JPH06130174A - Emergency reactor core cooling water injecting system for light water reactor - Google Patents
Emergency reactor core cooling water injecting system for light water reactorInfo
- Publication number
- JPH06130174A JPH06130174A JP4283315A JP28331592A JPH06130174A JP H06130174 A JPH06130174 A JP H06130174A JP 4283315 A JP4283315 A JP 4283315A JP 28331592 A JP28331592 A JP 28331592A JP H06130174 A JPH06130174 A JP H06130174A
- Authority
- JP
- Japan
- Prior art keywords
- tank
- valve
- reactor
- cooling water
- water
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Withdrawn
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【0001】[0001]
【産業上の利用分野】本発明は、軽水炉の非常用炉心冷
却水注入装置に係り、特に、一次冷却水の水位が低下し
た際に、受動的に作動して冷却水を原子炉内に注入して
安全性を確保する技術に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an emergency core cooling water injection device for a light water reactor, and in particular, when the water level of the primary cooling water is lowered, the cooling water is passively operated to inject the cooling water into the reactor. It is related to the technology for ensuring safety.
【0002】[0002]
【従来の技術】非常用炉心冷却系設備は、一次冷却水喪
失事故が発生した時に、一次冷却水を原子炉圧力容器内
に注入して炉心の冠水状態を保持するものであり、蓄
圧注入系、高圧注入系、低圧注入系、自動減圧系
等がある。2. Description of the Related Art Emergency core cooling system equipment is used to maintain the submerged state of the core by injecting primary cooling water into the reactor pressure vessel when a primary cooling water loss accident occurs. , High pressure injection system, low pressure injection system, automatic decompression system, etc.
【0003】これらの設備では、原子炉圧力容器内の水
位の異常低下を水位計測装置により検出して電気信号を
出力させ、この電気信号により電気または空気圧等の動
力を供給し、弁を開放作動させて、非常用冷却水タンク
から冷却水(またはほう酸水)を原子炉圧力容器内に注
入するようにしている。したがって、非常時には、信号
伝送のための装置や動力によって作動する装置と、非常
用炉心冷却系を確実に作動させるために信頼性の高い動
力源とを確保することが必要である。In these facilities, an abnormal drop in the water level in the reactor pressure vessel is detected by a water level measuring device, an electric signal is output, and power such as electricity or pneumatic pressure is supplied by this electric signal to open the valve. The cooling water (or boric acid water) is injected into the reactor pressure vessel from the emergency cooling water tank. Therefore, in an emergency, it is necessary to secure a device for signal transmission and a device that operates by power, and a reliable power source for reliably operating the emergency core cooling system.
【0004】近年、原子炉システムの簡素化をねらいと
して、受動的安全システムを大幅に取り入れた新しい思
想に基づく原子炉の開発が要望されている。これらの原
子炉に用いられる受動的安全システムは、外部からのエ
ネルギあるいは信号、操作なしに、それ自体の有するメ
カニズムによって安全機能の達成を確保しようとしてい
る。In recent years, with the aim of simplifying the reactor system, there has been a demand for the development of a reactor based on a new idea that largely incorporates a passive safety system. The passive safety systems used in these reactors seek to ensure the achievement of safety functions by their own mechanism without external energy or signals or manipulation.
【0005】受動的安全システムに関連する技術とし
て、特開昭62−108192号公報「軽水冷却型原子
炉」が提案されている。その技術の概略を説明すると、
原子炉圧力容器の上方位置に、非常用給水系の給水タン
クを連設しておくとともに、非常用給水系の途中にポン
プの吐出圧力低下時に管路を開放する制御弁を配設し
て、炉心を冠水状態にしている一次冷却水またはほう酸
水の一部をポンプで吸引し続けるようになし、ポンプの
吐出圧力を直接制御弁に伝送して非常用給水系の管路を
閉じておき、原子炉圧力容器の水位低下により気体の吸
引現象が生じてポンプの吐出圧力が低下した場合に、制
御弁が受動的に管路を開放することによって、冷却水や
ほう酸水の供給を自動的に開始して炉心の冠水状態を維
持するようにしたものである。As a technique related to a passive safety system, Japanese Patent Application Laid-Open No. 62-108192, "Light Water Cooled Reactor" has been proposed. To explain the outline of the technology,
In the upper position of the reactor pressure vessel, a water supply tank for the emergency water supply system is connected in series, and a control valve that opens the pipeline when the discharge pressure of the pump drops when the emergency water supply system is installed, A part of the primary cooling water or boric acid water that is flooding the core is kept sucked by the pump, the discharge pressure of the pump is directly transmitted to the control valve, and the emergency water supply system pipeline is closed, When gas suction phenomenon occurs due to the water level drop in the reactor pressure vessel and the pump discharge pressure drops, the control valve passively opens the pipeline to automatically supply cooling water and boric acid water. It was started to maintain the flooded state of the core.
