JP7389764B2 - Reactor containment cooling system - Google Patents

Reactor containment cooling system Download PDF

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JP7389764B2
JP7389764B2 JP2021004834A JP2021004834A JP7389764B2 JP 7389764 B2 JP7389764 B2 JP 7389764B2 JP 2021004834 A JP2021004834 A JP 2021004834A JP 2021004834 A JP2021004834 A JP 2021004834A JP 7389764 B2 JP7389764 B2 JP 7389764B2
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water
cooling water
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匠 宇都宮
ギヨームローラント グランジョン
花梨 小野
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Hitachi GE Nuclear Energy Ltd
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Description

本発明は、原子炉格納容器の冷却システムに関する。 The present invention relates to a cooling system for a nuclear reactor containment vessel.

従来の改良型沸騰水型原子炉（ＡＢＷＲ）においては、原子炉圧力容器内で発生する蒸気を原子炉格納容器内のサプレッションプールに導入して凝縮させ、原子炉圧力容器および原子炉格納容器の過圧を防止している。また、サプレッションプールに導入される蒸気で駆動しサプレッションプールの冷却水を原子炉圧力容器内に注水し、炉心の冠水および冷却を維持している。 In a conventional advanced boiling water reactor (ABWR), steam generated in the reactor pressure vessel is introduced into a suppression pool in the reactor containment vessel and condensed, and the steam generated in the reactor pressure vessel and reactor containment vessel is condensed. Prevents overpressure. It is also driven by steam introduced into the suppression pool and injects cooling water from the suppression pool into the reactor pressure vessel to maintain flooding and cooling of the reactor core.

また、蒸気により熱せられるサプレッションプールの冷却水は、残留熱除去系のポンプにより原子炉格納容器外の熱交換器に送られ冷却される。これにより、原子炉格納容器は、温度および圧力の上昇を防止されている。 Cooling water in the suppression pool heated by steam is sent to a heat exchanger outside the reactor containment vessel by a pump in the residual heat removal system and is cooled. This prevents the reactor containment vessel from increasing in temperature and pressure.

しかし、例えば、全交流電源喪失（Station Black Out:ＳＢＯ）により残留熱除去系のポンプが停止した場合、サプレッションプールの冷却水を原子炉格納容器外の熱交換器に送ることができず、原子炉格納容器の温度および圧力が長期的に緩やかに上昇する。これにより、原子炉格納容器の放射性物質の閉じ込め機能に影響を及ぼす可能性がある。 However, for example, if the pumps in the residual heat removal system stop due to a station black out (SBO), the cooling water from the suppression pool cannot be sent to the heat exchanger outside the reactor containment vessel, and the Temperature and pressure in the reactor containment vessel increase slowly over time. This may affect the ability of the reactor containment vessel to contain radioactive materials.

全交流電源喪失時に原子炉格納容器を継続して冷却できる冷却システムが、特許文献１に開示されている。特許文献１の原子炉格納容器の冷却システムは、冷却水が原子炉格納容器を冷却する外周プールへ原子炉格納容器の外に設置した補給水タンクから重力により給水され、給水調整弁により外周プールの水位に応じて補給水タンクから外周プールへ供給される冷却水の水量が調整される。 A cooling system that can continuously cool a reactor containment vessel when all AC power is lost is disclosed in Patent Document 1. In the reactor containment cooling system of Patent Document 1, cooling water is supplied by gravity from a make-up water tank installed outside the reactor containment vessel to an outer circumferential pool that cools the reactor containment vessel, and a water supply regulating valve is used to supply cooling water to an outer circumferential pool that cools the reactor containment vessel. The amount of cooling water supplied from the make-up water tank to the outer pool is adjusted according to the water level.

特開２０１５－２２７８３０号公報Japanese Patent Application Publication No. 2015-227830

特許文献１の原子力格納容器の冷却システムは、大量の冷却水を貯蔵する外周プールと補給水タンクが必要で、これらの建設のためにかかる工期やコストの点で改善の余地がある。 The cooling system for a nuclear power containment vessel disclosed in Patent Document 1 requires a peripheral pool and a make-up water tank for storing a large amount of cooling water, and there is room for improvement in terms of the construction period and cost required for constructing these.

本発明の目的は、全交流電源喪失時等により既存の冷却システムが停止した場合でも原子炉格納容器を継続して冷却でき、工期とコストを抑制できる冷却システムを提供する。 An object of the present invention is to provide a cooling system that can continue to cool a nuclear reactor containment vessel even when the existing cooling system is stopped due to a complete loss of AC power, thereby reducing construction time and costs.

上記目的を達成するために、本発明は、炉心を内蔵する原子炉圧力容器を格納する鋼製の原子炉格納容器を冷却する冷却システムであって、前記原子炉鋼製容器の外壁に接触する複数の水冷伝熱管と、前記複数の水冷伝熱管の各々の両端と連結し、前記複数の水冷伝熱管の各々に冷却水を流通させる冷却水配管と、前記冷却水配管と連通し、前記冷却水配管に冷却水を供給する冷却水槽とを備える。 In order to achieve the above object, the present invention provides a cooling system for cooling a steel reactor containment vessel housing a reactor pressure vessel containing a reactor core, the cooling system being in contact with an outer wall of the reactor steel vessel. a plurality of water-cooled heat transfer tubes, a cooling water pipe connected to both ends of each of the plurality of water-cooled heat transfer tubes and for circulating cooling water to each of the plurality of water-cooled heat transfer tubes, and communicating with the cooling water pipe for cooling the water-cooled heat transfer tubes; A cooling water tank that supplies cooling water to the water pipes is provided.

本発明によれば、全交流電源喪失時等により既存の冷却システムが停止した場合でも原子炉格納容器を継続して冷却でき、工期とコストを抑制できる冷却システムを提供できる。上記した以外の課題、構成及び効果は、以下の実施形態の説明により明らかにされる。 According to the present invention, it is possible to provide a cooling system that can continue to cool the reactor containment vessel even when the existing cooling system is stopped due to a complete loss of AC power, etc., and can reduce construction time and costs. Problems, configurations, and effects other than those described above will be made clear by the following description of the embodiments.

