JP6941081B2 - Auxiliary cooling equipment for nuclear power plants - Google Patents

Auxiliary cooling equipment for nuclear power plants Download PDF

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JP6941081B2
JP6941081B2 JP2018135657A JP2018135657A JP6941081B2 JP 6941081 B2 JP6941081 B2 JP 6941081B2 JP 2018135657 A JP2018135657 A JP 2018135657A JP 2018135657 A JP2018135657 A JP 2018135657A JP 6941081 B2 JP6941081 B2 JP 6941081B2
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cooling
circulation pump
branch pipe
heat exchanger
auxiliary
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JP2020012749A (en
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莉沙子 毛笠
莉沙子 毛笠
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Hitachi GE Nuclear Energy Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/04—Pumping arrangements
    • 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
    • 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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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Other Air-Conditioning Systems (AREA)

Description

本発明は、原子力プラントの補機冷却設備に関する。 The present invention relates to auxiliary cooling equipment for a nuclear power plant.

原子力プラントの補機冷却設備を開示するものとして、例えば特許文献１がある。特許文献１には、「補機冷却系２４は、冷却配管２８ａに設けられた補機冷却系ポンプ３５ａにより補機冷却水を循環させ、冷却配管２８ａと２８ｂから分岐した配管により連絡する高圧炉心注水系４や残留熱除去機能を有する低圧注水系５及び区分IIにおけるその他の負荷３６に対して、中間熱交換器３３を介して補機冷却水を循環させて冷却を行う。なお、高圧炉心注水系４はその他の熱負荷５，３６に対して冷却装置２７側に設けることとする。熱は中間熱交換器３３から海水冷却系ポンプ３５ｂにより海水冷却系３０を介して、通常は最終のヒートシンクとして海中へ放出される。」（段落［００４８］）、「補機冷却系２４の除熱量は相対的には小さいから、補機冷却系２４の冷却装置２７としては、比較的小型の装置を用いることが可能である。例えば、冷却水を落下させ空冷を行うクーリングタワーや、冷却水の流れる配管の伝熱面積を大きく取り配管の周囲から空冷を行うエアフィンクーラーのような装置を採用すれのが好適である。」（段落［００４９］）、「この構成によれば、隔離弁３４ａ及び３４ｂを開としかつ冷却装置２７側の隔離弁３４ｃ及び３４ｄを閉とすることで、高圧炉心注水系４を含む区分IIの熱負荷４，５，３６を補機冷却系２４及び海水冷却系３０により冷却を行う。すなわちこの場合の補機冷却水の循環路は図１１に示した従来の補機冷却系１９と同様である。しかし、逆に隔離弁３４ａ及び３４ｂを閉としかつ冷却装置２７側の隔離弁３４ｃ及び３４ｄを閉とすることで、高圧炉心注水系４の熱負荷を補機冷却系２４のその他の熱負荷の冷却水循環路から完全に隔離し、冷却装置２７により冷却することが可能となる。」（段落［００５１］）との記載がある。 Patent Document 1, for example, discloses auxiliary cooling equipment for a nuclear power plant. Patent Document 1 states that "the auxiliary cooling system 24 is a high-pressure core in which auxiliary cooling water is circulated by an auxiliary cooling system pump 35a provided in the cooling pipe 28a and is connected by a pipe branched from the cooling pipes 28a and 28b. Auxiliary cooling water is circulated through the intermediate heat exchanger 33 to cool the water injection system 4, the low pressure water injection system 5 having the residual heat removal function, and the other loads 36 in Category II. The water injection system 4 is provided on the cooling device 27 side with respect to the other heat loads 5 and 36. Heat is usually final from the intermediate heat exchanger 33 via the seawater cooling system pump 35b via the seawater cooling system 30. It is released into the sea as a heat sink (paragraph [0048]), "Since the amount of heat removed from the auxiliary cooling system 24 is relatively small, the cooling device 27 of the auxiliary cooling system 24 is a relatively small device. For example, a cooling tower that drops cooling water to perform air cooling, or an air fin cooler that takes a large heat transfer area of the piping through which the cooling water flows and performs air cooling from around the piping is adopted. (Paragraph [0049]), "According to this configuration, the isolation valves 34a and 34b are opened and the isolation valves 34c and 34d on the cooling device 27 side are closed to inject the high pressure core. The heat loads 4, 5 and 36 of Category II including the water system 4 are cooled by the auxiliary cooling system 24 and the seawater cooling system 30. That is, the circulation path of the auxiliary cooling water in this case is the conventional auxiliary cooling water shown in FIG. It is the same as the machine cooling system 19. However, by closing the isolation valves 34a and 34b and the isolation valves 34c and 34d on the cooling device 27 side, the heat load of the high-pressure core water injection system 4 is supplemented. It is possible to completely isolate the cooling system 24 from the cooling water circulation path of other heat loads and cool it by the cooling device 27 ”(paragraph [0051]).

特開平１１−３０６８５号公報Japanese Unexamined Patent Publication No. 11-30685

特許文献１に記載の原子力発電プラントの補機冷却系では、例えば海洋生物の大量発生によって海水冷却系ポンプ（送水ポンプ）の取水部に目詰まりが生じたり、海水冷却系ポンプ（送水ポンプ）が故障したり、海水冷却系ポンプと中間熱交換器とを接続する配管に詰まりや破断が生じた場合に、中間熱交換器（熱交換器）に海水を流通させることができなくなる。その結果、補機冷却系（冷却閉回路）を循環する冷却水の熱を海水に逃がすことができなくなり、補機冷却機能が失われる。 In the auxiliary cooling system of the nuclear power plant described in Patent Document 1, for example, the intake portion of the seawater cooling system pump (water supply pump) is clogged due to a large amount of marine organisms, or the seawater cooling system pump (water supply pump) is used. If a failure occurs or the pipe connecting the seawater cooling system pump and the intermediate heat exchanger is clogged or broken, seawater cannot be circulated to the intermediate heat exchanger (heat exchanger). As a result, the heat of the cooling water circulating in the auxiliary cooling system (cooling closed circuit) cannot be released to the seawater, and the auxiliary cooling function is lost.