【0006】そして、この技術によれば、原子炉水位の
低下事故あるいはポンプ停止時に、受動的に給水系が作
動して給水がなされることによって、炉心の冠水状態を
保持することができるようになる。According to this technique, when the reactor water level is lowered or the pump is stopped, the submerged state of the reactor core can be maintained by passively activating the submersible system to supply water. Become.
【0007】[0007]
【発明が解決しようとする課題】しかし、ポンプを作動
させるためには、原子炉運転中における電動モータ等の
駆動源の停電事故の発生を防止する必要があり、また、
連続的に回転し続ける部分にあっては、安全性を確保す
るためにそのメンテナンスを考慮しなければならない等
の解決すべき課題が残されている。However, in order to operate the pump, it is necessary to prevent the occurrence of a power failure accident of the drive source such as the electric motor during the operation of the reactor.
In the part that continuously rotates, there are still problems to be solved, such as maintenance of the part in order to ensure safety.
【0008】本発明は、かかる事情に鑑みてなされたも
ので、冷却水供給系を遮断している部分を、自然力のみ
によって受動的に開放して給水を行なうことにより、原
子炉の安全性を確保することを目的としている。The present invention has been made in view of the above circumstances, and the safety of a nuclear reactor is ensured by passively opening the part that shuts off the cooling water supply system only by natural force to supply water. The purpose is to secure.
【0009】[0009]
【課題を解決するための手段】上記課題を解決するため
のいくつかの手段を提案している。第1の手段は、原子
炉圧力容器の上方位置に配される給水タンクと、原子炉
圧力容器における液相部分及び気相部分と給水タンクに
おける液相部分及び気相部分との間に配されこれらを接
続する給水用配管及び均圧用配管と、該給水用配管及び
均圧配管に介在状態に配され管路の開閉を行なう制御弁
と、該制御弁に接続されその開閉作動を行なう弁作動手
段とを具備し、該弁作動手段は、原子炉圧力容器におけ
る液相部分及び気相部分に接続状態の昇降タンクと、該
昇降タンクを昇降可能に支持し荷重減少時に昇降タンク
を上方移動させる荷重支持手段と、昇降タンクと制御弁
との間に介在状態に配され昇降タンクの上方移動時に制
御弁を開放作動させる弁駆動部とから構成される軽水炉
の非常用炉心冷却水注入装置としている。第2の手段
は、第1の手段に、弁作動手段における荷重支持手段
に、昇降タンクの重量を受ける弾発部材が配される構成
を付加した軽水炉の非常用炉心冷却水注入装置としてい
る。第3の手段は、第1または第2の手段に、弁作動手
段における弁駆動部に、制御弁を開放方向に駆動するリ
ンク機構が配される構成を付加した軽水炉の非常用炉心
冷却水注入装置としている。第4の手段は、第3の手段
に、リンク機構と制御弁との結合部分に、開放方向への
移動を遅らせる係合状態の長穴及びピンが配される構成
を付加した軽水炉の非常用炉心冷却水注入装置としてい
る。[Means for Solving the Problems] Several means for solving the above problems have been proposed. The first means is arranged between a water tank arranged above the reactor pressure vessel, a liquid phase portion and a gas phase portion of the reactor pressure vessel, and a liquid phase portion and a gas phase portion of the water tank. A water supply pipe and a pressure equalizing pipe for connecting them, a control valve arranged in the water supply pipe and the pressure equalizing pipe for opening and closing a pipeline, and a valve operation connected to the control valve for opening and closing the pipe. The valve actuating means includes an elevating tank connected to a liquid phase portion and a gas phase portion of the reactor pressure vessel, and the elevating tank is supported so as to be vertically movable and moves the elevating tank upward when the load decreases. An emergency core cooling water injection device for a light water reactor, comprising load supporting means and a valve drive unit interposed between the lifting tank and the control valve to open the control valve when the lifting tank moves upward. . The second means is an emergency core cooling water injection device for a light water reactor, in which the load supporting means in the valve actuating means and the elastic member for receiving the weight of the lifting tank are arranged in addition to the first means. A third means is an emergency core cooling water injection for a light water reactor, in which the first or second means has a structure in which a valve mechanism in the valve actuating means is provided with a link mechanism for driving the control valve in the opening direction. The device. A fourth means is an emergency for a light water reactor, in which a structure in which an elongated hole and a pin in an engaged state for delaying the movement in the opening direction are arranged is provided at the connecting portion of the link mechanism and the control valve in addition to the third means. It is used as a core cooling water injection device.