本発明の第１の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成を示す概略図である。1 is a schematic diagram showing the configuration of a nuclear power plant using a cooling system for a reactor containment vessel according to a first embodiment of the present invention. 本発明の第１の実施形態による原子炉格納容器の冷却システムにおける複数の水冷伝熱管と原子炉格納容器の配置を示す概略断面図である。FIG. 2 is a schematic cross-sectional view showing the arrangement of a plurality of water-cooled heat transfer tubes and a reactor containment vessel in the reactor containment cooling system according to the first embodiment of the present invention. 本発明の第２の実施形態による原子炉格納容器の冷却システムに用いられる水冷伝熱管の断面図である。FIG. 3 is a cross-sectional view of a water-cooled heat transfer tube used in a cooling system for a reactor containment vessel according to a second embodiment of the present invention. 本発明の第３の実施形態による原子炉格納容器の冷却システムにおける複数の水冷伝熱管の各々の断面形状と、複数の水冷伝熱管と原子炉格納容器の配置を示す概略断面図である。FIG. 7 is a schematic cross-sectional view showing the cross-sectional shape of each of a plurality of water-cooled heat transfer tubes and the arrangement of the plurality of water-cooled heat transfer tubes and the reactor containment vessel in a cooling system for a reactor containment vessel according to a third embodiment of the present invention. 本発明の第４の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成を示す概略図である。FIG. 3 is a schematic diagram showing the configuration of a nuclear power plant using a cooling system for a reactor containment vessel according to a fourth embodiment of the present invention. 本発明の第５の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成の一例を示す概略図である。FIG. 3 is a schematic diagram showing an example of the configuration of a nuclear power plant using a cooling system for a reactor containment vessel according to a fifth embodiment of the present invention. 本発明の第５の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成の他の例を示す概略図である。FIG. 7 is a schematic diagram showing another example of the configuration of a nuclear power plant using the reactor containment cooling system according to the fifth embodiment of the present invention. 本発明の第６の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成を示す概略図である。FIG. 3 is a schematic diagram showing the configuration of a nuclear power plant using a cooling system for a reactor containment vessel according to a sixth embodiment of the present invention. 本発明の第７の実施形態による原子炉格納容器の冷却システムを用いた原子力発電プラントの構成を示す概略図である。FIG. 7 is a schematic diagram showing the configuration of a nuclear power plant using a cooling system for a reactor containment vessel according to a seventh embodiment of the present invention.

以下、図面を用いて、本発明の第１～第７の実施形態による原子炉格納容器の冷却システムの構成及び動作について説明する。なお、各図において、同一符号は同一部分を示す。また、各図面は、互いに直交するＸＹＺ軸により方向を特定し、＋Ｘを「右」、－Ｘを「左」、＋Ｙを「上」、－Ｙを「下」、＋Ｚを「前」、－Ｚを「後」と規定する。また、本発明の冷却システムは、沸騰水型軽水炉（ＢＷＲ）に用いることができ、原子力発電プラントの熱出力に対して原子炉格納容器の表面積が大きい小型炉（ＳＭＲ）に特に好適である。 The configuration and operation of the reactor containment vessel cooling system according to the first to seventh embodiments of the present invention will be described below with reference to the drawings. Note that in each figure, the same reference numerals indicate the same parts. In addition, each drawing specifies the direction using the XYZ axes that are orthogonal to each other, and +X is "right", -X is "left", +Y is "up", -Y is "down", +Z is "front", - Z is defined as "back". Furthermore, the cooling system of the present invention can be used in a boiling water reactor (BWR), and is particularly suitable for a small reactor (SMR) in which the surface area of the reactor containment vessel is large relative to the thermal output of a nuclear power plant.

（第１の実施形態）
図１は、本発明の第１の実施形態による原子炉格納容器の冷却システム１０を用いた原子力発電プラント１００の構成を示す概略図で、図２は、本発明の第１の実施形態による原子炉格納容器の冷却システムにおける複数本の水冷伝熱管と原子炉格納容器の配置を示す概略断面図である。 (First embodiment)
FIG. 1 is a schematic diagram showing the configuration of a nuclear power plant 100 using a reactor containment cooling system 10 according to a first embodiment of the present invention, and FIG. FIG. 2 is a schematic cross-sectional view showing the arrangement of a plurality of water-cooled heat transfer tubes and a reactor containment vessel in a reactor containment cooling system.

原子力発電プラント１００は沸騰水型軽水炉（ＢＷＲ）で、図１に示すように、炉心１と、炉心１を内蔵する原子炉圧力容器２と、原子炉圧力容器２を格納する原子炉格納容器３と、原子炉格納容器３を冷却する冷却システム１０とを備える。 The nuclear power plant 100 is a boiling water light water reactor (BWR), and as shown in FIG. and a cooling system 10 that cools the reactor containment vessel 3.

原子炉格納容器３は、原子炉圧力容器を格納するための気密性の高い容器で、冷却システム１０により効率よく冷却するために鋼製になっている。また、本実施形態の原子炉格納容器３は略円筒形となっている。 The reactor containment vessel 3 is a highly airtight vessel for storing a reactor pressure vessel, and is made of steel in order to be efficiently cooled by the cooling system 10. Further, the reactor containment vessel 3 of this embodiment has a substantially cylindrical shape.

冷却システム１０は、鋼製の原子炉格納容器３を冷却するシステムで、原子炉格納容器３の側面に接触する複数の水冷伝熱管４と、複数の水冷伝熱管４の各々の両端と連結し、複数の水冷伝熱管４の各々に冷却水ＣＷを流通させる冷却水配管５と、冷却水配管５と連通し冷却水ＣＷを供給する冷却水槽６とを備える。 The cooling system 10 is a system for cooling the reactor containment vessel 3 made of steel, and is connected to a plurality of water-cooled heat transfer tubes 4 that contact the side surfaces of the reactor containment vessel 3 and both ends of each of the plurality of water-cooled heat transfer tubes 4. , a cooling water pipe 5 that allows cooling water CW to flow through each of the plurality of water-cooled heat transfer tubes 4, and a cooling water tank 6 that communicates with the cooling water pipe 5 and supplies the cooling water CW.

複数の水冷伝熱管４の各々は鋼管で、図１に示すように原子炉格納容器３の側面に沿ってＹ軸方向(上下方向)に伸び、原子炉格納容器３の側面に接触する。また、複数の水冷伝熱管４は、図２に示すように、原子炉格納容器３の周方向に隙間なく配列され、隣合う水冷伝熱管４どうしが接している。これにより、冷却システム１０は、原子炉格納容器３の熱を複数の水冷伝熱管４に移動させ、原子炉格納容器３を冷却できる。 Each of the plurality of water-cooled heat transfer tubes 4 is a steel pipe, and as shown in FIG. 1, extends in the Y-axis direction (vertical direction) along the side surface of the reactor containment vessel 3 and comes into contact with the side surface of the reactor containment vessel 3. Moreover, as shown in FIG. 2, the plurality of water-cooled heat transfer tubes 4 are arranged without gaps in the circumferential direction of the reactor containment vessel 3, and adjacent water-cooled heat transfer tubes 4 are in contact with each other. Thereby, the cooling system 10 can transfer the heat of the reactor containment vessel 3 to the plurality of water-cooled heat transfer tubes 4 to cool the reactor containment vessel 3.