本発明は、上記課題に鑑みてなされたものであり、その目的は、冷却水の熱を海水に逃がす熱交換器の機能が喪失した場合でも、すべての原子炉補機を冷却可能な原子力プラントの補機冷却設備を提供することにある。 The present invention has been made in view of the above problems, and an object of the present invention is a nuclear power plant capable of cooling all reactor accessories even if the function of a heat exchanger that dissipates the heat of cooling water to seawater is lost. To provide auxiliary cooling equipment.

上記目的を達成するために、本発明は、原子力プラントの補機冷却設備において、熱交換器と、前記熱交換器に海水を送水する送水ポンプと、前記原子力プラントの原子炉補機と前記熱交換器との間で冷却水を循環させる冷却閉回路と、前記冷却閉回路に設けられた第１循環ポンプと、前記第１循環ポンプに静水頭を与えるサージタンクと、前記冷却閉回路の前記第１循環ポンプの下流でかつ前記熱交換器の上流と前記冷却閉回路の前記熱交換器の下流でかつ前記原子炉補機の上流とを接続する第１分岐配管と、前記第１分岐配管に設けられた冷却塔と、前記第１循環ポンプから吐出された冷却水の送り先を前記熱交換器から前記冷却塔に切替可能な第１切替弁とを備えたものとする。 In order to achieve the above object, the present invention relates to a heat exchanger, a water supply pump for supplying seawater to the heat exchanger, a reactor auxiliary machine of the nuclear plant, and the heat in the auxiliary cooling equipment of the nuclear plant. A cooling closing circuit that circulates cooling water between the exchanger, a first circulation pump provided in the cooling closing circuit, a surge tank that gives a hydrostatic head to the first circulation pump, and the cooling closing circuit. A first branch pipe connecting the downstream of the first circulation pump and upstream of the heat exchanger and the downstream of the heat exchanger of the cooling closed circuit and upstream of the reactor auxiliary machine, and the first branch pipe. It is assumed that the cooling tower provided in the above and the first switching valve capable of switching the destination of the cooling water discharged from the first circulation pump from the heat exchanger to the cooling tower are provided.

以上のように構成した本発明によれば、第１循環ポンプから吐出された冷却水の送り先を第１切替弁によって熱交換器から冷却塔に切り替えることにより、冷却閉回路を循環する冷却水の熱を冷却塔で逃がすことができる。その結果、熱交換器の機能が喪失した場合でも、すべての原子炉補機を冷却することが可能となる。 According to the present invention configured as described above, the cooling water circulating in the cooling closed circuit is circulated by switching the destination of the cooling water discharged from the first circulation pump from the heat exchanger to the cooling tower by the first switching valve. Heat can be dissipated in the cooling tower. As a result, all reactor accessories can be cooled even if the heat exchanger loses its function.

本発明によれば、原子力プラントの補機冷却設備において、冷却水の熱を海水に逃がす熱交換器の機能が喪失した場合でも、すべての原子炉補機を冷却することが可能となる。 According to the present invention, in the auxiliary cooling equipment of a nuclear power plant, even if the function of the heat exchanger that dissipates the heat of the cooling water to the seawater is lost, it is possible to cool all the reactor auxiliary equipment.

本発明の第１の実施例に係る原子力プラントの補機冷却設備の構成図である。It is a block diagram of the auxiliary cooling equipment of the nuclear power plant which concerns on 1st Example of this invention. 本発明の第２または第３の実施例に係る原子力プラントの補機冷却設備の構成図である。It is a block diagram of the auxiliary cooling equipment of the nuclear power plant which concerns on 2nd or 3rd Embodiment of this invention. 本発明の第４または第５の実施例に係る原子力プラントの補機冷却設備の構成図である。It is a block diagram of the auxiliary cooling equipment of the nuclear power plant which concerns on 4th or 5th Examples of this invention.

以下、本発明の実施の形態について図面を参照しつつ説明する。なお、各図中、同等の部材には同一の符号を付し、重複した説明は適宜省略する。 Hereinafter, embodiments of the present invention will be described with reference to the drawings. In each figure, the same members are designated by the same reference numerals, and duplicate description will be omitted as appropriate.

図１は、本発明の第１の実施例に係る原子力プラントの補機冷却設備の構成図である。 FIG. 1 is a block diagram of an auxiliary cooling facility of a nuclear power plant according to the first embodiment of the present invention.

図１において、補機冷却設備２０は、循環ポンプ１（第１循環ポンプ）によって冷却閉回路２内の水（以下、冷却水）を循環させ、原子炉補機３ａ〜３ｃを通過した冷却水の熱を熱交換器４内を流通する海水に逃がすことにより、原子炉補機３ａ〜３ｃを冷却するものである。 In FIG. 1, the auxiliary cooling equipment 20 circulates water in the cooling closed circuit 2 (hereinafter referred to as cooling water) by the circulation pump 1 (first circulation pump), and the cooling water has passed through the reactor auxiliary machines 3a to 3c. The heat of the above is released to the seawater circulating in the heat exchanger 4 to cool the reactor auxiliary machines 3a to 3c.

冷却閉回路２の循環ポンプ１の上流には、循環ポンプ１に静水頭を与えるサージタンク５が設けられている。冷却閉回路２の循環ポンプ１の下流には、循環ポンプ１の吐出圧力を検出する圧力計６が設けられており、圧力計６で検出した循環ポンプ１の吐出圧力に基づいて循環ポンプ１の停止（故障）を検知することができる。 A surge tank 5 that provides a hydrostatic head to the circulation pump 1 is provided upstream of the circulation pump 1 of the cooling closing circuit 2. A pressure gauge 6 for detecting the discharge pressure of the circulation pump 1 is provided downstream of the circulation pump 1 of the cooling closing circuit 2, and the circulation pump 1 is based on the discharge pressure of the circulation pump 1 detected by the pressure gauge 6. Stop (failure) can be detected.

