pool water inlet pipe may be a heat transfer tube cooling pool as in the first embodiment, or a cooling water supply pool that is different from the heat transfer tube cooling pool as in the second embodiment. It is also good. The configuration of the condensed water control valve may be a combination of a valve that can be controlled to open and close and a check valve, as in the first embodiment, or may be only one valve that can be controlled to open and close as in the third embodiment.
次に、間接サイクル型原子力プラントの一つである加圧水型軽水炉(PWR)に適用した場合の例を示す。   Next, an example of applying to a pressurized water reactor (PWR) which is one of indirect cycle nuclear power plants will be shown.
図9に第5実施例を示す。本実施例は、PWRに適用したものであるため、原子炉圧力容器には蒸気発生器23が接続されているが、蒸気引き込み管および凝縮水戻し管は原子炉圧力容器に接続されており、装置の構成は第1実施例と同じである。第1実施例のBWRでは、蒸気引き込み管は原子炉圧力容器の通常運転時水位より上部に、凝縮水戻し管は原子炉圧力容器の通常運転時水位より下部に接続したが、PWRでは通常運転中は原子炉圧力容器内部に液相の水のみが存在し、水位は存在しない。注水装置が働くためには蒸気を引き込む必要があるため、冷却材喪失事故発生時など、PWRの原子炉圧力容器内部にも水位が存在する場合に作動する。この場合、原子炉圧力容器のダウンカマ24の上端より上方は蒸気部分に接している頻度が高いため、蒸気引き込み管は一例としてはダウンカマ上端よりも上方の位置に接続する。逆に凝縮水戻し管は一例としてはダウンカマ上端よりも下方に接続する。   FIG. 9 shows a fifth embodiment. Since this embodiment is applied to the PWR, the steam generator 23 is connected to the reactor pressure vessel, but the steam inlet pipe and the condensed water return pipe are connected to the reactor pressure vessel. The configuration of the apparatus is the same as that of the first embodiment. In the BWR of the first embodiment, the steam inlet pipe is connected above the water level during normal operation of the reactor pressure vessel, and the condensed water return pipe is connected below the water level during normal operation of the reactor pressure vessel. There is only liquid phase water inside the reactor pressure vessel, and no water level. Since it is necessary to draw steam in order for the water injection device to work, it operates when the water level is also present inside the reactor pressure vessel of the PWR, such as when a coolant loss accident occurs. In this case, since the frequency above the upper end of the downcomer 24 of the reactor pressure vessel is in contact with the steam portion is high, the steam intake pipe is connected to a position above the upper end of the downcomer as an example. On the contrary, the condensed water return pipe is connected below the upper end of the downcomer as an example.
凝縮水制御弁および蒸気引き込み制御弁の制御ロジックは第1実施例と同じである。   The control logic of the condensate control valve and the steam intake control valve is the same as in the first embodiment.
プール水引き込み管を接続する冷却材を貯蔵しているプールは、第1実施例と同じく伝熱管冷却プールとしても良いし、第2実施例と同じく伝熱管冷却プールとは別の冷却水供給プールとしても良い。凝縮水制御弁の構成は第1実施例と同じく、開閉制御できる弁と逆止弁の組み合わせでも良いし、第3実施例と同じく開閉制御できる弁1弁のみでも良い。プール水引き込み制御弁は第1実施例と同じく逆止弁でも良いし、第4実施例と同じく開閉制御できる弁でも良い。   The pool that stores the coolant that connects the pool water inlet pipe may be a heat transfer tube cooling pool as in the first embodiment, or a cooling water supply pool that is different from the heat transfer tube cooling pool as in the second embodiment. It is also good. The configuration of the condensed water control valve may be a combination of a valve that can be controlled to open and close and a check valve, as in the first embodiment, or may be only one valve that can be controlled to open and close as in the third embodiment. The pool water intake control valve may be a check valve as in the first embodiment, or may be a valve that can be controlled to open and close as in the fourth embodiment.