【0010】[0010]
【作用】第1の手段にあっては、原子炉圧力容器及び昇
降タンクにおける気相部分及び液相部分が連通した状態
であるために、原子炉圧力容器及び昇降タンクにおける
内部水位が同レベルとなる。原子炉圧力容器の水位が通
常の状態である場合には、昇降タンクの水量の多い状態
が維持されてその重量により昇降タンクが下がった状態
を継続し、制御弁による非常用給水系の管路の閉塞が継
続して行なわれる。原子炉圧力容器内の水位が低下した
場合には、昇降タンクの内部水位が同レベルまで下がる
ことにより重量が減少して昇降タンクが上昇し、弁駆動
部による制御弁の開放が行なわれて、原子炉圧力容器及
び給水タンクの液相部分及び気相部分が連通した状態と
なり、液相部分の水頭差によって給水タンクから原子炉
圧力容器内への給水がなされて、炉心の冠水状態の保持
が行なわれる。第2の手段にあっては、第1の手段によ
る作用に付加して、弾発部材の弾発力による上方への駆
動力が昇降タンクの重量を上回ると、昇降タンクが上昇
し始めて、制御弁の開放が行なわれる。第3の手段にあ
っては、第1の手段及び第2の手段による作用に付加し
て、弁作動手段から弁棒への駆動力の伝達が、リンク機
構を介して行なわれる。第4の手段にあっては、第3の
手段による作用に付加して、リンク機構が移動を開始し
た場合に、長穴及びピンの結合部分で力の伝達が遅れ、
原子炉圧力容器の水位が管理限界を越えると、原子炉圧
力容器への給水が行なわれる。In the first means, since the gas phase portion and the liquid phase portion of the reactor pressure vessel and the elevating tank are in communication with each other, the internal water levels in the reactor pressure vessel and the elevating tank are at the same level. Become. When the water level in the reactor pressure vessel is in a normal state, a large amount of water in the lift tank is maintained, and the lift tank continues to be lowered due to its weight, and the control valve provides an emergency water supply system pipeline. Is continuously closed. When the water level in the reactor pressure vessel drops, the internal water level of the lift tank drops to the same level, the weight decreases and the lift tank rises, and the control valve is opened by the valve drive unit. The liquid phase part and the gas phase part of the reactor pressure vessel and the water supply tank are in communication with each other, water is supplied from the water tank to the reactor pressure vessel due to the head difference of the liquid phase part, and the flooded state of the core is maintained. Done. In the second means, in addition to the operation of the first means, when the upward driving force by the elastic force of the elastic member exceeds the weight of the elevating tank, the elevating tank begins to rise and control is performed. The valve is opened. In the third means, in addition to the actions of the first means and the second means, the driving force is transmitted from the valve operating means to the valve rod via the link mechanism. In the fourth means, in addition to the action of the third means, when the link mechanism starts moving, the force transmission is delayed at the connecting portion of the slot and the pin,
When the water level in the reactor pressure vessel exceeds the control limit, water is supplied to the reactor pressure vessel.
【0011】[0011]
【実施例】以下、本発明に係る軽水炉の非常用炉心冷却
水注入装置の一実施例について、図1ないし図3に基づ
いて説明する。各図において、符号1は原子炉圧力容
器、2は炉心、3は一次系配管、11は給水タンク、1
2Aは給水用配管、12Bは均圧用配管、13A,13
Bは制御弁、14は弁作動手段、15は昇降タンク、1
6A,16Bは連通配管(サイホン管)、17は荷重支
持手段、18は弁駆動部、Aは液相部分、Bは気相部
分、Cは液相部分、Dは気相部分である。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of an emergency core cooling water injection system for a light water reactor according to the present invention will be described below with reference to FIGS. In each drawing, reference numeral 1 is a reactor pressure vessel, 2 is a reactor core, 3 is a primary system pipe, 11 is a water tank, and 1 is a water tank.
2A is a water supply pipe, 12B is a pressure equalizing pipe, 13A, 13
B is a control valve, 14 is a valve operating means, 15 is a lifting tank, 1
6A and 16B are communication pipes (siphon pipes), 17 is load supporting means, 18 is a valve drive unit, A is a liquid phase part, B is a gas phase part, C is a liquid phase part, and D is a gas phase part.
【0012】該一実施例における非常用炉心冷却水注入
装置にあっては、内部圧力に関係なく非常用冷却水を水
頭差を利用して原子炉圧力容器1の中に注水して、炉心
2の冠水状態を維持するものに適用している。In the emergency core cooling water injecting apparatus in the one embodiment, the emergency cooling water is injected into the reactor pressure vessel 1 by utilizing the head difference regardless of the internal pressure, and the core 2 It is applied to those that maintain the flooded condition of.
【0013】そして、非常用炉心冷却水注入装置は、図
1に示すように、原子炉格納容器5の外方でかつ上方位
置(高所)に配される給水タンク11と、原子炉圧力容
器1における液相部分A及び気相部分Bと給水タンク1
1における液相部分C及び気相部分Dとの間に接続状態
に配される給水用配管12A及び均圧用配管12Bと、
これら給水用配管12A及び均圧用配管12Bの途中に
介在状態に配され管路の開閉を行なうための制御弁13
A,13Bと、該制御弁13A,13Bに接続されその
その開閉作動を行なうための弁作動手段14とを具備し
ている。As shown in FIG. 1, the emergency core cooling water injection device includes a water supply tank 11 arranged outside the reactor containment vessel 5 and at an upper position (high place), and a reactor pressure vessel. 1. Liquid phase part A and gas phase part B and water tank 1
A water supply pipe 12A and a pressure equalizing pipe 12B arranged in a connected state between the liquid phase portion C and the gas phase portion D in FIG.