熱交換器４には送水ポンプ７によって海水ピット８に貯留された海水が送られ、熱交換器４から排出された海水は海に戻される。海水ピット８の水位が送水ポンプ７が吸水可能な水位を下回ると、送水ポンプ７から熱交換器４への送水が停止し、熱交換器４の機能が喪失する。そのため、海水ピット８には、海水の水位を監視するための水位計９が設けられている。なお、熱交換器４の機能が喪失したことを検知する手段はこれに限られず、送水ポンプ７の出口圧力の低下や、冷却閉回路２における熱交換器４の出口温度の上昇によって検知しても良い。 The seawater stored in the seawater pit 8 is sent to the heat exchanger 4 by the water pump 7, and the seawater discharged from the heat exchanger 4 is returned to the sea. When the water level in the seawater pit 8 is lower than the water level at which the water supply pump 7 can absorb water, the water supply from the water supply pump 7 to the heat exchanger 4 is stopped, and the function of the heat exchanger 4 is lost. Therefore, the seawater pit 8 is provided with a water level gauge 9 for monitoring the water level of seawater. The means for detecting the loss of the function of the heat exchanger 4 is not limited to this, and it is detected by a decrease in the outlet pressure of the water supply pump 7 or an increase in the outlet temperature of the heat exchanger 4 in the cooling closed circuit 2. Is also good.

冷却閉回路２の循環ポンプ１の下流でかつ熱交換器４の上流には分岐配管１０ａ（第１分岐配管）の一端が接続されており、分岐配管１０ａの他端は冷却塔１１の入口に接続されている。冷却閉回路２の熱交換器４の下流でかつ原子炉補機３ａ〜３ｃの上流には、分岐配管１０ｂ（第１分岐配管）の一端が接続されており、分岐配管１０ｂの他端は冷却塔１１の出口に接続されている。 One end of the branch pipe 10a (first branch pipe) is connected downstream of the circulation pump 1 of the cooling closing circuit 2 and upstream of the heat exchanger 4, and the other end of the branch pipe 10a is connected to the inlet of the cooling tower 11. It is connected. One end of the branch pipe 10b (first branch pipe) is connected to the downstream of the heat exchanger 4 of the cooling closed circuit 2 and upstream of the reactor accessories 3a to 3c, and the other end of the branch pipe 10b is cooled. It is connected to the exit of tower 11.

分岐配管１０ａには、分岐配管１０ａの連通と遮断とを切替可能な切替弁１２ａ（第１切替弁）が設けられている。冷却閉回路２の熱交換器４の上流でかつ分岐配管１０ａ下流には、冷却閉回路２の循環ポンプ１と熱交換器４との間の連通と遮断とを切替可能な切替弁１２ｂ（第１切替弁）が設けられている。 The branch pipe 10a is provided with a switching valve 12a (first switching valve) capable of switching between communication and shutoff of the branch pipe 10a. A switching valve 12b (No. 1) capable of switching between communication and interruption between the circulation pump 1 of the cooling closed circuit 2 and the heat exchanger 4 upstream of the heat exchanger 4 of the cooling closed circuit 2 and downstream of the branch pipe 10a. 1 switching valve) is provided.

補機冷却設備２０は、さらに、切替弁１２ａ，１２ｂの切替および冷却塔１１の起動／停止を制御する制御回路１３（第１制御回路）を備えている。制御回路１３は、水位計９で計測した海水ピット８の水位に基づいて熱交換器４が機能しているか否かを判定する。熱交換器４が機能していると判定した場合は、切替弁１２ａを閉じ、切替弁１２ｂを開き、冷却塔１１を起動しない。一方、熱交換器４が機能していないと判定した場合は、切替弁１２ａを開き、切替弁１２ｂを閉じ、冷却塔１１を起動する。なお、制御回路１３は必ずしも設ける必要は無く、水位計９で検出した海水ピット８の水位に応じて、オペレータが手動で切替弁１２ａを開き、切替弁１２ｂを閉じ、冷却塔１１を起動しても良い。 The auxiliary cooling equipment 20 further includes a control circuit 13 (first control circuit) that controls switching of the switching valves 12a and 12b and start / stop of the cooling tower 11. The control circuit 13 determines whether or not the heat exchanger 4 is functioning based on the water level of the seawater pit 8 measured by the water level gauge 9. When it is determined that the heat exchanger 4 is functioning, the switching valve 12a is closed, the switching valve 12b is opened, and the cooling tower 11 is not started. On the other hand, when it is determined that the heat exchanger 4 is not functioning, the switching valve 12a is opened, the switching valve 12b is closed, and the cooling tower 11 is started. The control circuit 13 does not necessarily have to be provided, and the operator manually opens the switching valve 12a, closes the switching valve 12b, and starts the cooling tower 11 according to the water level of the seawater pit 8 detected by the water level gauge 9. Is also good.

この動作によって、熱交換器４の機能が喪失した場合は、原子炉補機３ａ〜３ｂを通過した冷却水が循環ポンプ１によって冷却塔１１に送られ、熱交換器４を通過することなく、冷却閉回路２内を循環する。 When the function of the heat exchanger 4 is lost due to this operation, the cooling water that has passed through the reactor accessories 3a to 3b is sent to the cooling tower 11 by the circulation pump 1 without passing through the heat exchanger 4. It circulates in the cooling closed circuit 2.

