JPH0511592B2 - - Google Patents
Info
- Publication number
- JPH0511592B2 JPH0511592B2 JP60022397A JP2239785A JPH0511592B2 JP H0511592 B2 JPH0511592 B2 JP H0511592B2 JP 60022397 A JP60022397 A JP 60022397A JP 2239785 A JP2239785 A JP 2239785A JP H0511592 B2 JPH0511592 B2 JP H0511592B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel pool
- water
- fuel
- pool
- cooling
- 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.)
- Expired - Lifetime
Links
- 239000000446 fuel Substances 0.000 claims description 104
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 74
- 238000001816 cooling Methods 0.000 claims description 47
- 239000000498 cooling water Substances 0.000 claims description 11
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 3
- 238000011144 upstream manufacturing Methods 0.000 claims description 3
- 238000004891 communication Methods 0.000 claims description 2
- 239000002828 fuel tank Substances 0.000 claims 2
- 230000001629 suppression Effects 0.000 description 12
- 238000002955 isolation Methods 0.000 description 7
- 230000000694 effects Effects 0.000 description 5
- 238000007689 inspection Methods 0.000 description 5
- 206010073306 Exposure to radiation Diseases 0.000 description 4
- 238000012423 maintenance Methods 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000001914 filtration Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 238000012790 confirmation Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
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)
- Jet Pumps And Other Pumps (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、原子力発電所の原子炉燃料プール給
水系統に係り、特に原子炉残留熱除去系と燃料プ
ール冷却系と燃料プール補給水系とを合理的に系
統構成する接続系統に関するものである。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a reactor fuel pool water supply system in a nuclear power plant, and in particular, to rationalize a reactor residual heat removal system, a fuel pool cooling system, and a fuel pool make-up water system. This is related to the connection system that is configured as a system.
従来の原子炉周りの系統構成を第２図により説
明する。
The system configuration around a conventional nuclear reactor will be explained with reference to FIG.
原子炉停止時に残留熱を除去するための原子炉
残留熱除去系は、サプレツシヨンチヤンバ１，サ
プレツシヨンチヤンバ隔離弁２、その下流に配置
されるポンプ３，熱交換器４，，配管５，熱交換
器４から配管５への中間に設けられた熱交換器出
口ライン６，熱交換器出口仕切弁７などを含み、
図上左右対称に２系統が配置されている。 The reactor residual heat removal system for removing residual heat when the reactor is shut down includes a suppression chamber 1, a suppression chamber isolation valve 2, a pump 3 disposed downstream of the suppression chamber 1, a heat exchanger 4, etc. It includes a pipe 5, a heat exchanger outlet line 6 provided intermediately from the heat exchanger 4 to the pipe 5, a heat exchanger outlet gate valve 7, etc.
Two systems are arranged symmetrically in the figure.
また、燃料プール冷却系は、スキマーサージタ
ンク１４，燃料プール冷却系ポンプ３３，ろ過脱
塩器３２，熱交換器３１などからなり、原子炉建
物床３０の上に配置されている。燃料プール１８
内の燃料プール水は、その水面近くに開口したス
キマーを通してスキマーサージタンク１４に流入
し、ポンプ３３によりろ過脱塩器３２に供給さ
れ、浄化される。 Further, the fuel pool cooling system includes a skimmer surge tank 14, a fuel pool cooling system pump 33, a filtration demineralizer 32, a heat exchanger 31, etc., and is arranged on the reactor building floor 30. fuel pool 18
The water in the fuel pool flows into the skimmer surge tank 14 through a skimmer opened near the water surface, and is supplied to the filtration demineralizer 32 by a pump 33 and purified.
スキマーサージタンク１４は、燃料プール１８
内の冷却水の一部が失われたときに、ここでは詳
細には図示していないが外部に設置されている常
用の燃料プール水補給水系４０から冷却水の補給
を受ける。 The skimmer surge tank 14 is connected to the fuel pool 18
When some of the cooling water in the fuel pool is lost, cooling water is supplied from a regular fuel pool water replenishment water system 40 installed outside, although not shown in detail here.