冷却水配管５は、複数の水冷伝熱管４の各々の両端と連結し、複数の水冷伝熱管４の各々に冷却水ＣＷを流通させるための配管である。図１に示すように冷却水配管５は、水冷伝熱管４の上端と連結し冷却水配管５において上方（＋Ｙ軸方向）に配置される上方配管５ａと、水冷伝熱管４の下端と連結し冷却水配管５において下方（－Ｙ軸方向）に配置される下方配管５ｂと、上方配管５ａと下方配管５ｂとの間に設けられ上方配管５ａと下方配管５ｂとを連結する中間配管５ｃとを備える。中間配管５ｃには冷却水ポンプ５ｄと熱交換器５ｅが設けられ、冷却水ポンプ５ｄから熱交換器５ｅに冷却水が吐出されるように配置されている。 The cooling water pipe 5 is connected to both ends of each of the plurality of water-cooled heat exchanger tubes 4, and is a pipe for circulating cooling water CW to each of the plurality of water-cooled heat exchanger tubes 4. As shown in FIG. 1, the cooling water piping 5 is connected to the upper end of the water-cooled heat exchanger tube 4 and is connected to the upper piping 5a, which is arranged upward (in the +Y-axis direction) in the cooling water piping 5, and the lower end of the water-cooled heat exchanger tube 4. In the cooling water pipe 5, a lower pipe 5b is arranged downward (in the −Y axis direction), and an intermediate pipe 5c is provided between the upper pipe 5a and the lower pipe 5b and connects the upper pipe 5a and the lower pipe 5b. Be prepared. A cooling water pump 5d and a heat exchanger 5e are provided in the intermediate pipe 5c, and are arranged so that cooling water is discharged from the cooling water pump 5d to the heat exchanger 5e.

なお、冷却システム１０の冷却水配管５としては、原子力発電プラント１００の補機（図示せず）を冷却する冷却水系統（原子炉補機冷却水系）に含まれる既存の配管を用いることができる。この場合、冷却水ポンプ５ｄと熱交換器５ｅには、同じく原子炉補機冷却水系に含まれる冷却水ポンプと熱交換器が用いることができる。 Note that as the cooling water piping 5 of the cooling system 10, existing piping included in a cooling water system (reactor auxiliary cooling water system) that cools auxiliary equipment (not shown) of the nuclear power plant 100 can be used. . In this case, a cooling water pump and a heat exchanger that are also included in the reactor auxiliary cooling water system can be used as the cooling water pump 5d and the heat exchanger 5e.

冷却水槽６は、冷却水ＣＷが貯蔵されるタンクで、図１に示すように水冷伝熱管４の上端より上方（＋Ｙ軸方向）に配置されている。冷却水槽６の下部（本実施形態では底面）には第１排水口６ａが設けられ、第１排水口６ａには排水管６ｂの一端が取り付けられている。そして、排水管６ｂの他端には上方配管５ａが連結し、これにより冷却水槽６と上方配管５ａが連通される。そのため、冷却水槽６に冷却水ＣＷを満たすことにより、水冷伝熱管４と冷却水配管５には冷却水ＣＷが確保される。なお、冷却システム１０の冷却水槽６としては原子炉補機冷却水系に含まれるサージタンクを用いることができる。 The cooling water tank 6 is a tank in which cooling water CW is stored, and is arranged above the upper end of the water-cooled heat transfer tube 4 (in the +Y-axis direction), as shown in FIG. A first drain port 6a is provided at the lower part (bottom surface in this embodiment) of the cooling water tank 6, and one end of a drain pipe 6b is attached to the first drain port 6a. The upper pipe 5a is connected to the other end of the drain pipe 6b, thereby communicating the cooling water tank 6 and the upper pipe 5a. Therefore, by filling the cooling water tank 6 with cooling water CW, the cooling water CW is ensured in the water-cooled heat exchanger tubes 4 and the cooling water piping 5. Note that as the cooling water tank 6 of the cooling system 10, a surge tank included in the reactor auxiliary equipment cooling water system can be used.

（動作）
まず、通常通りに稼動する冷却システム１０の動作について説明する。冷却水槽６から注入され、冷却水配管５と水冷伝熱管４に充満する冷却水ＣＷは、冷却水ポンプ５ｄが稼動することにより冷却水配管５と水冷伝熱管４を循環する。 (motion)
First, the operation of the cooling system 10 that operates normally will be described. The cooling water CW injected from the cooling water tank 6 and filling the cooling water piping 5 and the water-cooled heat exchanger tubes 4 circulates through the cooling water piping 5 and the water-cooled heat exchanger tubes 4 by operating the cooling water pump 5d.

水冷伝熱管４を流通する冷却水ＣＷには、原子炉格納容器３から水冷伝熱管４に移動した熱が移動する。熱が移動した冷却水ＣＷは、水冷伝熱管４から上方配管５ａへ、上方配管５ａから中間配管５ｃへ流入する。中間配管５ｃには冷却水ポンプ５ｄが設けられていて、冷却水ＣＷは冷却水ポンプ５ｄにより熱交換器５ｅへ吐出される。熱交換器５ｅに送られた冷却水ＣＷは熱交換器５ｅにより熱が奪われ冷却される。冷却された冷却水ＣＷは、中間配管５ｃから下方配管５ｂへ流入し、下方配管５ｂから再び水冷伝熱管４に送られる。水冷伝熱管４では再び原子炉格納容器３から水冷伝熱管４に移動した熱が冷却水ＣＷに移動する。このように、通常通りに原子力発電プラント１００が稼動する場合の冷却システム１０は、冷却水ポンプ５ｄを稼動させることにより冷却水ＣＷを循環させ、原子炉格納容器３を冷却する。 The heat transferred from the reactor containment vessel 3 to the water-cooled heat transfer tubes 4 is transferred to the cooling water CW flowing through the water-cooled heat transfer tubes 4 . The cooling water CW, to which the heat has been transferred, flows from the water-cooled heat transfer tube 4 to the upper pipe 5a, and from the upper pipe 5a to the intermediate pipe 5c. A cooling water pump 5d is provided in the intermediate pipe 5c, and the cooling water CW is discharged to the heat exchanger 5e by the cooling water pump 5d. The cooling water CW sent to the heat exchanger 5e has its heat removed by the heat exchanger 5e and is cooled. The cooled cooling water CW flows into the lower pipe 5b from the intermediate pipe 5c, and is sent to the water-cooled heat transfer tube 4 again from the lower pipe 5b. In the water-cooled heat transfer tubes 4, the heat transferred from the reactor containment vessel 3 to the water-cooled heat transfer tubes 4 is transferred to the cooling water CW again. In this way, when the nuclear power plant 100 operates normally, the cooling system 10 circulates the cooling water CW by operating the cooling water pump 5d to cool the reactor containment vessel 3.