本実施例に係る原子力プラントの補機冷却設備２０は、熱交換器４と、熱交換器４に海水を送水する送水ポンプ２と、原子力プラントの原子炉補機３ａ〜３ｃと熱交換器４との間で冷却水を循環させる冷却閉回路２と、冷却閉回路２に設けられた第１循環ポンプ１と、第１循環ポンプ１に静水頭を与えるサージタンク５と、冷却閉回路２の第１循環ポンプ１の下流でかつ熱交換器４の上流と冷却閉回路２の熱交換器４の下流でかつ原子炉補機３ａ〜３ｃの上流とを接続する第１分岐配管１０ａ，１０ｂと、第１分岐配管１０ａ，１０ｂに設けられた冷却塔１１と、第１循環ポンプ１から吐出された冷却水の送り先を熱交換器４から冷却塔１１に切替可能な第１切替弁１２ａ，１２ｂとを備える。 The auxiliary cooling equipment 20 of the nuclear plant according to the present embodiment includes a heat exchanger 4, a water supply pump 2 for sending seawater to the heat exchanger 4, and nuclear reactor auxiliary machines 3a to 3c and a heat exchanger 4 of the nuclear plant. A cooling closing circuit 2 that circulates cooling water between the two, a first circulation pump 1 provided in the cooling closing circuit 2, a surge tank 5 that gives a hydrostatic head to the first circulation pump 1, and a cooling closing circuit 2. With the first branch pipes 10a and 10b downstream of the first circulation pump 1 and upstream of the heat exchanger 4 and downstream of the heat exchanger 4 of the cooling closed circuit 2 and upstream of the reactor auxiliary machines 3a to 3c. , The cooling tower 11 provided in the first branch pipes 10a and 10b, and the first switching valves 12a and 12b capable of switching the destination of the cooling water discharged from the first circulation pump 1 from the heat exchanger 4 to the cooling tower 11. And.

以上のように構成した本実施例によれば、熱交換器４の機能を喪失した場合でも、熱交換器４の機能を冷却塔１１で代替することにより、すべての原子炉補機３ａ〜３ｃを冷却することが可能となる。 According to the present embodiment configured as described above, even if the function of the heat exchanger 4 is lost, by substituting the function of the heat exchanger 4 with the cooling tower 11, all the reactor accessories 3a to 3c Can be cooled.

また、本実施例に係る原子力プラントの補機冷却設備２０は、熱交換器４の機能停止を検知して、第１循環ポンプ１から吐出された冷却水の送り先が熱交換器４から冷却塔１１に切り替わるように第１切替弁１２ａ，１２ｂを切り替え、かつ冷却塔１１を起動する第１制御回路１３を更に備える。これにより、熱交換器４の機能が喪失した後に、速やかに熱交換器４の機能を冷却塔１１で代替することが可能となる。 Further, the auxiliary cooling equipment 20 of the nuclear plant according to the present embodiment detects that the heat exchanger 4 has stopped functioning, and the destination of the cooling water discharged from the first circulation pump 1 is the cooling tower from the heat exchanger 4. A first control circuit 13 that switches the first switching valves 12a and 12b so as to switch to 11 and activates the cooling tower 11 is further provided. As a result, after the function of the heat exchanger 4 is lost, the function of the heat exchanger 4 can be quickly replaced by the cooling tower 11.

図２は、本発明の第２の実施例に係る原子力プラントの補機冷却設備の構成図である。以下、第１の実施例（図１に示す）との相違点を中心に説明する。 FIG. 2 is a block diagram of an auxiliary cooling facility for a nuclear power plant according to a second embodiment of the present invention. Hereinafter, the differences from the first embodiment (shown in FIG. 1) will be mainly described.

図２において、補機冷却設備２０Ａは、追加循環ポンプ１４（第２循環ポンプ）と、切替弁１５（第２切替弁）と、制御回路１６（第２制御回路）とを更に備える。 In FIG. 2, the auxiliary cooling equipment 20A further includes an additional circulation pump 14 (second circulation pump), a switching valve 15 (second switching valve), and a control circuit 16 (second control circuit).

追加循環ポンプ１４の吸入ポートと冷却閉回路２のサージタンク５の下流でかつ循環ポンプ１の上流とは、分岐配管１７ａ（第２分岐配管）で接続されている。追加循環ポンプ１４の吐出ポートと分岐配管１０ａの切替弁１２ａの上流（または、冷却閉回路２の循環ポンプ１の下流でかつ分岐配管１０ａの上流）とは、分岐配管１７ｂ（第２分岐配管）で接続されている。分岐配管１７ａには、分岐配管１７ａの連通と遮断とを切替可能な切替弁１５が設けられている。 The suction port of the additional circulation pump 14 and the downstream of the surge tank 5 of the cooling closing circuit 2 and the upstream of the circulation pump 1 are connected by a branch pipe 17a (second branch pipe). The discharge port of the additional circulation pump 14 and the upstream of the switching valve 12a of the branch pipe 10a (or the downstream of the circulation pump 1 of the cooling closed circuit 2 and the upstream of the branch pipe 10a) are the branch pipe 17b (second branch pipe). It is connected with. The branch pipe 17a is provided with a switching valve 15 capable of switching between communication and cutoff of the branch pipe 17a.

制御回路１６は、圧力計６で検出した循環ポンプ１の吐出圧力に基づいて循環ポンプ１の停止（故障）を検知する。制御回路１６は、循環ポンプ１の故障を検知した場合に、切替弁１５を開き、かつ追加循環ポンプ１４を起動する。なお、制御回路１６は必ずしも設ける必要は無く、圧力計６で検出した循環ポンプ１の吐出圧力に応じて、オペレータが手動で切替弁１５を開き、かつ追加循環ポンプ１４を起動しても良い。 The control circuit 16 detects the stoppage (failure) of the circulation pump 1 based on the discharge pressure of the circulation pump 1 detected by the pressure gauge 6. When the control circuit 16 detects a failure of the circulation pump 1, the control circuit 16 opens the switching valve 15 and starts the additional circulation pump 14. The control circuit 16 does not necessarily have to be provided, and the operator may manually open the switching valve 15 and start the additional circulation pump 14 according to the discharge pressure of the circulation pump 1 detected by the pressure gauge 6.