A control valve 13 arranged in the middle of the water supply pipe 12A and the pressure equalizing pipe 12B for opening and closing the pipeline.
A and 13B, and a valve operating means 14 connected to the control valves 13A and 13B for opening and closing the control valves 13A and 13B.
【0014】前記弁作動手段14は、図2に示すよう
に、原子炉圧力容器1の内部に形成される通常運転液位
H及び下限液位Lの高さ寸法Tに対応して例えばこれよ
りも大きな上下寸法を有する昇降タンク15と、該昇降
タンク15及び原子炉圧力容器1の内部間を上下の2箇
所で接続するための連通配管(サイホン管)16A,1
6Bと、昇降タンク15を昇降可能な状態に支持し昇降
タンク15の荷重減少時に昇降タンク15を上方移動さ
せる荷重支持手段17と、昇降タンク15と制御弁13
A,13Bとの間に接続状態に配されて昇降タンク15
の上方移動時に制御弁13A,13Bを開放作動させる
ための弁駆動部18とから構成される。As shown in FIG. 2, the valve operating means 14 corresponds to the height dimension T of the normal operating liquid level H and the lower limit liquid level L formed inside the reactor pressure vessel 1, for example And a communicating pipe (siphon pipe) 16A, 1 for connecting the lifting tank 15 having a large vertical dimension and the inside of the lifting tank 15 and the reactor pressure vessel 1 at two locations, an upper side and a lower side.
6B, load supporting means 17 for supporting the lifting tank 15 in a vertically movable state, and moving the lifting tank 15 upward when the load on the lifting tank 15 decreases, the lifting tank 15, and the control valve 13
A lift tank 15 is placed in a connected state between A and 13B.
And a valve drive section 18 for opening the control valves 13A and 13B when the control valve moves upward.
【0015】さらに詳しく説明すると、昇降タンク15
及び連通配管16A,16Bは、原子炉圧力容器1の内
部圧力が印加されるために、十分な耐圧性を有するもの
とすることが必要であるが、連通配管16A,16Bに
あっては、昇降タンク15の上下移動を妨げない程度の
変形性(撓み性)が付与される。そして、下方位置の連
通配管16Aは、原子炉圧力容器1の内部側の開口位置
が、液相部分Aの下限液位Lよりも下方となるように設
定され、上方位置の連通配管16Bは、その開口位置
が、通常運転液位Hの近傍または気相部分Bとなるよう
に設定される。また、下方位置の連通配管16Aは、昇
降タンク15の内底部近傍に開口位置が設定され、上方
位置の連通配管16Bは、昇降タンク15の内部上方に
開口位置が設定される。More specifically, the lifting tank 15
Since the internal pressure of the reactor pressure vessel 1 is applied to the communication pipes 16A and 16B, it is necessary that the communication pipes 16A and 16B have sufficient pressure resistance. Deformability (flexibility) is provided to such an extent that the vertical movement of the tank 15 is not hindered. The communication pipe 16A at the lower position is set such that the opening position on the inner side of the reactor pressure vessel 1 is below the lower limit liquid level L of the liquid phase portion A, and the communication pipe 16B at the upper position is The opening position is set near the normal operating liquid level H or in the gas phase portion B. Further, the communication pipe 16A at the lower position has an opening position near the inner bottom of the lifting tank 15, and the communication pipe 16B at the upper position has an opening position above the inside of the lifting tank 15.
【0016】前記荷重支持手段17は、図2に示すよう
に、昇降タンク15と支持構造物17aとの間に配され
昇降タンク15の重量を受けて荷重減少時に上方に移動
させるための弾発部材17bと、昇降タンク15の回り
に配され上下移動を許容するとともに水平方向の移動を
拘束して耐震性を付与するための昇降ガイド17cとを
有している。As shown in FIG. 2, the load supporting means 17 is disposed between the lifting tank 15 and the support structure 17a and receives the weight of the lifting tank 15 to move upward when the load is reduced. It has a member 17b and an elevating guide 17c which is arranged around the elevating tank 15 to allow vertical movement and restrain horizontal movement to impart seismic resistance.
【0017】前記弁駆動部18は、図2及び図3に示す
ように、昇降タンク15と制御弁13A,13Bの弁棒
13dとの間に接続状態に配されるリンク機構18a
と、該リンク機構18aと弁棒13dとの結合部分に配
される係合状態の長穴18b及びピン18cとを有し
て、昇降タンク15が下方に位置している場合に、弁棒
13dの上下方向の自由な移動を許容し、昇降タンク1
5が上方に移動した場合に、図3の鎖線で示すように、
リンク機構18a及びピン18cが弁棒13dを引き上
げて制御弁13A,13Bを開放状態とするように設定
される。As shown in FIGS. 2 and 3, the valve driving section 18 is a link mechanism 18a arranged in a connected state between the lifting tank 15 and the valve rods 13d of the control valves 13A and 13B.