次に、全交流電源喪失時等により冷却水ポンプ５ｄが停止した場合の冷却システム１０の動作について説明する。この場合、冷却水ポンプ５ｄが停止するため、冷却水ＣＷは冷却水配管５と水冷伝熱管４を循環せず、冷却水配管５と水冷伝熱管４に滞留する。 Next, the operation of the cooling system 10 when the cooling water pump 5d stops due to a complete loss of AC power, etc. will be described. In this case, since the cooling water pump 5d is stopped, the cooling water CW does not circulate through the cooling water piping 5 and the water-cooled heat exchanger tubes 4, but stays in the cooling water piping 5 and the water-cooled heat exchanger tubes 4.

水冷伝熱管４に滞留する冷却水ＣＷは、原子炉格納容器３から水冷伝熱管４に移動した熱により熱せられる。これにより、水冷伝熱管４の冷却水ＣＷは、冷却水配管５と冷却水槽６の冷却水ＣＷと比較して相対的に高温になる。そのため、水冷伝熱管４の冷却水ＣＷは上昇し、上方配管５ａを介して冷却水槽６に流入する。また、冷却水槽６の冷却水ＣＷは下降し、上方配管５ａを介して水冷伝熱管４に流入する。そのため、水冷伝熱管４と冷却水槽６の間には、冷却水ＣＷの自然対流現象が発生する。これにより、水冷伝熱管４の熱を冷却水ＣＷに移動させ、原子炉格納容器３を冷却することができる。 The cooling water CW staying in the water-cooled heat transfer tube 4 is heated by the heat transferred from the reactor containment vessel 3 to the water-cooled heat transfer tube 4 . As a result, the cooling water CW of the water-cooled heat transfer tube 4 becomes relatively high in temperature compared to the cooling water CW of the cooling water pipe 5 and the cooling water tank 6. Therefore, the cooling water CW of the water-cooled heat transfer tube 4 rises and flows into the cooling water tank 6 via the upper pipe 5a. Further, the cooling water CW in the cooling water tank 6 descends and flows into the water-cooled heat transfer tubes 4 via the upper pipe 5a. Therefore, a natural convection phenomenon of the cooling water CW occurs between the water-cooled heat transfer tube 4 and the cooling water tank 6. Thereby, the heat of the water-cooled heat transfer tube 4 can be transferred to the cooling water CW, and the reactor containment vessel 3 can be cooled.

特に原子炉圧力容器２と原子炉格納容器３の間に存在する配管（図示せず）が破断し原子炉圧力容器２の崩壊熱を含んだ蒸気が原子炉格納容器３に流入する原子炉冷却材喪失事故（ＬＯＣＡ）時において、原子炉格納容器３を密閉したまま効率よく原子炉格納容器３を冷却できるので、本実施形態は好適である。 In particular, reactor cooling occurs when a pipe (not shown) existing between the reactor pressure vessel 2 and the reactor containment vessel 3 ruptures, and steam containing the decay heat of the reactor pressure vessel 2 flows into the reactor containment vessel 3. In the event of a loss of material accident (LOCA), the present embodiment is suitable because the reactor containment vessel 3 can be efficiently cooled while the reactor containment vessel 3 is kept sealed.

なお、水冷伝熱管４の上端から第１排水口６ａに至るまでの上方配管５ａ及び排水管６ｂの高さは単調に増加するように設けることが好ましい。このように上方配管５ａ及び排水管６ｂを設けると、冷却水槽６内の冷却水ＣＷが重力により水冷伝熱管４内に容易に導入されるので、水冷伝熱管４と冷却水槽６の間における冷却水ＣＷの対流が発生しやすくなり、原子炉格納容器３を冷却しやすくなる。 Note that it is preferable that the heights of the upper pipe 5a and the drain pipe 6b from the upper end of the water-cooled heat transfer tube 4 to the first drain port 6a increase monotonically. When the upper pipe 5a and the drain pipe 6b are provided in this way, the cooling water CW in the cooling water tank 6 is easily introduced into the water-cooled heat exchanger tube 4 by gravity, so that the cooling between the water-cooled heat exchanger tube 4 and the cooling water tank 6 is improved. Convection of water CW is more likely to occur, making it easier to cool the reactor containment vessel 3.

（効果）
本実施形態の原子炉格納容器３の冷却システム１０は、全交流電源喪失時等により冷却水ポンプ５ｄが稼動せず、通常時における冷却システム１０が停止する非常時において、原子炉格納容器３に接する水冷伝熱管４と冷却水槽６の間に冷却水ＣＷの自然対流現象が発生し、原子炉格納容器３を継続して冷却できる。 (effect)
The cooling system 10 for the reactor containment vessel 3 according to the present embodiment is configured to cool the reactor containment vessel 3 in an emergency when the cooling water pump 5d does not operate due to a total AC power loss, etc., and the cooling system 10 normally stops. A natural convection phenomenon of cooling water CW occurs between the water-cooled heat transfer tubes 4 and the cooling water tank 6 that are in contact with each other, and the reactor containment vessel 3 can be continuously cooled.

また、本実施形態の原子炉格納容器３の冷却システム１０は、大量の冷却水を貯蔵する外周プールを備えないため、工期とコストを抑制できる。特に、本実施形態の原子炉格納容器３の冷却システム１０は、冷却水配管５として原子炉補機冷却水系に含まれる既存の配管を用い、冷却水槽６として原子炉補機冷却水系に含まれる既存のサージタンクを用いることができる。そのため、冷却水配管５と冷却水槽６として新規設備を設けなくてもよく、工期とコストをさらに抑制できる。 Moreover, since the cooling system 10 for the reactor containment vessel 3 of this embodiment does not include an outer peripheral pool that stores a large amount of cooling water, the construction period and cost can be reduced. In particular, the cooling system 10 for the reactor containment vessel 3 of this embodiment uses existing piping included in the reactor auxiliary cooling water system as the cooling water piping 5, and using existing piping included in the reactor auxiliary cooling water system as the cooling water tank 6. An existing surge tank can be used. Therefore, there is no need to provide new equipment for the cooling water piping 5 and the cooling water tank 6, and the construction period and cost can be further reduced.

（第２の実施形態）
図３は、本発明の第２の実施形態による原子炉格納容器３の冷却システム１０に用いられる水冷伝熱管４の断面図である。 (Second embodiment)
FIG. 3 is a sectional view of a water-cooled heat transfer tube 4 used in a cooling system 10 for a reactor containment vessel 3 according to a second embodiment of the present invention.