この構成において、制御回路１６は、熱交換器４の機能を喪失した状態（切替弁１２ｂが閉じ、かつ切替弁１２ａが開いた状態）でさらに循環ポンプ１が故障した場合に、切替弁１５を開き、かつ追加循環ポンプ１４を起動する。 In this configuration, the control circuit 16 uses the switching valve 15 when the circulation pump 1 fails further in a state where the function of the heat exchanger 4 is lost (a state in which the switching valve 12b is closed and the switching valve 12a is open). Open and activate the additional circulation pump 14.

この動作によって、熱交換器４の機能を喪失した状態で循環ポンプ１が故障した場合は、原子炉補機３ａ〜３ｂを通過した冷却水が追加循環ポンプ１４によって冷却塔１１に送られ、循環ポンプ１および熱交換器４を通過することなく、冷却閉回路２内を循環する。 If the circulation pump 1 fails in a state where the function of the heat exchanger 4 is lost due to this operation, the cooling water that has passed through the reactor accessories 3a to 3b is sent to the cooling tower 11 by the additional circulation pump 14 to circulate. It circulates in the cooling closed circuit 2 without passing through the pump 1 and the heat exchanger 4.

本実施例に係る原子力プラントの補機冷却設備２０Ａは、冷却閉回路２の原子炉補機３ａ〜３ｃの下流でかつ第１循環ポンプ１の上流と第１分岐配管１０ａの第１切替弁１２ａの上流または冷却閉回路２の第１循環ポンプ１の下流でかつ第１分岐配管１０ａの上流とを接続する第２分岐配管１７ａ，１７ｂと、第２分岐配管１７ａ，１７ｂに設けられた第２循環ポンプ１４と、第２分岐配管１７ａ，１７ｂの第２循環ポンプ１４の上流に設けられ、第２分岐配管１７ａ，１７ｂの連通と遮断とを切替可能な第２切替弁１５とを更に備える。 The auxiliary cooling equipment 20A of the nuclear plant according to the present embodiment is downstream of the reactor auxiliary machines 3a to 3c of the cooling closed circuit 2, upstream of the first circulation pump 1, and the first switching valve 12a of the first branch pipe 10a. The second branch pipes 17a and 17b connected to the upstream of the above or the downstream of the first circulation pump 1 of the cooling closed circuit 2 and the upstream of the first branch pipe 10a, and the second branch pipes 17a and 17b provided in the second branch pipes 17a and 17b. A circulation pump 14 and a second switching valve 15 provided upstream of the second circulation pump 14 of the second branch pipes 17a and 17b and capable of switching between communication and interruption of the second branch pipes 17a and 17b are further provided.

以上のように構成した本実施例によれば、熱交換器４の機能を冷却塔１１で代替している状態でさらに第１循環ポンプ１が故障した場合でも、第１循環ポンプ１の機能を第２循環ポンプ１４で代替することにより、すべての原子炉補機３ａ〜３ｃを冷却することが可能となる。 According to the present embodiment configured as described above, even if the first circulation pump 1 fails in a state where the function of the heat exchanger 4 is replaced by the cooling tower 11, the function of the first circulation pump 1 can be maintained. By substituting with the second circulation pump 14, it is possible to cool all the reactor accessories 3a to 3c.

また、本実施例に係る原子力プラントの補機冷却設備２０Ａは、第１循環ポンプ１の故障を検知して、第２分岐配管１７ａ，１７ｂが連通するように第２切替弁１５を切り替え、かつ第２循環ポンプ１４を起動する第２制御回路１６を備える。これにより、第１循環ポンプ１が停止した後に、速やかに第１循環ポンプ１の機能を第２循環ポンプ１４で代替することが可能となる。 Further, the auxiliary cooling equipment 20A of the nuclear power plant according to the present embodiment detects the failure of the first circulation pump 1 and switches the second switching valve 15 so that the second branch pipes 17a and 17b communicate with each other. A second control circuit 16 for activating the second circulation pump 14 is provided. As a result, after the first circulation pump 1 is stopped, the function of the first circulation pump 1 can be quickly replaced by the second circulation pump 14.

本発明の第３の実施例に係る原子力プラントの補機冷却設備について第１の実施例との相違点を中心に説明する。 The auxiliary cooling equipment of the nuclear power plant according to the third embodiment of the present invention will be described focusing on the differences from the first embodiment.

本実施例に係る原子力プラントの補機冷却設備の構成は、第２の実施例（図２に示す）と同様である。 The configuration of the auxiliary cooling equipment of the nuclear power plant according to this embodiment is the same as that of the second embodiment (shown in FIG. 2).

図２において、本実施例に係る補機冷却設備２０Ａでは、熱交換器４が機能している状態（切替弁１２ａが閉じ、かつ切替弁１２ｂが開いた状態）で循環ポンプ１が故障した場合に、分岐配管１７ａの切替弁１５を開き、追加循環ポンプ１４を起動する。 In FIG. 2, in the auxiliary cooling equipment 20A according to the present embodiment, when the circulation pump 1 fails in a state where the heat exchanger 4 is functioning (a state in which the switching valve 12a is closed and the switching valve 12b is open). The switching valve 15 of the branch pipe 17a is opened, and the additional circulation pump 14 is started.

この動作によって、熱交換器４が機能している状態で循環ポンプ１が故障した場合は、原子炉補機３ａ〜３ｂを通過した冷却水が追加循環ポンプ１４によって熱交換器４に送られ、循環ポンプ１および冷却塔１１を通過することなく、冷却閉回路２内を循環する。 If the circulation pump 1 fails while the heat exchanger 4 is functioning due to this operation, the cooling water that has passed through the reactor accessories 3a to 3b is sent to the heat exchanger 4 by the additional circulation pump 14. It circulates in the cooling closed circuit 2 without passing through the circulation pump 1 and the cooling tower 11.