And the elongated hole 18b and the pin 18c which are in an engaged state and which are arranged at the connecting portion between the link mechanism 18a and the valve rod 13d, and when the lifting tank 15 is located below, the valve rod 13d Allows free movement in the vertical direction of the
When 5 moves upward, as shown by the chain line in FIG.
The link mechanism 18a and the pin 18c are set so as to pull up the valve rod 13d to open the control valves 13A and 13B.
【0018】なお、制御弁13A,13Bは、図3に示
すように、弁箱13aの内部に弁座13b及び弁体13
cが配され、押えばね13eの弾発力によって弁棒13
dを押して弁座13bの閉塞状態を保持し、かつ、シー
ル部13fによって外部から弁室13gを隔離する構造
等とされる。そして、押えばね13eの弾発力は、原子
炉圧力容器1の通常の内部圧力印加時に、弁座13bの
閉塞状態を維持し得るものが適用される。As shown in FIG. 3, the control valves 13A and 13B have a valve seat 13b and a valve body 13 inside a valve box 13a.
c is arranged, and the valve rod 13 is pressed by the elastic force of the presser spring 13e.
The structure is such that the valve seat 13b is kept closed by pressing d and the valve chamber 13g is isolated from the outside by the seal portion 13f. The elastic force of the pressing spring 13e is such that the valve seat 13b can be kept closed when the normal internal pressure of the reactor pressure vessel 1 is applied.
【0019】このような非常用炉心冷却水注入装置にあ
っては、原子炉圧力容器1における液相部分A及び気相
部分Bに、連通配管16A,16Bを介して昇降タンク
15が接続されるために、昇降タンク15の中に、液相
部分Aの液位と同じ高さの液位が形成される。In such an emergency core cooling water injection device, the lifting tank 15 is connected to the liquid phase portion A and the vapor phase portion B of the reactor pressure vessel 1 via the communication pipes 16A and 16B. Therefore, a liquid level having the same height as the liquid level of the liquid phase portion A is formed in the lifting tank 15.
【0020】したがって、原子炉の通常運転時にあって
は、原子炉圧力容器1の液相部分Aが図2の通常運転液
位Hとなって、昇降タンク15の中に一次冷却水がほぼ
充満状態に送り込まれ、昇降タンク15の重量によって
荷重支持手段17の弾発部材17bが弾性変形した状態
となり、弁駆動部18のリンク機構18aが図3の実線
で示すように、下がった位置を維持する。この場合に
は、長穴18bの存在によって弁棒13dとリンク機構
18aとの間で力の伝達が行なわれない。Therefore, during normal operation of the reactor, the liquid phase portion A of the reactor pressure vessel 1 becomes the normal operation liquid level H in FIG. 2, and the lift tank 15 is almost filled with the primary cooling water. State, the elastic member 17b of the load supporting means 17 is elastically deformed by the weight of the lifting / lowering tank 15, and the link mechanism 18a of the valve drive unit 18 maintains the lowered position as shown by the solid line in FIG. To do. In this case, due to the existence of the elongated hole 18b, the force is not transmitted between the valve rod 13d and the link mechanism 18a.
【0021】一方、一次系配管3の破断に基づく漏洩等
によって、原子炉圧力容器1の液位が低下すると、これ
に連動して昇降タンク15における液相部分15aが低
下して、昇降タンク15の全体重量が減少するため、弾
発部材17bの弾発力によって昇降タンク15が平衡す
る位置まで若干上昇して停止する。昇降タンク15の上
方移動量が弁駆動部18の長穴18bの範囲内である場
合には、制御弁13A,13Bの弁棒13dの上方移動
が行なわれず、したがって制御弁13A,13Bが開放
されることはなく、給水タンク11や、給水タンク11
と制御弁13A,13Bとの間の給水用配管12A及び
均圧用配管12Bに、原子炉圧力容器1の内圧が印加さ
れることはない。On the other hand, when the liquid level in the reactor pressure vessel 1 is lowered due to a leak or the like caused by breakage of the primary system piping 3, the liquid phase portion 15a of the lift tank 15 is lowered in conjunction with this, and the lift tank 15 is lowered. Since the overall weight of the tank is reduced, the elastic force of the elastic member 17b causes the elevating tank 15 to slightly rise to a position where it is in equilibrium and then stop. When the amount of upward movement of the lift tank 15 is within the range of the elongated hole 18b of the valve drive unit 18, the upward movement of the valve rod 13d of the control valves 13A and 13B is not performed, so that the control valves 13A and 13B are opened. Water tank 11 and water tank 11
The internal pressure of the reactor pressure vessel 1 is not applied to the water supply pipe 12A and the pressure equalizing pipe 12B between the control valve 13A and the control valves 13A and 13B.