さらに、燃料プーール補給水系は、復水貯蔵タ
ンク８，ポンプ吸込側弁９，燃料プール補給水ポ
ンプ１０，ポンプ吐出側弁１１，ポンプ吐出管１
９などから構成されている。 Further, the fuel pool makeup water system includes a condensate storage tank 8, a pump suction side valve 9, a fuel pool makeup water pump 10, a pump discharge side valve 11, and a pump discharge pipe 1.
It consists of 9 etc.
本系統の機能は、地震時の溢水またはプールラ
イナ破損によるプール水の漏洩等により、燃料プ
ールの冷却水保有量の一部が喪失し、かつ常用の
燃料プール水補給水系４０が使用できない時に冷
却水を燃料プールに補給するものである。冷却水
を貯蔵する水源である復水貯蔵タンク８から、燃
料プール補給水ポンプ１０で燃料プール１８に冷
却水を補給できるようにする。押込圧力が低下し
て、NPSH不足により補給水ポンプ１０が損傷
を受けないように、補給水ポンプ１０を入口圧力
「低」で停止させて保護する。また、補給水ポン
プ１０は、入口弁９が開以外は起動不可とする。 The function of this system is to provide cooling when a portion of the fuel pool's cooling water capacity is lost due to overflow during an earthquake or leakage of pool water due to damage to the pool liner, and the regular fuel pool water make-up water system 40 cannot be used. It supplies water to the fuel pool. A fuel pool 18 can be supplied with cooling water from a condensate storage tank 8, which is a water source for storing cooling water, by a fuel pool makeup water pump 10. In order to prevent the make-up water pump 10 from being damaged due to NPSH shortage due to a drop in the pushing pressure, the make-up water pump 10 is stopped at a "low" inlet pressure to protect the make-up water pump 10. Furthermore, the make-up water pump 10 cannot be started unless the inlet valve 9 is open.
本系統はS1以上の地震時または、燃料プール水
漏洩が発生するような不測事事態の事象において
使用を要求されるものである。したがつて、通常
状態では使用することが殆どない系統設備であ
り、設備の合理化，改善等が必ずしも十分配慮さ
れていなかつた。 This system is required to be used in the event of an earthquake of S 1 or higher or in an unforeseen event such as a fuel pool water leak. Therefore, the system equipment is rarely used under normal conditions, and sufficient consideration has not necessarily been given to rationalizing and improving the equipment.
一方、従来の残留熱除去系の主な運転モードと
して、原子炉停止時冷却モードがある。このモー
ドは、原子炉再循環ポンプ吸込配管から炉水をポ
ンプ２８により吸引し、熱交換器４，２０で冷却
した後、原子炉再循環ポンプ吐出配管（ジエツト
ポンプ経由で炉心へ循環）を経由して、再び原子
炉に戻すものである。 On the other hand, the main operating mode of conventional residual heat removal systems is a cooling mode during reactor shutdown. In this mode, reactor water is sucked by the pump 28 from the reactor recirculation pump suction pipe, cooled by the heat exchangers 4 and 20, and then passed through the reactor recirculation pump discharge pipe (circulated to the reactor core via the jet pump). It is then returned to the reactor.