以上のように構成した本実施例によれば、熱交換器４が機能している状態で第１循環ポンプ１が故障した場合でも、第１循環ポンプ１の機能を第２循環ポンプ１４で代替することにより、すべての原子炉補機３ａ〜３ｃを冷却することが可能となる。 According to the present embodiment configured as described above, even if the first circulation pump 1 fails while the heat exchanger 4 is functioning, the function of the first circulation pump 1 is replaced by the second circulation pump 14. By doing so, it becomes possible to cool all the reactor accessories 3a to 3c.

図３は、本発明の第４の実施例に係る原子力プラントの補機冷却設備の構成図である。以下、第３の実施例（図２に示す）との相違点を中心に説明する。 FIG. 3 is a block diagram of an auxiliary cooling facility for a nuclear power plant according to a fourth embodiment of the present invention. Hereinafter, the differences from the third embodiment (shown in FIG. 2) will be mainly described.

図３において、補機冷却設備２０Ｂは、追加循環ポンプ１４（第２循環ポンプ）および制御回路１６（第２制御回路）を備えていない。また、分岐配管１７ａの下流端には、可搬型ポンプの吸入ポートを接続するための接続口１８ａが設けられており、分岐配管１７ｂの上流端には、可搬型ポンプの吐出ポートを接続するための接続口１８ａが設けられている。 In FIG. 3, the auxiliary cooling equipment 20B does not include the additional circulation pump 14 (second circulation pump) and the control circuit 16 (second control circuit). Further, a connection port 18a for connecting the suction port of the portable pump is provided at the downstream end of the branch pipe 17a, and a discharge port of the portable pump is connected to the upstream end of the branch pipe 17b. Connection port 18a is provided.

この構成において、熱交換器４の機能を喪失した状態（切替弁１２ｂが閉じ、かつ切替弁１２ａが開いた状態）でさらに循環ポンプ１が故障した場合に、分岐配管１７ａの切替弁１５を閉じたまま、分岐配管１７ａの接続口１８ａに可搬型ポンプからなる追加循環ポンプ１４の吸入ポートを接続し、分岐配管１７ｂの接続口１８ｂに追加循環ポンプ１４の吐出ポートを接続する。追加循環ポンプ１４の設置が完了したら、分岐配管１７ａの切替弁１５を開き、追加循環ポンプ１４を起動する。 In this configuration, when the circulation pump 1 further fails in a state where the function of the heat exchanger 4 is lost (a state in which the switching valve 12b is closed and the switching valve 12a is open), the switching valve 15 of the branch pipe 17a is closed. While still, the suction port of the additional circulation pump 14 made of a portable pump is connected to the connection port 18a of the branch pipe 17a, and the discharge port of the additional circulation pump 14 is connected to the connection port 18b of the branch pipe 17b. When the installation of the additional circulation pump 14 is completed, the switching valve 15 of the branch pipe 17a is opened to start the additional circulation pump 14.

この動作によって、熱交換器４の機能を喪失した状態でさらに循環ポンプ１が故障した場合は、原子炉補機３ａ〜３ｂを通過した冷却水が追加循環ポンプ１４によって冷却塔１１に送られ、循環ポンプ１および熱交換器４を通過することなく、冷却閉回路２内を循環する。 If the circulation pump 1 further fails in a state where the function of the heat exchanger 4 is lost due to this operation, the cooling water that has passed through the reactor accessories 3a to 3b is sent to the cooling tower 11 by the additional circulation pump 14. It circulates in the cooling closed circuit 2 without passing through the circulation pump 1 and the heat exchanger 4.

本実施例に係る原子力プラントの補機冷却設備２０Ｂは、冷却閉回路２の原子炉補機３ａ〜３ｃの下流でかつ第１循環ポンプ１の上流と第１分岐配管１０ａの第１切替弁１２ａの上流または冷却閉回路２の第１循環ポンプ１の下流でかつ第１分岐配管１０ａの上流とを接続する第２分岐配管１７ａ，１７ｂと、第２分岐配管１７ａ，１７ｂに設けられ、第２分岐配管１７ａ，１７ｂに可搬型ポンプからなる第２循環ポンプ１４を接続するための接続口１８ａ，１８ｂと、第２分岐配管１７ａ，１７ｂの接続口１８ａ，１８ｂの上流に設けられ、第２分岐配管１７ａ，１７ｂの連通と遮断とを切替可能な第２切替弁１５とを更に備える。 The auxiliary cooling equipment 20B of the nuclear plant according to the present embodiment is downstream of the reactor auxiliary machines 3a to 3c of the cooling closed circuit 2, upstream of the first circulation pump 1, and the first switching valve 12a of the first branch pipe 10a. The second branch pipes 17a and 17b and the second branch pipes 17a and 17b are provided to be upstream of the above or downstream of the first circulation pump 1 of the cooling closed circuit 2 and connected to the upstream of the first branch pipe 10a. The connection ports 18a and 18b for connecting the second circulation pump 14 made of a portable pump to the branch pipes 17a and 17b and the second branch are provided upstream of the connection ports 18a and 18b of the second branch pipes 17a and 17b. A second switching valve 15 capable of switching between communication and interruption of the pipes 17a and 17b is further provided.