【0022】液相部分Aが下限液位Lまで低下するよう
な事態が生じると、昇降タンク15の総重量が著しく減
少して、弾発部材17bによって昇降タンク15が押し
上げられ、図3に鎖線で示すように、リンク機構18a
が上方に移動することによって、弁棒13dが強制的に
持ち上げられ、弁体13cが弁座13bから離間して、
給水用配管12A及び均圧用配管12Bの管路が開放さ
れる。When a situation occurs in which the liquid phase portion A drops to the lower limit liquid level L, the total weight of the lifting tank 15 is significantly reduced, and the lifting member 15b pushes the lifting tank 15 up, and the chain line in FIG. As shown in FIG.
Moves upward, the valve rod 13d is forcibly lifted, the valve body 13c is separated from the valve seat 13b, and
Pipe lines of the water supply pipe 12A and the pressure equalizing pipe 12B are opened.
【0023】給水用配管12A及び均圧用配管12Bに
よる管路が開放された場合には、原子炉圧力容器1にお
ける気相部分Bと給水タンク11における気相部分Dと
の圧力差がなくなり、二つの液相部分A,Cの高低差分
の圧力差によって、給水タンク11から原子炉圧力容器
1の内部にほう酸水等の非常用冷却水が順次注入され、
炉心2の冠水状態の保持が行なわれるものである。この
場合にあっては、原子炉圧力容器1の内部圧力の大きさ
に左右されることなく、非常用冷却水が注入される。When the pipelines for the water supply pipe 12A and the pressure equalizing pipe 12B are opened, the pressure difference between the gas phase portion B in the reactor pressure vessel 1 and the gas phase portion D in the water supply tank 11 disappears, and Due to the difference in pressure between the two liquid phase portions A and C, the emergency cooling water such as boric acid water is sequentially injected from the water supply tank 11 into the reactor pressure vessel 1,
The flooded state of the reactor core 2 is maintained. In this case, the emergency cooling water is injected regardless of the internal pressure of the reactor pressure vessel 1.
【0024】これらの非常時の給水にあっては、電気や
空気圧等の駆動源が使用されず、昇降タンク15の重量
減少、弾発力による上昇、リンク機構18aによる制御
弁13A,13Bの開放操作等、自然力によって受動的
に行なわれ、停電等の影響を受けることがない。In these emergency water supplies, a driving source such as electricity or air pressure is not used, the weight of the lifting tank 15 is reduced, the lifting force is raised, and the control valves 13A and 13B are opened by the link mechanism 18a. It is carried out passively by natural force such as operation, and is not affected by power failure.
【0025】〔他の実施態様〕本発明にあっては、実施
例に代えて次の技術を採用することができる。 a)一つの弁作動手段14における弁駆動部18のリン
ク機構18aを一部延長すること等によって、給水用配
管12A及び均圧用配管12Bの両制御弁13A,13
Bを作動させること。 b)弾発部材17bを板ばねや引っ張りばねとするこ
と。 c)昇降タンク15と支持構造物17aとの間にスナッ
バ等を配して、昇降タンク15の上下移動性や耐震性を
確保すること。[Other Embodiments] In the present invention, the following techniques can be adopted instead of the embodiments. a) By partially extending the link mechanism 18a of the valve drive unit 18 in one valve actuating means 14, both control valves 13A, 13 of the water supply pipe 12A and the pressure equalizing pipe 12B
Activate B. b) The elastic member 17b should be a leaf spring or a tension spring. c) A snubber or the like is provided between the lifting tank 15 and the support structure 17a to ensure vertical movement and earthquake resistance of the lifting tank 15.
