JP6294168B2 - Nuclear power plant - Google Patents

Nuclear power plant Download PDF

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JP6294168B2
JP6294168B2 JP2014129464A JP2014129464A JP6294168B2 JP 6294168 B2 JP6294168 B2 JP 6294168B2 JP 2014129464 A JP2014129464 A JP 2014129464A JP 2014129464 A JP2014129464 A JP 2014129464A JP 6294168 B2 JP6294168 B2 JP 6294168B2
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water level
nuclear power
power plant
reactor well
water
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JP2016008883A (en
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達也 塚原
達也 塚原
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Hitachi GE Nuclear Energy Ltd
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    • 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
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    • Y02E30/30—Nuclear fission reactors

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Description

本発明は、原子炉ウェルを備えた原子力プラントに関するものである。   The present invention relates to a nuclear power plant having a reactor well.

原子力プラントでは、燃料から放出される放射線を遮蔽するため、定期検査時に燃料取り出し作業を行う際は、圧力容器上蓋および格納容器トップヘッドを取り外して燃料の取り出し経路となる圧力容器及び原子炉ウェルの水張りを行うとともに、水位計を用いて原子炉ウェル水位を監視する。   In a nuclear power plant, in order to shield the radiation emitted from the fuel, when performing fuel removal work during periodic inspections, the pressure vessel and reactor wells that serve as the fuel removal path by removing the pressure vessel top lid and the containment vessel top head are removed. In addition to water filling, the reactor well water level is monitored using a water level gauge.

定期検査時に原子炉ウェル水位を監視する方法として、例えば特許文献１及び２に記載のものがある。特許文献１には、原子炉ウェルプールの上方に設置した原子炉ウェル水位計を用いて原子炉ウェル水位を監視する方法が記載されている（図５及び［００５６］等）。一方、特許文献２には、圧力容器の内部に連通する計装配管に接続された定検時水張り用水位計を用いて原子炉ウェル水位を監視する方法が記載されている（図１及び［００１６］等）。   As a method for monitoring the reactor well water level during periodic inspection, there are methods described in Patent Documents 1 and 2, for example. Patent Document 1 describes a method of monitoring a reactor well water level using a reactor well water level meter installed above a reactor well pool (FIG. 5 and [0056], etc.). On the other hand, Patent Document 2 describes a method of monitoring a reactor well water level using a water gauge for water filling during regular inspection connected to an instrumentation pipe communicating with the inside of a pressure vessel (FIGS. 1 and [ 0016] etc.).

特開平１１−２０２０７９号公報Japanese Patent Laid-Open No. 11-202079 特開２０１３−１０８８１０号公報JP 2013-108810 A

原子力プラントの安全性を向上するため、重大事故等の発生時に原子炉ウェルの水張りを行うことにより、格納容器と格納容器トップヘッドとを連結する格納容器フランジ部の過温破損を防止する方法が考案されている。   In order to improve the safety of nuclear power plants, there is a method to prevent overheating damage of the containment vessel flange part connecting the containment vessel and the containment vessel top head by filling the reactor well when a serious accident occurs. It has been devised.

しかしながら、特許文献１に記載の原子炉ウェル水位計及び特許文献２に記載の定検時水張り用水位計は、いずれも圧力容器上蓋及び格納容器トップヘッドが取り外された状態（定期検査時）での使用を想定しており、圧力容器上蓋及び格納容器トップヘッドが取り付けられた状態（プラント運転時）は使用できない。また、原子炉ウェルの内壁には金属ライナーが施工されており、サポート金具等の取り付けができないため、既設プラントにおいて原子炉ウェルの内部に水位計を設置することは困難である。従って、重大事故等の発生時に原子炉ウェルへの注水を行った場合、原子炉ウェル水位を監視できないという課題が生じる。   However, the reactor well water level meter described in Patent Document 1 and the water level meter for water filling during regular inspection described in Patent Document 2 are both in a state in which the pressure vessel top cover and the containment vessel top head are removed (during periodic inspection). The pressure vessel top lid and the containment vessel top head are attached (during plant operation) and cannot be used. In addition, since a metal liner is applied to the inner wall of the reactor well and support fittings cannot be attached, it is difficult to install a water level gauge inside the reactor well in an existing plant. Therefore, when water is injected into the reactor well when a serious accident occurs, there is a problem that the reactor well water level cannot be monitored.