以上のように構成した本実施例によれば、熱交換器４の機能を冷却塔１１で代替している状態でさらに第１循環ポンプ１が故障した場合でも、可搬型ポンプからなる第２循環ポンプ１４を第２分岐配管１７ａ，１７ｂに設置し、第１循環ポンプ１の機能を第２循環ポンプ１４で代替することにより、すべての原子炉補機３ａ〜３ｃを冷却することが可能となる。 According to the present embodiment configured as described above, even if the first circulation pump 1 fails while the function of the heat exchanger 4 is replaced by the cooling tower 11, the second circulation composed of the portable pump By installing the pump 14 in the second branch pipes 17a and 17b and substituting the function of the first circulation pump 1 with the second circulation pump 14, it is possible to cool all the reactor auxiliary machines 3a to 3c. ..

本発明の第５の実施例に係る原子力プラントの補機冷却設備について、第４の実施例との相違点を中心に説明する。 The auxiliary cooling equipment of the nuclear power plant according to the fifth embodiment of the present invention will be described focusing on the differences from the fourth embodiment.

本実施例に係る原子力プラントの補機冷却設備の構成は、第４の実施例（図４に示す）と同様である。 The configuration of the auxiliary cooling equipment of the nuclear power plant according to this embodiment is the same as that of the fourth embodiment (shown in FIG. 4).

図４において、本実施例に係る補機冷却設備２０Ｂでは、熱交換器４が機能している状態（切替弁１２ａが閉じ、かつ切替弁１２ｂが開いた状態）で第１循環ポンプ１が故障した場合に、分岐配管１７ａの切替弁１５を閉じたまま、分岐配管１７ａの接続口１８ａに可搬型ポンプからなる追加循環ポンプ１４の吸入ポートを接続し、分岐配管１７ｂの接続口１８ｂに追加循環ポンプ１４の吐出ポートを接続する。追加循環ポンプ１４の設置が完了したら、切替弁１５を開き、追加循環ポンプ１４を起動する。 In FIG. 4, in the auxiliary cooling equipment 20B according to the present embodiment, the first circulation pump 1 fails in a state where the heat exchanger 4 is functioning (a state in which the switching valve 12a is closed and the switching valve 12b is open). In this case, with the switching valve 15 of the branch pipe 17a closed, the suction port of the additional circulation pump 14 made of a portable pump is connected to the connection port 18a of the branch pipe 17a, and the additional circulation is made to the connection port 18b of the branch pipe 17b. Connect the discharge port of the pump 14. When the installation of the additional circulation pump 14 is completed, the switching valve 15 is opened and the additional circulation pump 14 is started.

この動作によって、熱交換器４が機能している状態で循環ポンプ１が故障した場合は、原子炉補機３ａ〜３ｂを通過した冷却水が追加循環ポンプ１４によって熱交換器４に送られ、循環ポンプ１および冷却塔１１を通過することなく、冷却閉回路２内を循環する。 If the circulation pump 1 fails while the heat exchanger 4 is functioning due to this operation, the cooling water that has passed through the reactor accessories 3a to 3b is sent to the heat exchanger 4 by the additional circulation pump 14. It circulates in the cooling closed circuit 2 without passing through the circulation pump 1 and the cooling tower 11.

以上のように構成した本実施例によれば、熱交換器４が機能している状態で循環ポンプ１が故障した場合でも、可搬型ポンプからなる第２循環ポンプ１４を第２分岐配管１７ａ，１７ｂに設置し、第１循環ポンプ１の機能を第２循環ポンプ１４で代替することにより、すべての原子炉補機３ａ〜３ｃを冷却することが可能となる。 According to the present embodiment configured as described above, even if the circulation pump 1 fails while the heat exchanger 4 is functioning, the second circulation pump 14 made of a portable pump can be connected to the second branch pipe 17a. By installing it in 17b and substituting the function of the first circulation pump 1 with the second circulation pump 14, it becomes possible to cool all the reactor auxiliary machines 3a to 3c.

以上、本発明の実施例について詳述したが、本発明は、上記した実施例に限定されるものではなく、様々な変形例が含まれる。例えば、上記した実施例は、本発明を分かり易く説明するために詳細に説明したものであり、必ずしも説明した全ての構成を備えるものに限定されるものではない。また、ある実施例の構成に他の実施例の構成の一部を加えることも可能であり、ある実施例の構成の一部を削除し、あるいは、他の実施例の一部と置き換えることも可能である。 Although the examples of the present invention have been described in detail above, the present invention is not limited to the above-mentioned examples, and includes various modifications. For example, the above-described embodiment has been described in detail in order to explain the present invention in an easy-to-understand manner, and is not necessarily limited to those having all the described configurations. It is also possible to add a part of the configuration of another embodiment to the configuration of one embodiment, delete a part of the configuration of one embodiment, or replace it with a part of another embodiment. It is possible.

１…循環ポンプ（第１循環ポンプ）、２…冷却閉回路、３ａ，３ｂ，３ｃ…原子炉補機、４…熱交換器、５…サージタンク、６…圧力計、７…送水ポンプ、８…海水ピット、９…水位計、１０ａ，１０ｂ…分岐配管（第１分岐配管）、１１…冷却塔、１２ａ，１２ｂ…切替弁（第１切替弁）、１３…制御回路（第１制御回路）、１４…追加循環ポンプ（第２循環ポンプ）、１５…切替弁（第２切替弁）、１６…制御回路（第２制御回路）、１７ａ，１７ｂ…分岐配管（第２分岐配管）、１８ａ，１８ｂ…接続口、２０，２０Ａ，２０Ｂ…補機冷却設備。 1 ... Circulation pump (1st circulation pump), 2 ... Cooling closed circuit, 3a, 3b, 3c ... Reactor auxiliary equipment, 4 ... Heat exchanger, 5 ... Surge tank, 6 ... Pressure gauge, 7 ... Water pump, 8 ... Seawater pit, 9 ... Water level gauge, 10a, 10b ... Branch pipe (first branch pipe), 11 ... Cooling tower, 12a, 12b ... Switching valve (first switching valve), 13 ... Control circuit (first control circuit) , 14 ... Additional circulation pump (second circulation pump), 15 ... Switching valve (second switching valve), 16 ... Control circuit (second control circuit), 17a, 17b ... Branch piping (second branch piping), 18a, 18b ... Connection port, 20, 20A, 20B ... Auxiliary cooling equipment.