また、燃料プール冷却補助系として、燃料プー
ル水を本系統のポンプ２８から吸引し、熱交換器
４，２０で冷却した後、燃料プール１８へ戻すこ
とも行なわれる。燃料プール冷却補助ライン３４
はそのために設けてある。計画取出し量以上の使
用済燃料を、燃料プール１８に貯蔵する非常の場
合に、原子炉残留熱除去系でプール水を冷却し
て、規定の温度（例えば約70℃）以下に維持でき
るように、仕切弁１５を介してスキマーサージタ
ンク１４の出口配管を分岐し、原子炉残留熱除去
系統に接続し、残留熱除去系統のポンプ３，２４
および熱交換器４，２０を通り、補助ライン３４
から戻るようにしてある。 Further, as a fuel pool cooling auxiliary system, fuel pool water is sucked from the pump 28 of the main system, cooled by the heat exchangers 4 and 20, and then returned to the fuel pool 18. Fuel pool cooling auxiliary line 34
is provided for that purpose. In an emergency situation where more spent fuel than the planned removal amount is stored in the fuel pool 18, the reactor residual heat removal system cools the pool water to maintain it below a specified temperature (for example, about 70°C). , the outlet piping of the skimmer surge tank 14 is branched via the gate valve 15 and connected to the reactor residual heat removal system, and the pumps 3 and 24 of the residual heat removal system are connected to the reactor residual heat removal system.
and the auxiliary line 34 through the heat exchangers 4 and 20.
It is designed to return from
燃料プール補給水系と燃料プール冷却補助系と
は、各系統の作動を簡易化することと、各系統機
能の独立性を確保するために、個々の独立した系
統設備とすることが一般的であつた。燃料プール
冷却補助系も、通常状態では使用することが極め
て稀な系統設備であり、設備の合理化や改善等が
必ずしも十分ではなかつた。 The fuel pool make-up water system and the fuel pool cooling auxiliary system are generally separate system equipment in order to simplify the operation of each system and ensure the independence of each system function. Ta. The fuel pool cooling auxiliary system is also a system equipment that is rarely used under normal conditions, and the rationalization and improvement of the equipment has not necessarily been sufficient.
また、原子炉の停止毎に原子炉停止時冷却モー
ド運転するが、その度に燃料プール冷却補助ライ
ン３４にも炉水が充満し、特にこのライン３４が
建物内高位部に設けてあつたために配管付近の放
射線量を高くして、パトロールや保守点検作業を
行う作業員の被曝の主原因のひとつとなつてい
た。これに対する被曝防止の通常手段として実施
される遮蔽施工は、遮蔽材の追加と遮蔽スペース
の占有を必要とし、ここでも経済的かつ合理的な
プラントの構成となつていなかつた。 In addition, each time the reactor is shut down, the reactor shutdown cooling mode is operated, but each time the reactor cooling auxiliary line 34 is also filled with reactor water, especially since this line 34 is installed in a high part of the building. This increased the radiation dose near the pipes, and was one of the main causes of radiation exposure for workers conducting patrols and maintenance inspections. Shielding construction, which is normally carried out as a means of preventing exposure, requires the addition of shielding materials and the occupation of shielded space, which again does not provide an economical and rational plant configuration.
本発明の目的は、合理的構成で、原子炉残留熱
除去系の燃料プール冷却補助系配管等の物量を削
減して、有効スペースを確保するとともに、作業
員の被曝を低減させた燃料プール給水系統を提供
することである。
The purpose of the present invention is to reduce the amount of piping for the fuel pool cooling auxiliary system of the reactor residual heat removal system with a rational configuration, secure effective space, and reduce the exposure of workers to the fuel pool water supply. It is to provide a system.
本発明は、原子炉残留熱除去系熱交換器出口ラ
インから建物内の高位に設置されている燃料プー
ルへの燃料プール冷却補助ライン３４に代えて、
次のような構成を提案するものである。建物内の
低位にある上記熱交換器４と、同じく建物内低位
に設置されている燃料プール補給水ポンプ１０の
出口ラインとを接続し、燃料プール補給水ポンプ
吐出管１９に先の補助ライン３４の機能を果さ
せ、配管，サポート，保温材等を削減し、それと
ともに補助ライン３４で問題であつた被曝の問題
をなくす構成である。勿論、兼用化しても、燃料
プール補給水系の機能と燃料プール冷却補助系の
機能の独立性が保たれるように、両系統合流部に
は隔離弁１３を設置する。それにより系統機能確
認試験も可能とする。
In the present invention, instead of the fuel pool cooling auxiliary line 34 from the reactor residual heat removal system heat exchanger outlet line to the fuel pool installed at a high level in the building,
The following configuration is proposed. The heat exchanger 4 located at a low level in the building is connected to the outlet line of the fuel pool makeup water pump 10 which is also installed at a low location in the building, and the auxiliary line 34 is connected to the fuel pool makeup water pump discharge pipe 19. This configuration reduces the need for piping, supports, heat insulating materials, etc., and eliminates the problem of exposure to radiation, which was a problem with the auxiliary line 34. Of course, an isolation valve 13 is installed at the junction of both systems so that the independence of the functions of the fuel pool make-up water system and the fuel pool cooling auxiliary system can be maintained even if the systems are combined. This will also enable system function confirmation tests.