本発明は、上記の課題に鑑みてなされたものであり、その目的は、プラント運転時に原子炉ウェルへの注水を行うとともに、原子炉ウェル水位を監視できる原子力プラントを提供することである。   The present invention has been made in view of the above problems, and an object thereof is to provide a nuclear power plant that can inject water into a reactor well and monitor the reactor well water level during plant operation.

上記課題を解決するために、本発明は、原子炉圧力容器と、前記原子炉圧力容器を格納する格納容器と、前記格納容器の上方に位置する原子炉ウェルと、前記原子炉ウェルの上部を閉塞するウェルカバーとを備えた原子力プラントにおいて、前記ウェルカバーに挿通して設けられ、前記原子炉ウェルに注水を行う注水ラインと、前記原子炉ウェルの床面に接続され、前記原子炉ウェルの水抜きを行うドレンラインと、前記ドレンラインに一端が接続された検出配管と、前記検出配管の他端に接続され、水頭圧によって前記原子炉ウェルの水位を計測する差圧式水位計とを備える。   In order to solve the above problems, the present invention provides a reactor pressure vessel, a containment vessel for storing the reactor pressure vessel, a reactor well positioned above the containment vessel, and an upper portion of the reactor well. In a nuclear power plant having a well cover to be closed, the reactor is inserted through the well cover, and is connected to a water injection line for injecting water into the reactor well, and a floor surface of the reactor well. A drain line for draining water, a detection pipe having one end connected to the drain line, and a differential pressure type water level gauge connected to the other end of the detection pipe and measuring the water level of the reactor well by water head pressure .

本発明によれば、プラント運転時に原子炉ウェルへの注水を行うとともに、原子炉ウェル水位を監視できる。   According to the present invention, water can be injected into the reactor well during plant operation, and the reactor well water level can be monitored.

本発明の第１の実施の形態に係る原子力プラントの概略構成図である。1 is a schematic configuration diagram of a nuclear power plant according to a first embodiment of the present invention. 本発明の第２の実施の形態に係る原子力プラントの概略構成図である。It is a schematic block diagram of the nuclear power plant which concerns on the 2nd Embodiment of this invention. 本発明の第２の実施の形態に係る原子力プラントが備える隔膜式水位計の構成図である。It is a block diagram of the diaphragm type water level meter with which the nuclear power plant which concerns on the 2nd Embodiment of this invention is provided. 本発明の第３の実施の形態に係る原子力プラントの概略構成図である。It is a schematic block diagram of the nuclear power plant which concerns on the 3rd Embodiment of this invention.

以下、本発明の実施の形態を、図面を参照して説明する。   Hereinafter, embodiments of the present invention will be described with reference to the drawings.

＜第１の実施の形態＞
図１は、本発明の第１の実施の形態に係る原子力プラントの概略構成図である。図１において、原子力プラント１００は、原子炉圧力容器（以下、圧力容器という）１を格納する格納容器２と、格納容器２の上方に位置する原子炉ウェル３と、原子炉ウェル３の隣に位置する機器仮置きプール４と、原子炉ウェル３を挟んで機器仮置きプール４の反対側に位置する使用済燃料プール５とを備えている。 <First Embodiment>
FIG. 1 is a schematic configuration diagram of a nuclear power plant according to a first embodiment of the present invention. In FIG. 1, a nuclear power plant 100 includes a containment vessel 2 for storing a reactor pressure vessel (hereinafter referred to as a pressure vessel) 1, a reactor well 3 positioned above the containment vessel 2, and a reactor well 3 next to the containment vessel 2. An equipment temporary storage pool 4 and a spent fuel pool 5 positioned on the opposite side of the equipment temporary storage pool 4 across the reactor well 3 are provided.