【0026】[0026]
【発明の効果】請求項1に係る軽水炉の非常用炉心冷却
水注入装置にあっては、以下の効果を奏する。 (1) 原子炉圧力容器と給水タンクとの液相部分及び
気相部分を相互に接続する給水用配管及び均圧配管に介
在させられる制御弁と、その開閉作動を行なう弁作動手
段とを具備し、弁作動手段が、原子炉圧力容器における
液相部分及び気相部分に接続状態の昇降タンクと、昇降
タンクを昇降可能に支持する荷重支持手段と、昇降タン
クの上方移動時に制御弁を開放作動させる弁駆動部とか
ら構成されるものとすることにより、一次冷却水の水位
が低下した際に、受動的作動によって気相部分の均圧化
が図られて水頭差に基づいて冷却水を円滑に原子炉圧力
容器内部に注入して、炉心を冠水状態にして原子炉の安
全性を確保することができる。 (2) 非常時の給水にあっては、電気や空気圧等の駆
動源が使用されず、自然力によって受動的に行なわれ、
停電等の影響を受けることがない。 請求項2に係る軽水炉の非常用炉心冷却水注入装置にあ
っては、弁作動手段における荷重支持手段に、昇降タン
クの重量を受ける弾発部材が配される構成の採用によ
り、請求項1の注入装置に以下の効果が付加される。昇
降タンクの重量を弾発部材の弾発力で支持しておくこと
により、重量変化が生じた場合の検出を容易にし、か
つ、給水を確実に実施することができる。請求項3に係
る軽水炉の非常用炉心冷却水注入装置にあっては、弁作
動手段における弁駆動部に、制御弁を開放方向に駆動す
るリンク機構が配される構成の採用により、請求項1ま
たは請求項2の注入装置に以下の効果が付加される。弁
作動手段から制御弁への駆動力の伝達が、リンク機構を
介して行なわれることにより、接続距離及び方向の自由
性を向上させることができる。請求項4に係る軽水炉の
非常用炉心冷却水注入装置にあっては、リンク機構と制
御弁との結合部分に、開放方向への移動を遅らせる係合
状態の長穴及びピンが配される構成の採用により、請求
項3の注入装置に以下の効果が付加される。結合部分で
の力の伝達を遅らせることにより、原子炉圧力容器の水
位が管理限界を超えるまでの液位の設定を容易にし、必
要時に原子炉圧力容器への給水を速やかに実施すること
ができる。The emergency core cooling water injection device for a light water reactor according to the first aspect of the present invention has the following effects. (1) A control valve interposed in a water supply pipe and a pressure equalizing pipe for connecting a liquid phase portion and a gas phase portion of a reactor pressure vessel and a water supply tank to each other, and a valve operating means for opening and closing the control valve. Then, the valve operating means opens and closes the lifting tank connected to the liquid phase part and the gas phase part of the reactor pressure vessel, the load supporting means that supports the lifting tank so that it can move up and down, and opens the control valve when the lifting tank moves upward. By configuring the valve drive unit to operate, when the water level of the primary cooling water drops, the passive operation operates to equalize the pressure in the gas phase portion and to cool the cooling water based on the head difference. It is possible to smoothly inject the fuel into the reactor pressure vessel to bring the core into a flooded state and ensure the safety of the reactor. (2) In the case of emergency water supply, a drive source such as electricity or air pressure is not used, but it is performed passively by natural force,
Not affected by power outages. In the emergency core cooling water injection device for a light water reactor according to claim 2, the load supporting means of the valve actuating means is provided with the elastic member for receiving the weight of the lifting tank. The following effects are added to the injection device. By supporting the weight of the lifting tank by the elastic force of the elastic member, it is possible to easily detect a change in weight and reliably supply water. The emergency core cooling water injection device for a light water reactor according to claim 3 employs a configuration in which a link mechanism for driving the control valve in the opening direction is arranged in the valve drive portion of the valve actuation means. Alternatively, the following effects are added to the injection device of claim 2. By transmitting the driving force from the valve actuating means to the control valve via the link mechanism, it is possible to improve the freedom of connection distance and direction. In the emergency core cooling water injection device for a light water reactor according to claim 4, an elongated hole and a pin in an engaged state for delaying the movement in the opening direction are arranged at a connecting portion between the link mechanism and the control valve. By adopting, the following effects are added to the injection device of claim 3. By delaying the transmission of force at the joint, it is possible to easily set the liquid level until the water level of the reactor pressure vessel exceeds the control limit, and to quickly supply water to the reactor pressure vessel when necessary. .
【図1】本発明に係る軽水炉の非常用炉心冷却水注入装
置の一実施例を示す正断面図である。FIG. 1 is a front sectional view showing an embodiment of an emergency core cooling water injection device for a light water reactor according to the present invention.
【図2】図1に示す弁作動手段の部分の正断面図であ
る。FIG. 2 is a front sectional view of a portion of the valve actuating means shown in FIG.
【図3】図2に示す制御弁及び弁駆動部の正断面図であ
る。FIG. 3 is a front sectional view of a control valve and a valve drive section shown in FIG.