図10に第6実施例を示す。本実施例は、PWRの蒸気発生器に適用したものである。装置の構成は第1実施例と同じであり、蒸気引き込み管は蒸気発生器の通常運転時水位より上方に接続され、凝縮水戻し管は蒸気発生器の通常運転時水位25dより下方に接続される。   FIG. 10 shows a sixth embodiment. The present embodiment is applied to a PWR steam generator. The configuration of the apparatus is the same as in the first embodiment, the steam inlet pipe is connected above the water level during normal operation of the steam generator, and the condensed water return pipe is connected below the water level 25d during normal operation of the steam generator. The
凝縮水制御弁および蒸気引き込み制御弁の制御ロジックは第1実施例と同じである。   The control logic of the condensate control valve and the steam intake control valve is the same as in the first embodiment.
プール水引き込み管を接続する冷却材を貯蔵しているプールは、第1実施例と同じく伝熱管冷却プールとしても良いし、第2実施例と同じく伝熱管冷却プールとは別の冷却水供給プールとしても良い。凝縮水制御弁の構成は第1実施例と同じく、開閉制御できる弁と逆止弁の組み合わせでも良いし、第3実施例と同じく開閉制御できる弁1弁のみでも良い。プール水引き込み制御弁は第1実施例と同じく逆止弁でも良いし、第4実施例と同じく開閉制御できる弁でも良い。   The pool that stores the coolant that connects the pool water inlet pipe may be a heat transfer tube cooling pool as in the first embodiment, or a cooling water supply pool that is different from the heat transfer tube cooling pool as in the second embodiment. It is also good. The configuration of the condensed water control valve may be a combination of a valve that can be controlled to open and close and a check valve, as in the first embodiment, or may be only one valve that can be controlled to open and close as in the third embodiment. The pool water intake control valve may be a check valve as in the first embodiment, or may be a valve that can be controlled to open and close as in the fourth embodiment.
原子力プラントの第1実施例。1st Example of a nuclear power plant. 蒸気引き込み管と凝縮水戻し管の質量流量の時系列変化の一例。An example of a time-series change of mass flow rate of a steam drawing pipe and a condensed water return pipe. 第1実施例を用いる場合の凝縮水制御弁および蒸気引き込み制御弁の制御ロジックの一例。An example of the control logic of a condensed water control valve in the case of using a 1st Example and a steam drawing-in control valve. 原子力プラントの第2実施例。2nd Example of a nuclear power plant. 原子力プラントの第3実施例。3rd Example of a nuclear power plant. 第3実施例を用いる場合の凝縮水制御弁および蒸気引き込み制御弁の制御ロジックの一例。An example of the control logic of a condensed water control valve and a steam drawing control valve in the case of using 3rd Example. 原子力プラントの第4実施例。4th Example of a nuclear power plant. 第4実施例を用いる場合のプール水引き込み制御弁の制御ロジックの一例。An example of the control logic of the pool water drawing-in control valve in the case of using 4th Example. 原子力プラントの第5実施例。5th Example of a nuclear power plant. 原子力プラントの第6実施例。6th Example of a nuclear power plant.
符号の説明Explanation of symbols
1 原子炉圧力容器
2 蒸気引き込み管
3 上部ヘッダ
4 蒸気凝縮伝熱管
5 下部ヘッダ
6 凝縮水戻し管
7 伝熱管冷却プール
8 凝縮水制御弁
9 蒸気引き込み制御弁
10 凝縮水逆止弁
11 プール水引き込み管
12 水位測定用差圧計
13 プール水引き込み制御弁
14 蒸気引き込み制御器
15 原子炉格納容器壁面
16 主蒸気管
17 主給水管
18 制御室コンピュータ
19 差圧水量換算器
20 冷却水供給プール
21 プール水引き込み制御弁差圧計
22 プール水引き込み制御器
23 蒸気発生器
24 ダウンカマ
25a 原子炉圧力容器内部の通常運転時水位
25b 伝熱管冷却プール内の通常運転時水位
25c 冷却水供給プールの通常運転時水位
25d 蒸気発生器の通常運転時水位
26 信号線
27 一次系出口配管
28 一次系入口配管
DESCRIPTION OF SYMBOLS 1 Reactor pressure vessel 2 Steam intake pipe 3 Upper header 4 Steam condensation heat transfer pipe 5 Lower header 6 Condensate return pipe 7 Heat transfer pipe cooling pool 8 Condensate control valve 9 Steam intake control valve 10 Condensate check valve 11 Pool water intake Pipe 12 Differential pressure gauge for water level measurement 13 Pool water drawing control valve 14 Steam drawing controller 15 Reactor containment wall 16 Main steam pipe 17 Main water supply pipe 18 Control room computer 19 Differential pressure water amount converter 20 Cooling water supply pool 21 Pool water Pull-in control valve differential pressure gauge 22 Pool water pull-in controller 23 Steam generator 24 Downcomer 25a Water level 25b during normal operation inside reactor pressure vessel Water level 25c during normal operation in heat transfer tube cooling pool Water level 25d during normal operation of cooling water supply pool Normal level of steam generator 26 Signal line 27 Primary system outlet piping 28 Primary system inlet piping