本実施形態に係る冷却システム１０が第１実施形態と異なる点は、水冷伝熱管４の内壁に複数の伝熱フィン４ａが設けられている点である。これにより、水冷伝熱管４は冷却水ＣＷと接する表面積が大きくなり、原子炉格納容器３の熱を第１実施形態の円環の水冷伝熱管４よりも多く冷却水ＣＷに移動させることができる。 The cooling system 10 according to this embodiment differs from the first embodiment in that a plurality of heat transfer fins 4a are provided on the inner wall of the water-cooled heat transfer tube 4. As a result, the water-cooled heat transfer tube 4 has a larger surface area in contact with the cooling water CW, and can transfer more heat from the reactor containment vessel 3 to the cooling water CW than the annular water-cooled heat transfer tube 4 of the first embodiment. .

（第３の実施形態）
図４は、本発明の第３の実施形態による原子炉格納容器３の冷却システム１０における複数の水冷伝熱管４の各々の断面形状と、複数の水冷伝熱管４と原子炉格納容器３の配置を示す概略断面図である。 (Third embodiment)
FIG. 4 shows the cross-sectional shape of each of a plurality of water-cooled heat exchanger tubes 4 in a cooling system 10 for a reactor containment vessel 3 according to a third embodiment of the present invention, and the arrangement of a plurality of water-cooled heat exchanger tubes 4 and a reactor containment vessel 3. FIG.

本実施形態に係る冷却システム１０が第１実施形態と異なる点は、水冷伝熱管４の形状である。具体的には、本実施形態に係る複数の水冷伝熱管４の各々には、原子炉格納容器３の外壁に対向し、原子炉格納容器３の外壁と面接触する第１側面４ｂが設けられている。これにより、複数の水冷伝熱管４の各々の原子炉格納容器３の外壁と接触する面積が大きくなり、原子炉格納容器３から水冷伝熱管４に移動する熱を多くすることができる。 The cooling system 10 according to this embodiment differs from the first embodiment in the shape of the water-cooled heat exchanger tubes 4. Specifically, each of the plurality of water-cooled heat transfer tubes 4 according to the present embodiment is provided with a first side surface 4b that faces the outer wall of the reactor containment vessel 3 and is in surface contact with the outer wall of the reactor containment vessel 3. ing. This increases the area of each of the plurality of water-cooled heat transfer tubes 4 in contact with the outer wall of the reactor containment vessel 3, and it is possible to increase the amount of heat transferred from the reactor containment vessel 3 to the water-cooled heat transfer tubes 4.

また、本実施形態に係る複数の水冷伝熱管４のうち隣合う２つの水冷伝熱管４の各々には、互いに対向し、互いに面接触する第２側面４ｃが設けられている。これにより、複数の水冷伝熱管４の各々は、冷却水ＣＷの流量と冷却水ＣＷに接する水冷伝熱管４の内壁の表面積を増加させることができ、原子炉格納容器３から冷却水ＣＷに移動する熱量が多くなるので、原子炉格納容器３を効果的に冷却できる。 Further, each of two adjacent water-cooled heat exchanger tubes 4 among the plurality of water-cooled heat exchanger tubes 4 according to this embodiment is provided with second side surfaces 4c that face each other and make surface contact with each other. As a result, each of the plurality of water-cooled heat transfer tubes 4 can increase the flow rate of the cooling water CW and the surface area of the inner wall of the water-cooled heat transfer tubes 4 in contact with the cooling water CW, and move from the reactor containment vessel 3 to the cooling water CW. Since the amount of heat generated increases, the reactor containment vessel 3 can be effectively cooled.

（第４の実施形態）
図５は、本発明の第４の実施形態による原子炉格納容器３の冷却システム２０を用いた原子力発電プラント１００の構成を示す概略図である。 (Fourth embodiment)
FIG. 5 is a schematic diagram showing the configuration of a nuclear power plant 100 using a cooling system 20 for a reactor containment vessel 3 according to a fourth embodiment of the present invention.

本実施形態に係る冷却システム２０が第１実施形態と異なる点は、冷却水槽６の形態である。即ち、本実施形態に係る冷却システム２０は、冷却水槽６として、原子炉格納容器３の上部に設けられ、燃料交換時に水が貯蔵される原子炉ウェルを用いる。そのため、冷却水槽６を新たに設けなくてもよく、工期とコストを抑制できる。なお、図５において、第１排水口６ａの位置を冷却水槽６である原子炉ウェルの側面の下部に示したが、これは一例であり、原子炉ウェルの底面でもよいことは言うまでもない。 The cooling system 20 according to this embodiment differs from the first embodiment in the form of the cooling water tank 6. That is, the cooling system 20 according to the present embodiment uses, as the cooling water tank 6, a reactor well that is provided in the upper part of the reactor containment vessel 3 and stores water during fuel exchange. Therefore, there is no need to newly provide the cooling water tank 6, and the construction period and cost can be reduced. In FIG. 5, the position of the first drain port 6a is shown at the lower side of the reactor well, which is the cooling water tank 6, but this is just an example, and it goes without saying that it may be located at the bottom of the reactor well.

（第５の実施形態）
図６は、本発明の第５の実施形態による原子炉格納容器３の冷却システム３０を用いた原子力発電プラント１００の構成の一例を示す概略図である。また、図７は、本発明の第５の実施形態による原子炉格納容器３の冷却システム３０を用いた原子力発電プラント１００の構成の他の例を示す概略図である。 (Fifth embodiment)
FIG. 6 is a schematic diagram showing an example of the configuration of a nuclear power plant 100 using a cooling system 30 for a reactor containment vessel 3 according to a fifth embodiment of the present invention. Moreover, FIG. 7 is a schematic diagram showing another example of the configuration of the nuclear power plant 100 using the cooling system 30 for the reactor containment vessel 3 according to the fifth embodiment of the present invention.

本実施形態に係る冷却システム３０が第１実施形態または第４の実施形態と異なる点は、冷却水槽６（サージタンクまたは原子炉ウェル）に第２排水口６ｃと冷水下降用配管６ｄと冷水下降用配管６ｄの冷却水ＣＷの流れを制御する制御弁（本実施形態では逆止弁６ｅ）とを備える点である。 The cooling system 30 according to the present embodiment is different from the first embodiment or the fourth embodiment in that the cooling water tank 6 (surge tank or reactor well) has a second drain port 6c, a cold water descending pipe 6d, and a cold water descending pipe 6d. It is provided with a control valve (in this embodiment, a check valve 6e) that controls the flow of cooling water CW in the service pipe 6d.