圧力容器１の上部には、圧力容器フランジ部１ａを介して圧力容器上蓋１ｂが取り付けられ、格納容器２の上部には、格納容器フランジ部２ａを介して格納容器トップヘッド２ｂが取り付けられ、原子炉ウェル３の上部はウェルカバー６によって閉塞されている。定期点検時は、圧力容器上蓋１ｂ、格納容器トップヘッド２ｂ及びウェルカバー６を取り外して圧力容器１及び原子炉ウェル３に水張りを行い、燃料交換等の作業を行う。なお、ウェルカバー６には原子炉ウェル注水ライン（以下、注水ラインという）１１が挿通して設けられており、プラント運転時も原子炉ウェル３への注水を行うことができる。   A pressure vessel upper lid 1b is attached to the upper portion of the pressure vessel 1 via a pressure vessel flange portion 1a, and a storage vessel top head 2b is attached to the upper portion of the containment vessel 2 via a containment vessel flange portion 2a. The upper part of the furnace well 3 is closed by a well cover 6. During the periodic inspection, the pressure vessel top lid 1b, the containment vessel top head 2b and the well cover 6 are removed, and the pressure vessel 1 and the reactor well 3 are filled with water, and work such as fuel replacement is performed. The well cover 6 is provided with a reactor well water injection line (hereinafter referred to as a water injection line) 11 inserted therethrough, so that water can be injected into the reactor well 3 even during plant operation.

機器仮置きプール４は、水密性の低いスロットプラグ７によって原子炉ウェル３と仕切られており、原子炉ウェル３への注水時にウェル堰１０を越えた水が機器仮置きプール４に流出する。一方、使用済燃料プール５は、水密性の低いスロットプラグ８及び水密性の高いプールゲート９によって原子炉ウェル３と仕切られており、また、使用済燃料プール５にはプラント通常運転時も水が張られているため、原子炉ウェル３への注水時に原子炉ウェル３から使用済燃料プール５に水が流出することはない。   The equipment temporary storage pool 4 is partitioned from the reactor well 3 by a slot plug 7 having low water tightness, and water that has passed over the well weir 10 flows out to the equipment temporary storage pool 4 when water is injected into the reactor well 3. On the other hand, the spent fuel pool 5 is partitioned from the nuclear reactor well 3 by a slot plug 8 having a low water tightness and a pool gate 9 having a high water tightness, and the spent fuel pool 5 has water during normal plant operation. Therefore, water does not flow out from the reactor well 3 to the spent fuel pool 5 when water is injected into the reactor well 3.

原子炉ウェル３の床面には、原子炉ウェル３の水抜きを行う原子炉ウェルドレンライン（以下、ドレンラインという）１２が接続され、ドレンライン１２の途中にはドレンライン１２を閉止する原子炉ウェルドレンライン止め弁（以下、ドレンライン止め弁という）１３が設けられている。これにより、原子炉ウェル３の水張り時はドレンライン止め弁１３まで満水状態となる。ドレンライン１２のドレンライン止め弁１３上流側には検出配管１４の一端が接続されており、検出配管１４の他端は差圧式水位計２０に接続されている。検出配管１４は、原子炉ウェル３の水抜き時にドレンライン１２からスラッジが混入して閉塞することを防止するため、ドレンライン１２から差圧式水位計２０に向かって上り勾配を有するように設けられている。検出配管１４の途中には検出元弁１５が設けられており、差圧式水位計２０は、原子炉ウェル注水時に検出元弁１５を開弁した状態で、水頭圧によって原子炉ウェル水位を計測することができる。   A reactor well drain line (hereinafter referred to as a drain line) 12 for draining the reactor well 3 is connected to the floor of the reactor well 3, and an atom that closes the drain line 12 in the middle of the drain line 12. A furnace well drain line stop valve (hereinafter referred to as a drain line stop valve) 13 is provided. As a result, when the reactor well 3 is filled with water, the drain line stop valve 13 is fully filled. One end of a detection pipe 14 is connected to the drain line 12 upstream of the drain line stop valve 13, and the other end of the detection pipe 14 is connected to a differential pressure type water level gauge 20. The detection pipe 14 is provided so as to have an upward gradient from the drain line 12 toward the differential pressure type water level gauge 20 in order to prevent sludge from being mixed and blocked from the drain line 12 when the reactor well 3 is drained. ing. A detection source valve 15 is provided in the middle of the detection pipe 14, and the differential pressure type water level meter 20 measures the reactor well water level by the water head pressure in a state where the detection source valve 15 is opened when the reactor well is injected. be able to.