原子炉停止時冷却モードが作動し、２系列独立
に設置されている残留熱除去系熱交換器４，２０
の内どちらかの１系列が稼動中であつても、もう
一方の熱交換器を利用して、燃料プール冷却補助
ラインの機能が十分維持されるように、２つの熱
交換器の出口を連絡する配管２１，弁２２，サポ
ート等からなる連絡ラインを設置し、仕切弁２
２，２３の開閉操作により、使用する熱交換器を
選択する。 Residual heat removal system heat exchangers 4 and 20 are installed in two independent lines and the reactor shutdown cooling mode is activated.
The outlet of the two heat exchangers is connected so that even if one of the lines is in operation, the function of the fuel pool cooling auxiliary line is maintained sufficiently by using the other heat exchanger. A communication line consisting of piping 21, valve 22, support, etc. is installed, and gate valve 2
Select the heat exchanger to be used by opening and closing operations 2 and 23.
通常の燃料プール冷却系以外に、燃料プール冷
却補助設備を使用する場合が、仮に発生し、同時
に、燃料プール水が漏洩するような不測事態が発
生した場合には、直ちに、燃料プールに十分な冷
却保有水量を供給することを優先的に考える必要
がある。したがつて、燃料プール冷却補助系と補
給水系との間に設けてある系統隔離弁１３は、遠
隔操作により緊急締切可能な弁とする。また、そ
の弁１３と燃料プール補給水ポンプ１０とは、イ
ンターロツクにより接続し、系統隔離弁１３が閉
状態で、燃料プール補給水ポンプが起動可能とな
るようにしてある。 If fuel pool cooling auxiliary equipment is used in addition to the normal fuel pool cooling system, and an unexpected situation such as fuel pool water leaks occurs, immediately ensure that the fuel pool has enough water. It is necessary to give priority to supplying the amount of water available for cooling. Therefore, the system isolation valve 13 provided between the fuel pool cooling auxiliary system and the make-up water system is a valve that can be shut off in an emergency by remote control. Further, the valve 13 and the fuel pool make-up water pump 10 are connected by an interlock so that the fuel pool make-up water pump can be started when the system isolation valve 13 is closed.
本発明の一実施例を第１図により説明する。図
中の太線部分が、本発明により改良された系統構
成を示す。
An embodiment of the present invention will be explained with reference to FIG. The bold line portion in the figure shows the system configuration improved by the present invention.
サプレツシヨンチヤンバ１を水源とし、サプレ
ツシヨンチヤンバ隔離弁２，，ポンプ３，熱交換
器４，配管５等からなる２系列を有する残留熱除
去系において、熱交換器出口ライン６に設置され
ている熱交換器口仕切弁７の上流側から、復水貯
蔵タンク８，ポンプ吸込側弁９，燃料プール補給
水系ポンプ１０，ポンプ吐出管逆止弁１１，ポン
プ吐出管１９等からなり開ループを構成する燃料
プール補給水系の燃料プール補給水ポンプ吐出管
逆止弁１１の下流側に、配管１２および遠隔操作
可能電動弁１３からなる燃料プール冷却補助ライ
ンを設置する。 In a residual heat removal system that uses a suppression chamber 1 as a water source and has two lines consisting of a suppression chamber isolation valve 2, a pump 3, a heat exchanger 4, piping 5, etc., a heat exchanger outlet line 6 is connected to the suppression chamber 1. From the upstream side of the installed heat exchanger opening gate valve 7, it consists of a condensate storage tank 8, a pump suction side valve 9, a fuel pool makeup water system pump 10, a pump discharge pipe check valve 11, a pump discharge pipe 19, etc. A fuel pool cooling auxiliary line consisting of piping 12 and a remotely controllable electric valve 13 is installed downstream of the fuel pool make-up water pump discharge pipe check valve 11 of the fuel pool make-up water system forming an open loop.