Claims (16)

  1. 原子炉と、
    該原子炉から蒸気を抜き取る蒸気引き込み管と、
    該蒸気引き込み管に接続され引き込んだ蒸気を凝縮する蒸気凝縮伝熱管と、
    該蒸気凝縮伝熱管に接続され前記蒸気凝縮伝熱管内で凝縮した蒸気のドレンを前記原子炉に戻す凝縮水戻し管と、
    内部に水を貯蔵し前記蒸気凝縮伝熱管をその水中に設置する伝熱管冷却プールとを有し、
    前記蒸気引き込み管上には蒸気引き込み制御弁を備え、
    前記凝縮水戻し管上には凝縮水制御弁を備え、
    プール水引き込み管は、前記蒸気引き込み管又は前記蒸気凝縮伝熱管又は前記凝縮水戻し管の前記蒸気引き込み制御弁より下流側で前記凝縮水制御弁より上流側に接続され、前記プール水引き込み管の残りの一方は前記伝熱管冷却プール又は給水プールの通常運転時水位よりも下の位置に接続され、
    前記プール水引き込み管上にはプール水引き込み制御弁を備えることを特徴とする原子力プラント。
    A nuclear reactor,
    A steam inlet pipe for extracting steam from the reactor;
    A steam condensing heat transfer tube connected to the steam drawing tube and condensing the drawn steam;
    A condensed water return pipe connected to the steam condensation heat transfer pipe and returning the drain of the steam condensed in the steam condensation heat transfer pipe to the reactor;
    A heat transfer tube cooling pool for storing water therein and installing the steam condensation heat transfer tube in the water;
    A steam suction control valve is provided on the steam suction pipe,
    A condensed water control valve is provided on the condensed water return pipe,
    The pool water inlet pipe is connected to the steam inlet pipe, the steam condensation heat transfer pipe, or the condensed water return pipe downstream from the steam inlet control valve and upstream from the condensed water control valve. The remaining one is connected to a position below the water level during normal operation of the heat transfer tube cooling pool or water supply pool,
    A nuclear power plant comprising a pool water drawing control valve on the pool water drawing pipe.
  2. 原子炉と、
    該原子炉に接続され、原子炉で発生した熱を用いて蒸気を発生させる蒸気発生器と、
    該蒸気発生器から蒸気を抜き取る蒸気引き込み管と、
    該蒸気引き込み管に接続され引き込んだ蒸気を凝縮する蒸気凝縮伝熱管と、
    該蒸気凝縮伝熱管に接続され前記蒸気凝縮伝熱管内で凝縮した蒸気のドレンを前記蒸気発生器に戻す凝縮水戻し管と、
    内部に水を貯蔵し前記蒸気凝縮伝熱管をその水中に設置するための伝熱管冷却プールとを有し、
    前記蒸気引き込み管上には蒸気引き込み制御弁を備え、
    前記凝縮水戻し管上には凝縮水制御弁を備え、
    プール水引き込み管は、前記蒸気引き込み管又は前記蒸気凝縮伝熱管又は前記凝縮水戻し管の前記蒸気引き込み制御弁より下流側で前記凝縮水制御弁より上流側に接続され、前記プール水引き込み管の残りの一方は前記伝熱管冷却プール又は給水プールの通常運転時水位よりも下の位置に接続され、
    前記プール水引き込み管上にはプール水引き込み制御弁を備えることを特徴とする原子力プラント。
    A nuclear reactor,
    A steam generator connected to the reactor and generating steam using heat generated in the reactor;
    A steam inlet pipe for extracting steam from the steam generator;
    A steam condensing heat transfer tube connected to the steam drawing tube and condensing the drawn steam;
    A condensed water return pipe connected to the steam condensation heat transfer pipe and returning the drain of the steam condensed in the steam condensation heat transfer pipe to the steam generator;
    A heat transfer tube cooling pool for storing water inside and installing the steam condensation heat transfer tube in the water,
    A steam suction control valve is provided on the steam suction pipe,
    A condensed water control valve is provided on the condensed water return pipe,
    The pool water inlet pipe is connected to the steam inlet pipe, the steam condensation heat transfer pipe, or the condensed water return pipe downstream from the steam inlet control valve and upstream from the condensed water control valve. The remaining one is connected to a position below the water level during normal operation of the heat transfer tube cooling pool or water supply pool,
    A nuclear power plant comprising a pool water drawing control valve on the pool water drawing pipe.