本実施の形態に係る原子力プラント３００では、重大事故等の発生時にドレンライン止め弁１３を閉弁して注水ライン１１から原子炉ウェル３へ注水を行う。その間、検出元弁１５を開弁して差圧式水位計２０を用いて原子炉ウェル水位を監視し、原子炉ウェル水位を格納容器フランジ部２ａより高い水位に保つ。これにより、格納容器フランジ部２ａが冠水して冷却されるため、格納容器フランジ部２ａの過温破損を防止することができる。   In the nuclear power plant 300 according to the present embodiment, the drain line stop valve 13 is closed and water is injected from the water injection line 11 to the reactor well 3 when a serious accident or the like occurs. Meanwhile, the detection source valve 15 is opened and the reactor well water level is monitored using the differential pressure type water level gauge 20, and the reactor well water level is kept higher than the containment flange portion 2a. Thereby, since the containment vessel flange part 2a is flooded and cooled, the overheat damage of the containment vessel flange part 2a can be prevented.

なお、本実施の形態においては、原子炉ウェル水が格納容器トップヘッド２ｂから伝わる熱によって膨張し、また、検出配管１４を水抜き待機とすることで原子炉ウェル３への注水時に検出配管１４内に空気が残留することにより、差圧式水位計２０による原子炉ウェル水位の計測精度の低下が懸念される。しかし、格納容器フランジ部２ａの冷却を目的として原子炉ウェル３の水張りを行う際は、下記の理由により高い計測精度は要求されないため、計測精度の低下は問題とならない。   In the present embodiment, the reactor well water expands due to the heat transmitted from the containment vessel top head 2b, and the detection pipe 14 is filled with water into the reactor well 3 by placing the detection pipe 14 in a standby state for draining water. If air remains in the inside, there is a concern that the measurement accuracy of the reactor well water level by the differential pressure type water level gauge 20 may be lowered. However, when the reactor well 3 is filled with water for the purpose of cooling the containment vessel flange portion 2a, high measurement accuracy is not required for the following reasons, so that a decrease in measurement accuracy is not a problem.

（理由１）少なくとも原子炉ウェル水位が格納容器フランジ部２ａより高いことを検知できれば、格納容器フランジ部２ａの冠水状態を維持できる。   (Reason 1) If it can be detected that at least the reactor well water level is higher than the containment vessel flange portion 2a, the flooded state of the containment vessel flange portion 2a can be maintained.

（理由２）原子炉ウェル３に注水を行い、原子炉ウェル水位が格納容器フランジ部２ａより高く位置するウェル堰１０の高さに達すると、それ以降、原子炉ウェル３の水はウェル堰１０を越えて機器仮置きプール４に流出し、機器仮置きプール４に設けられたドレンライン（図示せず）を介して排出されるため、原子炉ウェル水位は上昇しなくなる。従って、少なくとも原子炉ウェル３への注水時に原子炉ウェル水位が上昇しなくなったことを検知できれば、格納容器フランジ部２ａの冠水状態を維持できる。   (Reason 2) When water is poured into the reactor well 3 and the water level of the reactor well reaches the height of the well weir 10 positioned higher than the containment flange portion 2a, the water in the reactor well 3 thereafter flows into the well weir 10 Overflowing into the equipment temporary storage pool 4 and discharged through a drain line (not shown) provided in the equipment temporary storage pool 4, the reactor well water level does not rise. Therefore, if it can be detected that the reactor well water level has not risen at least when water is injected into the reactor well 3, the flooded state of the containment vessel flange portion 2a can be maintained.

上記のように構成した本実施の形態においては、圧力容器１及び格納容器２がそれぞれ圧力容器上蓋１ｂ及び格納容器トップヘッド２ｂによって封止され、かつ原子炉ウェル３の上部がウェルカバー６で閉塞されているプラント運転時に、原子炉ウェル注水ライン１１を介して原子炉ウェル３に注水を行うとともに、原子炉ウェルドレンライン１２に設けられた差圧式水位計２０によって原子炉ウェル水位を監視することができる。これにより、重大事故等の発生時に格納容器フランジ部２ａを冠水させて冷却することが可能となり、格納容器フランジ部２ａの過温破損を防止できる。また、差圧式水位計２０がドレンライン１２に接続されるため、既存プラントへの差圧式水位計２０の取り付けが容易である。   In the present embodiment configured as described above, the pressure vessel 1 and the containment vessel 2 are sealed by the pressure vessel upper lid 1b and the containment vessel top head 2b, respectively, and the upper portion of the reactor well 3 is closed by the well cover 6. During the operation of the plant, water is injected into the reactor well 3 through the reactor well injection line 11, and the reactor well water level is monitored by the differential pressure type water level gauge 20 provided in the reactor well drain line 12. Can do. As a result, the containment flange portion 2a can be submerged and cooled when a serious accident or the like occurs, and overheating damage to the containment vessel flange portion 2a can be prevented. Moreover, since the differential pressure type water level gauge 20 is connected to the drain line 12, it is easy to attach the differential pressure type water level gauge 20 to an existing plant.