通常の計画取出し量以上の使用済燃料を燃料プ
ール１８に貯蔵する非常の場合、スキマーサージ
タンク１４下流側の仕切弁１５を開き、燃料プー
ル冷却補助用残留熱除去系タイライン１６の仕切
弁１７を開く。それによつて残留熱除去系ポンプ
３よりも高位にある燃料プール１８内の水が、ポ
ンプ３の吸込側配管に充満する。その際、サプレ
ツシヨンチヤンバ隔離弁２は閉じておき、燃料プ
ール内の水が、サプレツシヨンチヤンバ１内に混
入しないようにすると同時に、サプレツシヨンチ
ヤンバ内の水も隔離し、サプレツシヨンチヤンバ
内の水が燃料プール１８に混入しないよううにす
る。 In an emergency where more spent fuel is stored in the fuel pool 18 than the normal planned withdrawal amount, the gate valve 15 downstream of the skimmer surge tank 14 is opened, and the gate valve 17 of the residual heat removal system tie line 16 for assisting fuel pool cooling is opened. open. As a result, water in the fuel pool 18 located at a higher level than the residual heat removal system pump 3 fills the suction side piping of the pump 3. At this time, the suppression chamber isolation valve 2 is closed to prevent the water in the fuel pool from entering the suppression chamber 1, and at the same time isolate the water in the suppression chamber. Water in the suppression chamber is prevented from entering the fuel pool 18.
次に熱交換器出口仕切弁７を閉じ弁１３と弁２
３を開く。残留熱除去系ポンプ３を起動すると、
燃料プール内の水は、ポンプ３の吐出側流路か
ら、配管１２，弁１３を介し、燃料プール補給水
ポンプ吐出管１９を通り、燃料プール１８へ流れ
込む。その際、熱交換器４にて規定の温度（例え
ば約70℃）以下に充分冷却される。燃料プーール
冷却補助系を作動させる時点においては、プラン
トが停止中だから、残留熱除去系をいつでも使用
できるよう待機させておく必要はない。したがつ
て、残留熱除去系を利用した本系統設備の使用
は、安全上支障のないものといえる。 Next, close the heat exchanger outlet gate valve 7 and close the valves 13 and 2.
Open 3. When the residual heat removal system pump 3 is started,
Water in the fuel pool flows from the discharge side flow path of the pump 3 through the piping 12 and the valve 13, through the fuel pool make-up water pump discharge pipe 19, and into the fuel pool 18. At that time, the heat exchanger 4 sufficiently cools the material to a specified temperature (for example, about 70° C.) or lower. Since the plant is stopped when the fuel pool cooling auxiliary system is activated, there is no need to keep the residual heat removal system ready for use at any time. Therefore, it can be said that the use of this system equipment using a residual heat removal system does not pose any safety problems.