第２排水口６ｃは、第１排水口６ａと同様に冷却水槽６の下部に設けられ、冷水下降用配管６ｄが取り付けられている。冷水下降用配管６ｄは下方配管５ｂに連結し、冷却水槽６と下方配管５ｂを連通する。なお、冷却水槽６に貯蔵された冷却水ＣＷを水冷伝熱管４へ短時間で供給するためには、冷水下降用配管６ｄの長さはできるだけ短いことが好ましい。 The second drain port 6c is provided at the lower part of the cooling water tank 6 similarly to the first drain port 6a, and a cold water descending pipe 6d is attached thereto. The cold water descending pipe 6d is connected to the lower pipe 5b, and communicates the cooling water tank 6 with the lower pipe 5b. In addition, in order to supply the cooling water CW stored in the cooling water tank 6 to the water-cooled heat exchanger tube 4 in a short time, it is preferable that the length of the cold water descending pipe 6d is as short as possible.

また、冷水下降用配管６ｄには、冷却水槽６から下方配管５ｂへの冷却水ＣＷの流れを許容し、下方配管５ｂから冷却水槽６への冷却水ＣＷの流れを禁止する逆止弁６ｅが設けられている。なお、逆止弁６ｅは、冷却水ポンプ５ｄが停止したときに、冷水下降用配管６ｄ内の冷却水ＣＷの自重を加えた圧力によって逆止弁６ｅの弁がより開きやすいように、冷水下降用配管６ｄの下部（下方配管５ｂのできるだけ近く）に設けることが好ましい。 Further, the cold water descending pipe 6d is provided with a check valve 6e that allows the flow of the cooling water CW from the cooling water tank 6 to the lower pipe 5b and prohibits the flow of the cooling water CW from the lower pipe 5b to the cooling water tank 6. It is provided. In addition, the check valve 6e is designed so that when the cooling water pump 5d stops, the check valve 6e is opened more easily by the pressure added with the weight of the cooling water CW in the cold water descending pipe 6d. It is preferable to provide it at the lower part of the pipe 6d (as close as possible to the lower pipe 5b).

（動作）
全交流電源喪失時等により冷却水ポンプ５ｄが停止した場合、水冷伝熱管４に滞留する冷却水ＣＷは、原子炉格納容器３から水冷伝熱管４に移動した熱により熱せられる。これにより、水冷伝熱管４の冷却水ＣＷは、冷却水配管５と冷却水槽６の冷却水ＣＷと比較して相対的に高温になる。そのため、水冷伝熱管４の冷却水ＣＷは上昇し、上方配管５ａと排水管６ｂを介して冷却水槽６に流入する。そして、冷却水槽６の冷却水ＣＷは下降し、冷水下降用配管６ｄと下方配管５ｂを介して水冷伝熱管４に流入する。これにより、水冷伝熱管４の熱を冷却水ＣＷに移動させ、原子炉格納容器３を冷却することができる。 (motion)
When the cooling water pump 5d is stopped due to a complete loss of AC power, etc., the cooling water CW remaining in the water-cooled heat exchanger tubes 4 is heated by the heat transferred from the reactor containment vessel 3 to the water-cooled heat exchanger tubes 4. As a result, the cooling water CW of the water-cooled heat transfer tube 4 becomes relatively high in temperature compared to the cooling water CW of the cooling water pipe 5 and the cooling water tank 6. Therefore, the cooling water CW of the water-cooled heat transfer tube 4 rises and flows into the cooling water tank 6 via the upper pipe 5a and the drain pipe 6b. Then, the cooling water CW in the cooling water tank 6 descends and flows into the water-cooled heat transfer tube 4 via the cold water descending pipe 6d and the lower pipe 5b. Thereby, the heat of the water-cooled heat transfer tube 4 can be transferred to the cooling water CW, and the reactor containment vessel 3 can be cooled.

なお、逆止弁６ｅは、冷却水ポンプ５ｄが稼動する場合（通常時）には、冷却水ポンプ５ｄにより中間配管５ｃから下方配管５ｂへ吐出された冷却水ＣＷが冷水下降用配管６ｄに流入することを防止する。一方、冷却水ポンプ５ｄが停止する場合（非常時）には、逆止弁６ｅは冷却水槽６に貯蔵されている冷却水ＣＷの水圧により開き、冷却水槽６から下方配管５ｂに冷却水ＣＷを流す。 Note that the check valve 6e prevents the cooling water CW discharged from the intermediate pipe 5c to the lower pipe 5b by the cooling water pump 5d from flowing into the cold water descending pipe 6d when the cooling water pump 5d operates (normally). prevent On the other hand, when the cooling water pump 5d is stopped (in an emergency), the check valve 6e is opened by the water pressure of the cooling water CW stored in the cooling water tank 6, and the cooling water CW is supplied from the cooling water tank 6 to the lower pipe 5b. Flow.

（効果）
本実施形態の冷却システム３０は、全交流電源喪失時等により冷却水ポンプ５ｄを稼動できない非常時において、原子炉格納容器３から水冷伝熱管４に移動した熱により加熱されて上昇する冷却水（温水）ＣＷが上方配管５ａを介して排水管６ｂから冷却水槽６に流入するときに、冷却水槽６内の冷却水（冷水）ＣＷを下方配管５ｂ（水冷伝熱管４の下端）に流入できる冷水下降用配管６ｄを備えている。すなわち、本実施形態の冷却システム３０では、冷水下降用配管６ｄが追加することにより水冷伝熱管４と冷却水槽６の間を冷却水ＣＷが自然対流により循環する流路が形成されるので、原子炉格納容器３を確実に継続して冷却できる。 (effect)
In the case of an emergency in which the cooling water pump 5d cannot be operated due to a total AC power loss or the like, the cooling system 30 of this embodiment is configured to provide cooling water ( Cold water that can flow the cooling water (cold water) CW in the cooling water tank 6 into the lower pipe 5b (lower end of the water-cooled heat transfer tube 4) when the hot water) CW flows into the cooling water tank 6 from the drain pipe 6b via the upper pipe 5a. A descending pipe 6d is provided. That is, in the cooling system 30 of this embodiment, by adding the cold water descending pipe 6d, a flow path is formed in which the cooling water CW circulates between the water-cooled heat exchanger tube 4 and the cooling water tank 6 by natural convection, so that the atomic The reactor containment vessel 3 can be reliably and continuously cooled.