＜第２の実施の形態＞
図２は、本発明の第２の実施の形態に係る原子力プラントの概略構成図である。図２において、第１の実施の形態と同一の構成については同一の符号を付し、説明は省略する。 <Second Embodiment>
FIG. 2 is a schematic configuration diagram of a nuclear power plant according to the second embodiment of the present invention. In FIG. 2, the same components as those in the first embodiment are denoted by the same reference numerals, and description thereof is omitted.

本実施の形態に係る原子力プラント２００は、第１の実施の形態における差圧式水位計２０に代えて隔膜式水位計３０を備え、更に、検出配管１４に接続された洗浄用ライン４０と、洗浄用ライン４０の途中に設けられた洗浄用ライン開閉弁４１とを備えている。原子炉ウェルドレンライン止め弁１３及び検出元弁１５を開弁するとともに、洗浄用ライン開閉弁４１を開弁して洗浄用ライン４０から洗浄水を供給することにより、検出配管１４を洗浄することができる。これにより、検出配管１４に混入したスラッジが除去され、隔膜式水位計３０による原子炉ウェル水位の計測精度の低下が抑制される。   The nuclear power plant 200 according to the present embodiment includes a diaphragm type water level gauge 30 instead of the differential pressure type water level gauge 20 in the first embodiment, and further includes a cleaning line 40 connected to the detection pipe 14, and a cleaning A cleaning line opening / closing valve 41 provided in the middle of the cleaning line 40 is provided. The detection pipe 14 is cleaned by opening the reactor well drain line stop valve 13 and the detection source valve 15 and opening the cleaning line opening / closing valve 41 and supplying cleaning water from the cleaning line 40. Can do. Thereby, the sludge mixed in the detection pipe 14 is removed, and a decrease in the measurement accuracy of the reactor well water level by the diaphragm type water level gauge 30 is suppressed.

図３は、隔膜式水位計３０の構成図である。図３において、隔膜式水位計３０は、圧力計３１と、圧力計３１に接続された圧力計配管３２ａ，３２ｂと、圧力計配管３２ａ，３２ｂのそれぞれに接続された隔膜３３ａ，３３ｂとを備えている。圧力計配管３２ａ，３２ｂ内には、圧力媒体として非圧縮性特殊液が充填されている。圧力計３１は、隔膜３３ａ及び圧力計配管３２ａを介して伝達される検出配管１４の水圧と隔膜３３ｂ及び圧力計配管３２ｂを介して伝達される大気圧との差圧に基づいて原子炉ウェル水位を計測する。   FIG. 3 is a configuration diagram of the diaphragm type water level gauge 30. In FIG. 3, the diaphragm type water level gauge 30 includes a pressure gauge 31, pressure gauge pipes 32a and 32b connected to the pressure gauge 31, and diaphragms 33a and 33b connected to the pressure gauge pipes 32a and 32b, respectively. ing. The pressure gauge pipes 32a and 32b are filled with an incompressible special liquid as a pressure medium. The pressure gauge 31 is a reactor well water level based on the differential pressure between the water pressure of the detection pipe 14 transmitted through the diaphragm 33a and the pressure gauge pipe 32a and the atmospheric pressure transmitted through the diaphragm 33b and the pressure gauge pipe 32b. Measure.

上記のように構成した本実施の形態においても、第１の実施の形態と同様の効果が得られる。さらに、原子炉ウェル水位を計測する差圧式水位計を隔膜式水位計３０で構成し、隔膜３３ａと圧力計３１との間が非圧縮性特殊液で充填された圧力計配管３２ａで接続したことにより、ドレンライン１２と隔膜式水位計３０とを接続する検出配管１４が短縮される。これにより、検出配管１４内の残留空気が減少し、隔膜式水位計３０による原子炉ウェル水位の計測精度の低下が抑制される。   In the present embodiment configured as described above, the same effects as those of the first embodiment can be obtained. Further, the differential pressure type water level gauge for measuring the reactor well water level is constituted by the diaphragm type water level gauge 30, and the diaphragm 33a and the pressure gauge 31 are connected by a pressure gauge pipe 32a filled with an incompressible special liquid. Thus, the detection pipe 14 connecting the drain line 12 and the diaphragm type water level gauge 30 is shortened. As a result, the residual air in the detection pipe 14 is reduced, and a decrease in the measurement accuracy of the reactor well water level by the diaphragm type water level gauge 30 is suppressed.