  3. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記プール水引き込み管の残りの一方を前記伝熱管冷却プールに接続したことを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    A nuclear power plant characterized in that the other one of the pool water inlet pipes is connected to the heat transfer pipe cooling pool.
  4. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記プール水引き込み管の残りの一方を前記給水プールに接続したことを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    A nuclear power plant characterized in that the other one of the pool water intake pipes is connected to the water supply pool.
  5. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記蒸気引き込み制御弁は、前記凝縮水戻し管内又は前記蒸気凝縮伝熱管内の水位に基づいて開閉制御される蒸気引き込み制御器を有することを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    The nuclear power plant, wherein the steam drawing control valve includes a steam drawing controller that is controlled to open and close based on a water level in the condensed water return pipe or the steam condensed heat transfer pipe.
  6. 請求項4に記載の原子力プラントにおいて、
    前記凝縮水戻し管内又は前記蒸気凝縮伝熱管内の水位は、前記凝縮水戻し管内又は前記蒸気凝縮伝熱管内の圧力、又は前記凝縮水戻し管内の圧力と前記蒸気引き込み管又は前記蒸気凝縮伝熱管内の圧力との差圧に基づいて算出することを特徴とする原子力プラント。
    In the nuclear power plant according to claim 4,
    The water level in the condensed water return pipe or the steam condensation heat transfer pipe is determined by the pressure in the condensed water return pipe or the steam condensation heat transfer pipe, or the pressure in the condensed water return pipe and the steam suction pipe or the steam condensation heat transfer. A nuclear power plant that is calculated based on a differential pressure from the pressure in the pipe.
  7. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記凝縮水戻し管上には前記蒸気凝縮伝熱管から前記凝縮水戻し管へと流れる方向の冷却材流れのみを通す逆止弁を設けた原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    A nuclear power plant in which a check valve is provided on the condensed water return pipe to allow only a coolant flow in a direction flowing from the steam condensation heat transfer pipe to the condensed water return pipe.
  8. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記プール水引き込み管上のプール水引き込み制御弁は、前記給水プールから前記プール水引き込み管へと流れる方向の冷却材流れのみを通す逆止弁であることを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    The nuclear power plant, wherein the pool water intake control valve on the pool water intake pipe is a check valve that allows only a coolant flow in a direction flowing from the water supply pool to the pool water intake pipe.
  9. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記プール水引き込み制御弁は、プール水引き込み制御弁の上流側と下流側の圧力差によって開閉制御する制御器を有することを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    The nuclear water plant, wherein the pool water draw-in control valve has a controller that controls opening and closing by a pressure difference between an upstream side and a downstream side of the pool water draw-in control valve.
  10. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記給水プールの通常運転時水位は、前記原子炉内又は前記蒸気発生器内の通常運転時の水位よりも高いことを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    The nuclear power plant, wherein the water level during normal operation of the water supply pool is higher than the water level during normal operation in the nuclear reactor or the steam generator.
  11. 請求項1又は請求項2に記載の原子力プラントにおいて、
    前記原子炉内の通常運転時の水位は、前記伝熱管冷却プールの通常運転時水位よりも低いことを特徴とする原子力プラント。
    In the nuclear power plant according to claim 1 or claim 2,
    A nuclear power plant, wherein a water level during normal operation in the nuclear reactor is lower than a water level during normal operation of the heat transfer tube cooling pool.