Claims (5)

原子力プラントの補機冷却設備において、
熱交換器と、
前記熱交換器に海水を送水する送水ポンプと、
前記原子力プラントの原子炉補機と前記熱交換器との間で冷却水を循環させる冷却閉回路と、
前記冷却閉回路に設けられた第１循環ポンプと、
前記第１循環ポンプに静水頭を与えるサージタンクと、
前記冷却閉回路の前記第１循環ポンプの下流でかつ前記熱交換器の上流と前記冷却閉回路の前記熱交換器の下流でかつ前記原子炉補機の上流とを接続する第１分岐配管と、
前記第１分岐配管に設けられた冷却塔と、
前記第１循環ポンプから吐出された冷却水の送り先を前記熱交換器から前記冷却塔に切替可能な第１切替弁とを備えた
ことを特徴とする原子力プラントの補機冷却設備。 In auxiliary cooling equipment of a nuclear plant
With a heat exchanger
A water pump that sends seawater to the heat exchanger,
A cooling closed circuit that circulates cooling water between the reactor auxiliary equipment of the nuclear power plant and the heat exchanger, and
The first circulation pump provided in the cooling closed circuit and
A surge tank that provides a hydrostatic head to the first circulation pump,
With the first branch pipe connecting the downstream of the first circulation pump of the cooling closed circuit and the upstream of the heat exchanger and the downstream of the heat exchanger of the cooling closed circuit and the upstream of the reactor auxiliary machine. ,
The cooling tower provided in the first branch pipe and
Auxiliary cooling equipment for a nuclear plant, characterized in that it is provided with a first switching valve capable of switching the destination of the cooling water discharged from the first circulation pump from the heat exchanger to the cooling tower. 請求項１に記載の原子力プラントの補機冷却設備において、
前記熱交換器の機能停止を検知して、前記第１循環ポンプから吐出された冷却水の送り先が前記熱交換器から前記冷却塔に切り替わるように前記第１切替弁を切り替え、かつ前記冷却塔を起動する第１制御回路を更に備えた
ことを特徴とする原子力プラントの補機冷却設備。 In the auxiliary cooling equipment of the nuclear power plant according to claim 1.
When the function stop of the heat exchanger is detected, the first switching valve is switched so that the destination of the cooling water discharged from the first circulation pump is switched from the heat exchanger to the cooling tower, and the cooling tower is switched. Auxiliary cooling equipment for a nuclear plant, which is characterized by further having a first control circuit for starting up. 請求項１に記載の原子力プラントの補機冷却設備において、
前記冷却閉回路の前記原子炉補機の下流でかつ前記第１循環ポンプの上流と前記第１分岐配管の前記第１切替弁の上流または前記冷却閉回路の前記第１循環ポンプの下流でかつ前記第１分岐配管の上流とを接続する第２分岐配管と、
前記第２分岐配管に設けられた第２循環ポンプと、
前記第２分岐配管の前記第２循環ポンプの上流に設けられ、前記第２分岐配管の連通と遮断とを切替可能な第２切替弁とを更に備えた
ことを特徴とする原子力プラントの補機冷却設備。 In the auxiliary cooling equipment of the nuclear power plant according to claim 1.
Downstream of the reactor auxiliary machine of the cooling closed circuit and upstream of the first circulation pump and upstream of the first switching valve of the first branch pipe or downstream of the first circulation pump of the cooling closed circuit. The second branch pipe connecting to the upstream of the first branch pipe and
The second circulation pump provided in the second branch pipe and
Auxiliary equipment for a nuclear power plant, which is provided upstream of the second circulation pump of the second branch pipe and further provided with a second switching valve capable of switching between communication and shutoff of the second branch pipe. Cooling equipment. 請求項３に記載の原子力プラントの補機冷却設備において、
前記第１循環ポンプの故障を検知して、前記第２分岐配管が連通するように前記第２切替弁を切り替え、かつ前記第２循環ポンプを起動する第２制御回路を備えた
ことを特徴とする原子力プラントの補機冷却設備。 In the auxiliary cooling equipment of the nuclear power plant according to claim 3.
It is characterized by having a second control circuit that detects a failure of the first circulation pump, switches the second switching valve so that the second branch pipe communicates, and starts the second circulation pump. Auxiliary cooling equipment for nuclear power plants. 請求項１に記載の原子力プラントの補機冷却設備において、
前記冷却閉回路の前記原子炉補機の下流でかつ前記第１循環ポンプの上流と前記第１分岐配管の前記第１切替弁の上流または前記冷却閉回路の前記第１循環ポンプの下流でかつ前記第１分岐配管の上流とを接続する第２分岐配管と、
前記第２分岐配管に設けられ、前記第２分岐配管に可搬型ポンプからなる第２循環ポンプを接続するための接続口と、
前記第２分岐配管の前記接続口の上流に設けられ、前記第２分岐配管の連通と遮断とを切替可能な第２切替弁とを更に備えた
ことを特徴とする原子力プラントの補機冷却設備。 In the auxiliary cooling equipment of the nuclear power plant according to claim 1.
Downstream of the reactor auxiliary machine of the cooling closed circuit and upstream of the first circulation pump and upstream of the first switching valve of the first branch pipe or downstream of the first circulation pump of the cooling closed circuit. The second branch pipe connecting to the upstream of the first branch pipe and
A connection port provided in the second branch pipe for connecting a second circulation pump made of a portable pump to the second branch pipe, and
Auxiliary cooling equipment for a nuclear power plant, which is provided upstream of the connection port of the second branch pipe and further includes a second switching valve capable of switching between communication and disconnection of the second branch pipe. ..
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