また、冷却水ポンプ５ｄを稼動できる場合（通常時）には、冷却水ポンプ５ｄにより中間配管５ｃから下方配管５ｂへ吐出された冷却水ＣＷは、逆止弁６ｅにより冷水下降用配管６ｄに流入することが防止されるため、水冷伝熱管４を流通する冷却水ＣＷの量の減少が抑制され冷却性能を維持できる。 Furthermore, when the cooling water pump 5d can be operated (normally), the cooling water CW discharged from the intermediate pipe 5c to the lower pipe 5b by the cooling water pump 5d flows into the cold water descending pipe 6d by the check valve 6e. Since this is prevented, the decrease in the amount of cooling water CW flowing through the water-cooled heat exchanger tubes 4 is suppressed, and cooling performance can be maintained.

（第６の実施形態）
図８は、本発明の第６の実施形態による原子炉格納容器３の冷却システム４０を用いた原子力発電プラント１００の構成を示す概略図である。 (Sixth embodiment)
FIG. 8 is a schematic diagram showing the configuration of a nuclear power plant 100 using a cooling system 40 for a reactor containment vessel 3 according to a sixth embodiment of the present invention.

本実施形態に係る冷却システム４０が第５実施形態と異なる点は、逆止弁６ｅ（制御弁）に代えて、電磁弁６ｆとバッテーリー等の直流電源（図示せず）と制御装置（図示せず）を備える点である。 The cooling system 40 according to this embodiment differs from the fifth embodiment in that instead of a check valve 6e (control valve), a solenoid valve 6f, a DC power source (not shown) such as a battery, and a control device (not shown) are used. The point is to have the following.

電磁弁６ｆは、非通電時に閉じ通電時に開くノーマルクローズタイプの電磁弁である。制御装置は、直流電源と電磁弁６ｆの通電を制御する装置で、通常時には電磁弁６ｆに通電せず、非常時には電磁弁６ｆに通電する。すなわち、通常時には、電磁弁６ｆが閉じ、冷却水ポンプ５ｄにより中間配管５ｃから下方配管５ｂへ吐出された冷却水ＣＷが冷水下降用配管６ｄに流入することが防止されるため、水冷伝熱管４を流通する冷却水ＣＷの量の減少が抑制され、冷却性能を維持できる。 The solenoid valve 6f is a normally closed type solenoid valve that closes when not energized and opens when energized. The control device is a device that controls energization of the DC power source and the solenoid valve 6f, and does not energize the solenoid valve 6f in normal times, but energizes the solenoid valve 6f in an emergency. That is, in normal times, the solenoid valve 6f is closed and the cooling water CW discharged from the intermediate pipe 5c to the lower pipe 5b by the cooling water pump 5d is prevented from flowing into the cold water descending pipe 6d. A decrease in the amount of cooling water CW flowing through the cooling water CW is suppressed, and cooling performance can be maintained.

一方、異常時には、制御装置が電磁弁６ｆを通電して開き、冷却水槽６の冷却水ＣＷを冷水下降用配管６ｄにより下降させ、下方配管５ｂを介して水冷伝熱管４に流入させることができる。そのため、原子炉格納容器３に接する水冷伝熱管４と冷却水槽６の間に自然対流による冷却水ＣＷの循環を発生させ、原子炉格納容器３を確実に継続して冷却できる。 On the other hand, in the event of an abnormality, the control device energizes the solenoid valve 6f to open it, allowing the cooling water CW in the cooling water tank 6 to be lowered by the cold water descending pipe 6d, and to flow into the water-cooled heat exchanger tubes 4 via the lower pipe 5b. . Therefore, circulation of the cooling water CW by natural convection is generated between the water-cooled heat transfer tubes 4 and the cooling water tank 6 in contact with the reactor containment vessel 3, and the reactor containment vessel 3 can be reliably and continuously cooled.

（第７の実施形態）
図９は、本発明の第７の実施形態による原子炉格納容器３の冷却システム５０を用いた原子力発電プラント１００の構成を示す概略図である。本実施形態に係る冷却システム５０が第５実施形態と異なる点は、逆止弁６ｅに代えて、遮断弁６ｇと圧縮空気設備（図示せず）が設けられている点である。 (Seventh embodiment)
FIG. 9 is a schematic diagram showing the configuration of a nuclear power plant 100 using a cooling system 50 for a reactor containment vessel 3 according to a seventh embodiment of the present invention. The cooling system 50 according to this embodiment differs from the fifth embodiment in that a cutoff valve 6g and compressed air equipment (not shown) are provided in place of the check valve 6e.

遮断弁６ｇは、空圧により閉じるノーマルオープンタイプの空圧弁である。圧縮空気設備は、例えばコンプレッサーであり、通常時（通電時）には空気を供給して遮断弁６ｇを閉じ、異常時（非通電時）には空気の供給を停止して遮断弁６ｇを開く。 The shutoff valve 6g is a normally open type pneumatic valve that is closed by air pressure. The compressed air equipment is, for example, a compressor, which supplies air and closes the shutoff valve 6g during normal times (when energized), and stops the supply of air and opens the shutoff valve 6g during abnormal times (when not energized). .

すなわち、通常時には、遮断弁６ｇが閉じ、冷却水ポンプ５ｄにより中間配管５ｃから下方配管５ｂへ吐出された冷却水ＣＷは冷水下降用配管６ｄに流入できない。それにより、水冷伝熱管４を流通する冷却水ＣＷの量の減少が抑制され、冷却性能を維持できる。 That is, under normal conditions, the shutoff valve 6g is closed, and the cooling water CW discharged from the intermediate pipe 5c to the lower pipe 5b by the cooling water pump 5d cannot flow into the cold water descending pipe 6d. Thereby, a decrease in the amount of cooling water CW flowing through the water-cooled heat transfer tubes 4 is suppressed, and cooling performance can be maintained.

一方、異常時には、遮断弁６ｇが開き、冷却水槽６の冷却水ＣＷを冷水下降用配管６ｄにより下降させ、下方配管５ｂを介して水冷伝熱管４に流入させることができる。そのため、原子炉格納容器３に接する水冷伝熱管４と冷却水槽６の間に自然対流による冷却水ＣＷの循環が発生し、原子炉格納容器３を確実に継続して冷却できる。 On the other hand, in the event of an abnormality, the shutoff valve 6g is opened, and the cooling water CW in the cooling water tank 6 can be lowered by the cold water descending pipe 6d, and can be made to flow into the water-cooled heat transfer tube 4 via the lower pipe 5b. Therefore, circulation of the cooling water CW due to natural convection occurs between the water-cooled heat transfer tubes 4 and the cooling water tank 6 that are in contact with the reactor containment vessel 3, and the reactor containment vessel 3 can be reliably and continuously cooled.