1 原子炉圧力容器 2 炉心 3 一次系配管 11 給水タンク 12A 給水用配管 12B 均圧用配管 13A,13B 制御弁 13a 弁箱 13b 弁座 13c 弁体 13d 弁棒 13e 押えばね 13f シール部 13g 弁室 14 弁作動手段 15 昇降タンク 15a 液相部分 16A,16B 連通配管(サイホン管) 17 荷重支持手段 17a 支持構造物 17b 弾発部材 17c 昇降ガイド 18 弁駆動部 18a リンク機構 18b 長穴 18c ピン A 液相部分 B 気相部分 C 液相部分 D 気相部分 1 Reactor Pressure Vessel 2 Core 3 Primary System Pipe 11 Water Supply Tank 12A Water Supply Pipe 12B Pressure Equalizing Pipe 13A, 13B Control Valve 13a Valve Box 13b Valve Seat 13c Valve Body 13d Valve Rod 13e Presser Spring 13f Seal Part 13g Valve Room 14 Valve Operating means 15 Lifting tank 15a Liquid phase portion 16A, 16B Communication piping (siphon pipe) 17 Load supporting means 17a Support structure 17b Elastic member 17c Lifting guide 18 Valve drive part 18a Link mechanism 18b Slot 18c Pin A Liquid phase portion B Gas phase part C Liquid phase part D Gas phase part
Claims (4)
水タンクと、原子炉圧力容器における液相部分及び気相
部分と給水タンクにおける液相部分及び気相部分との間
に配されこれらを接続する給水用配管及び均圧用配管
と、該給水用配管及び均圧配管に介在状態に配され管路
の開閉を行なう制御弁と、該制御弁に接続されその開閉
作動を行なう弁作動手段とを具備し、該弁作動手段は、
原子炉圧力容器における液相部分及び気相部分に接続状
態の昇降タンクと、該昇降タンクを昇降可能に支持し荷
重減少時に昇降タンクを上方移動させる荷重支持手段
と、昇降タンクと制御弁との間に介在状態に配され昇降
タンクの上方移動時に制御弁を開放作動させる弁駆動部
とから構成されることを特徴とする軽水炉の非常用炉心
冷却水注入装置。1. A feed water tank disposed above the reactor pressure vessel, and a liquid phase portion and a gas phase portion of the reactor pressure vessel and a liquid phase portion and a gas phase portion of the feed water tank, respectively. Water supply pipe and pressure equalizing pipe for connecting the control valve, a control valve disposed in the water supply pipe and the pressure equalizing pipe for opening and closing the pipeline, and a valve operating means connected to the control valve for opening and closing the pipe. And the valve actuating means comprises:
A lift tank connected to a liquid phase portion and a gas phase portion of a reactor pressure vessel, load supporting means for supporting the lift tank so that it can be moved up and down, and moving the lift tank upward when the load is reduced, a lift tank and a control valve. An emergency core cooling water injection device for a light water reactor, characterized in that it is arranged in an intervening state and is constituted by a valve drive section that opens the control valve when the lifting tank moves upward.
降タンクの重量を受ける弾発部材が配されることを特徴
とする請求項1記載の軽水炉の非常用炉心冷却水注入装
置。2. The emergency core cooling water injection device for a light water reactor according to claim 1, wherein the load supporting means of the valve actuating means is provided with an elastic member for receiving the weight of the lifting tank.
を開放方向に駆動するリンク機構が配されることを特徴
とする請求項1または2記載の軽水炉の非常用炉心冷却
水注入装置。3. The emergency core cooling water injection device for a light water reactor according to claim 1 or 2, wherein a link mechanism for driving the control valve in the opening direction is arranged in the valve driving portion of the valve actuating means.
放方向への移動を遅らせる係合状態の長穴及びピンが配
されることを特徴とする請求項3記載の軽水炉の非常用
炉心冷却水注入装置。4. The emergency core of a light water reactor according to claim 3, wherein an elongated hole and a pin in an engaged state for delaying the movement in the opening direction are arranged at a connecting portion between the link mechanism and the control valve. Cooling water injection device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP4283315A JPH06130174A (en) | 1992-10-21 | 1992-10-21 | Emergency reactor core cooling water injecting system for light water reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP4283315A JPH06130174A (en) | 1992-10-21 | 1992-10-21 | Emergency reactor core cooling water injecting system for light water reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH06130174A true JPH06130174A (en) | 1994-05-13 |
Family
ID=17663875
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP4283315A Withdrawn JPH06130174A (en) | 1992-10-21 | 1992-10-21 | Emergency reactor core cooling water injecting system for light water reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH06130174A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2008249348A (en) * | 2007-03-29 | 2008-10-16 | Toshiba Corp | Boiling water reactor and its emergency core cooling system |
CN103778975A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive reactor core water-supplement system of pressure vessel and passive reactor core water-supplement method using the same |
CN103928062A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Self-pressurized reactor core water supply system |
DE102014223561A1 (en) * | 2014-11-18 | 2016-05-19 | Areva Gmbh | Feed-in system for a nuclear power plant |
-
1992
- 1992-10-21 JP JP4283315A patent/JPH06130174A/en not_active Withdrawn
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2008249348A (en) * | 2007-03-29 | 2008-10-16 | Toshiba Corp | Boiling water reactor and its emergency core cooling system |
JP4675926B2 (en) * | 2007-03-29 | 2011-04-27 | 株式会社東芝 | Boiling water reactor |
CN103778975A (en) * | 2012-10-22 | 2014-05-07 | 中国核动力研究设计院 | Passive reactor core water-supplement system of pressure vessel and passive reactor core water-supplement method using the same |
CN103928062A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Self-pressurized reactor core water supply system |
DE102014223561A1 (en) * | 2014-11-18 | 2016-05-19 | Areva Gmbh | Feed-in system for a nuclear power plant |
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