＜第３の実施の形態＞
図４は、本発明の第３の実施の形態に係る原子力プラントの概略構成図である。図４において、第１の実施の形態と同一の構成については同一の符号を付し、説明は省略する。なお、図４は、原子炉ウェル３の水張りが行われる前のプラント通常運転時の状態を示している。 <Third Embodiment>
FIG. 4 is a schematic configuration diagram of a nuclear power plant according to the third embodiment of the present invention. In FIG. 4, the same components as those in the first embodiment are denoted by the same reference numerals, and description thereof is omitted. FIG. 4 shows a state during normal plant operation before the reactor well 3 is filled with water.

本実施の形態に係る原子力プラント３００は、検出配管１４に接続された純水供給ライン（水張りライン）５０を備えており、プラント通常運転時に水張りライン５０を介してドレンライン１２の所定の水位Ｌまで水張りを行うとともに、差圧式水位計２０を用いてドレンライン１２の水位を監視し、蒸発等によりドレンライン１２の水位が所定の水位Ｌより低下したときは水張りライン５０から注水することにより、検出配管１４を満水状態に維持する。なお、所定の水位Ｌは、検出配管１４との接続点よりも上流側に位置するのであれば特に限定されない。   The nuclear power plant 300 according to the present embodiment includes a pure water supply line (water filling line) 50 connected to the detection pipe 14, and a predetermined water level L of the drain line 12 through the water filling line 50 during normal plant operation. The water level of the drain line 12 is monitored using the differential pressure type water level gauge 20, and when the water level of the drain line 12 falls below a predetermined water level L due to evaporation or the like, water is poured from the water filling line 50, The detection pipe 14 is kept full. The predetermined water level L is not particularly limited as long as it is located upstream of the connection point with the detection pipe 14.

上記のように構成した本実施の形態においても、第１の実施の形態と同様の効果が得られる。さらに、検出配管１４を満水待機させることにより、検出配管１４内の残留空気が排除され、差圧式水位計２０による原子炉ウェル水位の計測精度の低下が抑制される。   In the present embodiment configured as described above, the same effects as those of the first embodiment can be obtained. Further, by making the detection pipe 14 stand by for full water, residual air in the detection pipe 14 is eliminated, and a decrease in the measurement accuracy of the reactor well water level by the differential pressure type water level gauge 20 is suppressed.

＜その他の実施の形態＞
以上、本発明を実施の形態に基づいて説明したが、本発明は上記の実施の形態に限定されるものではない。例えば、図１に示した第１の実施の形態において、検出配管１４に図２に示した洗浄用ライン４０を接続しても良く、また、図２に示した第２の実施の形態において、洗浄用ライン４０を省略しても良い。あるいは、図４に示した第３の実施の形態において、差圧式水位計２０を図２に示した隔膜式水位計３０に置き換えても良い。 <Other embodiments>
While the present invention has been described based on the embodiments, the present invention is not limited to the above embodiments. For example, in the first embodiment shown in FIG. 1, the cleaning line 40 shown in FIG. 2 may be connected to the detection pipe 14. In the second embodiment shown in FIG. 2, The cleaning line 40 may be omitted. Alternatively, in the third embodiment shown in FIG. 4, the differential pressure type water level gauge 20 may be replaced with the diaphragm type water level gauge 30 shown in FIG.