なお、本発明は上記した実施形態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、上述した実施形態は本発明を分かりやす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、ある実施形態の構成の一部を他の実施形態の構成に置き換えることが可能であり、また、ある実施形態の構成に他の実施形態の構成を加えることも可能である。また、各実施形態の構成の一部について、他の構成の追加・削除・置換をすることが可能である。例えば、第３の実施形態による原子炉格納容器３の冷却システム１０における複数の水冷伝熱管４の各々の内壁に複数の伝熱フィン４ａを設けても良い。そして、複数の伝熱フィン４ａの形状は、複数の水冷伝熱管４の各々の内壁から複数の水冷伝熱管４の各々の中心軸に向かって突出する形状でも良く、複数の水冷伝熱管４の各々の内壁面の法線方向に突出する形状でもよく、その他の形状でもよい。 Note that the present invention is not limited to the embodiments described above, and includes various modifications. For example, the embodiments described above have been described in detail to explain the present invention in an easy-to-understand manner, and the present invention is not necessarily limited to having all the configurations described. Furthermore, it is possible to replace a part of the configuration of one embodiment with the configuration of another embodiment, and it is also possible to add the configuration of another embodiment to the configuration of one embodiment. Furthermore, it is possible to add, delete, or replace some of the configurations of each embodiment with other configurations. For example, a plurality of heat transfer fins 4a may be provided on the inner wall of each of the plurality of water-cooled heat transfer tubes 4 in the cooling system 10 for the reactor containment vessel 3 according to the third embodiment. The shape of the plurality of heat transfer fins 4a may be a shape that protrudes from the inner wall of each of the plurality of water-cooled heat transfer tubes 4 toward the center axis of each of the plurality of water-cooled heat transfer tubes 4, and It may have a shape that projects in the normal direction of each inner wall surface, or it may have another shape.

１…炉心、２…原子炉圧力容器、３…原子炉格納容器、４…水冷伝熱管、５…冷却水配管、６…冷却水槽 1...Reactor core, 2...Reactor pressure vessel, 3...Reactor containment vessel, 4...Water-cooled heat transfer tube, 5...Cooling water piping, 6...Cooling water tank

Claims (11)

炉心を内蔵する原子炉圧力容器を格納する鋼製の原子炉格納容器を冷却する冷却システムであって、
前記原子炉格納容器の外壁に接触する複数の水冷伝熱管と、
前記複数の水冷伝熱管の各々の両端と連結し、前記複数の水冷伝熱管の各々に冷却水を流通させる冷却水配管と、
前記冷却水配管と連通し、前記冷却水配管に冷却水を供給する冷却水槽とを備えることを特徴とする冷却システム。 A cooling system that cools a steel reactor containment vessel that stores a reactor pressure vessel containing a reactor core,
a plurality of water-cooled heat transfer tubes in contact with an outer wall of the reactor containment vessel;
Cooling water piping connected to both ends of each of the plurality of water-cooled heat exchanger tubes and circulating cooling water to each of the plurality of water-cooled heat exchanger tubes;
A cooling system comprising: a cooling water tank that communicates with the cooling water pipe and supplies cooling water to the cooling water pipe. 請求項１に記載の冷却システムにおいて、
前記冷却水配管は、補機を冷却する冷却水系統に含まれる配管であり、
前記冷却水槽は、前記補機を冷却する冷却水系統に含まれるサージタンクであることを特徴とする冷却システム。 The cooling system according to claim 1,
The cooling water pipe is a pipe included in a cooling water system that cools the auxiliary equipment,
The cooling system is characterized in that the cooling water tank is a surge tank included in a cooling water system that cools the auxiliary equipment. 請求項１に記載の冷却システムにおいて、
前記冷却水槽が、原子炉ウェルであることを特徴とする冷却システム。 The cooling system according to claim 1,
A cooling system characterized in that the cooling water tank is a nuclear reactor well. 請求項１に記載の冷却システムにおいて、
前記冷却水槽の排水口が前記複数の水冷伝熱管の各々より上方に設けられ、
前記複数の水冷伝熱管の下端と前記冷却水槽の排水口を連通する冷水下降用配管と、
前記冷水下降用配管を流れる冷却水の流れを制御する制御弁を備えることを特徴とする冷却システム。 The cooling system according to claim 1,
A drain port of the cooling water tank is provided above each of the plurality of water-cooled heat transfer tubes,
cold water descending piping that communicates the lower ends of the plurality of water-cooled heat transfer tubes with the drain port of the cooling water tank;
A cooling system comprising a control valve that controls the flow of cooling water flowing through the cold water descending pipe. 請求項４に記載の冷却システムにおいて、
前記制御弁が逆止弁であることを特徴とする冷却システム。 The cooling system according to claim 4,
A cooling system characterized in that the control valve is a check valve. 請求項４に記載の冷却システムにおいて、
前記制御弁が電磁弁であることを特徴とする冷却システム。 The cooling system according to claim 4,
A cooling system characterized in that the control valve is a solenoid valve. 請求項４に記載の冷却システムにおいて、
前記制御弁が、空気圧により冷却水の流れを遮断する遮断弁であることを特徴とする冷却システム。 The cooling system according to claim 4,
A cooling system characterized in that the control valve is a shutoff valve that shuts off the flow of cooling water using air pressure. 請求項１に記載の冷却システムにおいて、
前記原子炉格納容器の側面が、前記複数の水冷伝熱管により覆われていることを特徴とする冷却システム。 The cooling system according to claim 1,
A cooling system characterized in that a side surface of the reactor containment vessel is covered with the plurality of water-cooled heat transfer tubes. 請求項１に記載の冷却システムにおいて、
前記複数の水冷伝熱管の内周壁に複数の放熱フィンが設けられていることを特徴とする冷却システム。 The cooling system according to claim 1,
A cooling system characterized in that a plurality of radiation fins are provided on an inner peripheral wall of the plurality of water-cooled heat transfer tubes. 請求項１に記載の冷却システムにおいて、
前記複数の水冷伝熱管の各々には、前記原子炉格納容器の外壁に対向し、前記原子炉格納容器の外壁と面接触する第１側面が設けられていることを特徴とする冷却システム。 The cooling system according to claim 1,
A cooling system characterized in that each of the plurality of water-cooled heat transfer tubes is provided with a first side surface that faces the outer wall of the reactor containment vessel and makes surface contact with the outer wall of the reactor containment vessel. 請求項１０に記載の冷却システムにおいて、
前記複数の水冷伝熱管のうち隣合う２つの水冷伝熱管の各々には、互いに対向し、互いに面接触する第２側面が設けられていることを特徴とする冷却システム。 The cooling system according to claim 10,
A cooling system characterized in that each of two adjacent water-cooled heat transfer tubes among the plurality of water-cooled heat transfer tubes is provided with a second side surface that faces each other and makes surface contact with each other.
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