  12. 原子炉又は蒸気発生器から伝熱管内に蒸気を引き込み、
    前記伝熱管内に引き込んだ蒸気を貯めた状態で、前記伝熱管を前記原子炉又は前記蒸気発生器と隔離し、前記伝熱管内に引き込んだ蒸気を凝縮させ、
    前記伝熱管外部に設置したプールから前記伝熱管内に冷却水を引き込み、
    再度、前記原子炉又は前記蒸気発生器から前記伝熱管内に蒸気を引き込み、前記伝熱管内に引き込んだ冷却水を水頭により前記原子炉又は前記蒸気発生器に供給することを特徴とする原子力プラントの制御方法。
    Draw steam from the reactor or steam generator into the heat transfer tube,
    With the steam drawn into the heat transfer tube being stored, the heat transfer tube is isolated from the reactor or the steam generator, and the steam drawn into the heat transfer tube is condensed,
    Cooling water is drawn into the heat transfer tube from a pool installed outside the heat transfer tube,
    A nuclear power plant, wherein steam is again drawn into the heat transfer tube from the reactor or the steam generator, and cooling water drawn into the heat transfer tube is supplied to the reactor or the steam generator by a water head. Control method.
  13. 請求項12に記載の原子力プラントの制御方法において、
    前記隔離は
    前記原子炉又は前記蒸気発生器から蒸気を抜き取る蒸気引き込み管上に設けた蒸気引き込み制御弁と、蒸気凝縮伝熱管内で凝縮した蒸気のドレンを前記原子炉又は前記蒸気発生器に戻す凝縮水戻し管上に設けた凝縮水制御弁を閉状態とすることを特徴とする原子力プラントの制御方法。
    The method for controlling a nuclear power plant according to claim 12,
    The isolation includes a steam drawing control valve provided on a steam drawing pipe for extracting steam from the nuclear reactor or the steam generator, and a steam drain condensed in the steam condensation heat transfer pipe is returned to the reactor or the steam generator. A control method for a nuclear power plant, wherein a condensate control valve provided on a condensate return pipe is closed.
  14. 請求項12に記載の原子力プラントの制御方法において、
    前記隔離、その後、蒸気を引き込むことを繰り返すことにより、前記原子炉又は前記蒸気発生器に冷却水を供給する原子力プラントの制御方法。
    The method for controlling a nuclear power plant according to claim 12,
    A method for controlling a nuclear power plant that supplies cooling water to the nuclear reactor or the steam generator by repeating the isolation and then drawing in steam.
  15. 請求項14に記載の原子力プラントの制御方法において、
    前記隔離、その後、蒸気を引き込む操作は蒸気引き込み制御弁と、前記凝縮水制御弁を閉又は開動作することで行う原子力プラントの制御方法。
    The method for controlling a nuclear power plant according to claim 14,
    The nuclear plant control method in which the operation of drawing the steam after the isolation is performed by closing or opening the steam suction control valve and the condensed water control valve.
  16. 請求項12乃至請求項15に記載の原子力プラントの制御方法において、
    前記凝縮は、伝熱管冷却プール内に前記伝熱管を設けることにより行う原子力プラントの制御方法。
    The nuclear power plant control method according to any one of claims 12 to 15,
    The said condensation is a control method of the nuclear power plant performed by providing the said heat exchanger tube in a heat exchanger tube cooling pool.
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JP2014506998A (en) * 2011-02-15 2014-03-20 ニュースケール パワー エルエルシー Heat removal system and method for use in nuclear reactors
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WO2013081148A1 (en) * 2011-12-02 2013-06-06 三菱重工業株式会社 Fluid cooling device, static heat removal device, nuclear plant with fluid cooling device, and nuclear plant with static heat removal device
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CN107112059A (en) * 2014-10-22 2017-08-29 韩国原子力研究院 Stop cooling system and the nuclear facilities with the stopping cooling system
CN107112059B (en) * 2014-10-22 2020-06-30 韩国原子力研究院 Shutdown cooling system and nuclear facility with same
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