１ 原子炉圧力容器
１ａ 圧力容器フランジ部
１ｂ 圧力容器上蓋
２ 格納容器
２ａ 格納容器フランジ部
２ｂ 格納容器トップヘッド
３ 原子炉ウェル
４ 機器仮置きプール
５ 使用済燃料プール
６ ウェルカバー
７，８ スロットプラグ
９ プールゲート
１０ ウェル堰
１１ 原子炉ウェル注水ライン
１２ 原子炉ウェルドレンライン
１３ 原子炉ウェルドレンライン止め弁
１４ 検出配管
１５ 検出元弁
２０ 差圧式水位計
３０ 隔膜式水位計
３１ 圧力計
３２ａ，３２ｂ 圧力計配管
３３ａ，３３ｂ 隔膜
４０ 洗浄用ライン
４１ 洗浄用ライン開閉弁
５０ 純水供給ライン（水張りライン）
１００，２００，３００ 原子力プラント DESCRIPTION OF SYMBOLS 1 Reactor pressure vessel 1a Pressure vessel flange part 1b Pressure vessel upper cover 2 Containment vessel 2a Containment vessel flange part 2b Containment vessel top head 3 Reactor well 4 Equipment temporary storage pool 5 Spent fuel pool 6 Well cover 7, 8 Slot plug 9 Pool gate 10 Well weir 11 Reactor well water injection line 12 Reactor well drain line 13 Reactor well drain line stop valve 14 Detection pipe 15 Detection source valve 20 Differential pressure type water level gauge 30 Diaphragm type water level gauge 31 Pressure gauge 32a, 32b Pressure gauge Piping 33a, 33b Diaphragm 40 Cleaning line 41 Cleaning line on-off valve 50 Pure water supply line (water filling line)
100, 200, 300 Nuclear power plant

Claims (5)

原子炉圧力容器と、
前記原子炉圧力容器を格納する格納容器と、
前記格納容器の上方に位置する原子炉ウェルと、
前記格納容器のフランジ部より高く位置するウェル堰によって前記原子炉ウェルと隔てられた機器仮置きプールと、
前記原子炉ウェルの上部を閉塞するウェルカバーとを備えた原子力プラントにおいて、
前記ウェルカバーに挿通して設けられ、前記原子炉ウェルに注水を行う注水ラインと、
前記原子炉ウェルの床面に接続され、前記原子炉ウェルの水抜きを行うドレンラインと、
前記ドレンラインに一端が接続された検出配管と、
前記検出配管の他端に接続され、水頭圧によって前記原子炉ウェルの水位を計測する差圧式水位計と
を備え、
前記注水ラインを介して前記原子炉ウェルに注水を行う時に前記差圧式水位計で計測した前記原子炉ウェルの水位が上昇しなくなったことを検知することにより前記フランジ部の冠水状態を維持できるように構成されたことを特徴とする原子力プラント。 A reactor pressure vessel;
A containment vessel for housing the reactor pressure vessel;
A reactor well located above the containment vessel;
An equipment temporary storage pool separated from the reactor well by a well weir positioned higher than the flange portion of the containment vessel;
In a nuclear power plant with a well cover that closes the top of the reactor well,
A water injection line that is inserted through the well cover and injects water into the reactor well; and
A drain line connected to the floor of the reactor well for draining the reactor well;
A detection pipe having one end connected to the drain line;
A differential pressure type water level meter connected to the other end of the detection pipe and measuring the water level of the reactor well by water head pressure ,
It is possible to maintain the submerged state of the flange portion by detecting that the water level of the reactor well measured by the differential pressure type water level gauge does not rise when water is injected into the reactor well through the water injection line. nuclear power plant, characterized in that configured. 請求項１に記載の原子力プラントにおいて、
前記検出配管は、前記ドレンラインから前記差圧式水位計に向かって上り勾配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,
The nuclear power plant, wherein the detection pipe has an upward gradient from the drain line toward the differential pressure type water level gauge. 請求項１又は２に記載の原子力プラントにおいて、
前記差圧式水位計は、隔膜式水位計で構成されてい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 2,
The nuclear power plant, wherein the differential pressure type water level meter is constituted by a diaphragm type water level meter. 請求項１乃至３のいずれか１項に記載の原子力プラントにおいて、
前記検出配管に接続された水張りラインを更に備え、
プラント運転中に前記水張りラインを介して前記ドレンラインの所定の水位まで注水し、前記検出配管を満水待機させることを特徴とする原子力プラント。 In the nuclear power plant according to any one of claims 1 to 3,
A water filling line connected to the detection pipe;
A nuclear power plant that injects water to a predetermined water level of the drain line through the water filling line during plant operation, and makes the detection pipe wait for full water. 請求項１乃至３のいずれか１項に記載の原子力プラントにおいて、
前記検出配管に接続された洗浄用ラインを更に備えたことを特徴とする原子力プラント。 In the nuclear power plant according to any one of claims 1 to 3,
A nuclear power plant further comprising a cleaning line connected to the detection pipe.
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