次に、プラント停止中ではあるが、停止時冷却
モードが作動しており、残留熱除去系ポンプ，熱
交換器が既に使用されている段階で、燃料プール
冷却補助ラインの使用が発生したと考える。残留
熱除去系は、通常２系列の冷却機能を有するよう
に、ポンプ，熱交換器は各２台を備えた系統構成
となつている。もう一方の熱交換器２０の出口ラ
インから、配管２１仕切弁２２からなるタイライ
ンを、配管１２の弁１３より上流側に接続する。 Next, consider that the use of the fuel pool cooling auxiliary line occurred when the plant was shut down, but the shutdown cooling mode was operating, and the residual heat removal system pump and heat exchanger were already in use. . The residual heat removal system usually has a system configuration including two pumps and two heat exchangers so that it has two cooling functions. A tie line consisting of a pipe 21 and a gate valve 22 is connected from the outlet line of the other heat exchanger 20 to the upstream side of the valve 13 of the pipe 12.
仮に、停止時冷却モードが作動し、燃料プール
冷却補助のために、ポンプ３，熱交換器４の使用
が制限される場合は、前述と同様に、各仕切弁を
開閉する。そしてタイライン仕切弁２２を開き、
ポンプ２４を起動し、熱交換器２０で冷却し、タ
イライン２１，弁２２，弁１３，配管１９を介し
て燃料プール１８へ燃料プール内の水を戻す。し
たがつて、停止時冷却モードが作動していても、
燃料プール冷却補助機能は十分確保される。 If the stop cooling mode is activated and the use of the pump 3 and heat exchanger 4 is restricted to assist in cooling the fuel pool, each gate valve is opened and closed in the same manner as described above. Then, open the tie line gate valve 22,
The pump 24 is started, the water in the fuel pool is cooled by the heat exchanger 20, and is returned to the fuel pool 18 via the tie line 21, valve 22, valve 13, and piping 19. Therefore, even if the stop cooling mode is activated,
Sufficient fuel pool cooling support function will be ensured.
次に、地震時に燃料プール保有水が溢水し、ま
たは、プールライナー破損によりプールが漏洩
し、燃料プールの冷却水保有量の一部が失われた
時には、ポンプ１０が起動して、復水貯蔵タンク
８内の保有水をポンプ吐出管１９から燃料プール
１８に供給し、燃料プール内の必要保有水量を確
保する。 Next, when the water held in the fuel pool overflows during an earthquake, or the pool leaks due to damage to the pool liner, and part of the amount of cooling water held in the fuel pool is lost, the pump 10 is activated to store condensate. The water in the tank 8 is supplied to the fuel pool 18 from the pump discharge pipe 19 to ensure the required amount of water in the fuel pool.
その際、復水貯蔵タンク８内の水が、燃料プー
ル１８に導かれず、ポンプ１０の吐出配管１９に
接続されている配管１２や２１へ逆流しないよう
に、ポンプ１０が作動している間は弁１３が閉じ
るように、ポンプ１０と弁１３をインターロツク
しておく。また、燃料プール冷却補助系の作動中
に、緊急に燃料プール補給水系を作動させる必要
を想定し、弁１３を遠隔操作弁とする。必要に応
じて、即時に閉操作するとともに、燃料補給水ポ
ンプ１０を起動させ、燃料プール補給水系の機能
を確保する。残留熱除去系ポンプ３，２４は、従
来から、遠隔操作が可能であるから、ポンプ３，
４を速やかに停止させた後、弁１３を緊急に閉じ
て、ウオーターハンマーの発生や弁１３の閉操作
が困難になるのを回避する。 At that time, while the pump 10 is operating, the water in the condensate storage tank 8 is not led to the fuel pool 18 and is not allowed to flow back into the pipes 12 and 21 connected to the discharge pipe 19 of the pump 10. Pump 10 and valve 13 are interlocked so that valve 13 is closed. In addition, assuming that it is necessary to urgently operate the fuel pool replenishment water system while the fuel pool cooling auxiliary system is operating, the valve 13 is configured as a remote control valve. If necessary, the fuel pool makeup water system is immediately closed and the fuel water pump 10 is activated to ensure the function of the fuel pool makeup water system. Conventionally, the residual heat removal system pumps 3 and 24 can be remotely controlled.
After stopping the valve 4 quickly, the valve 13 is closed urgently to avoid occurrence of water hammer and difficulty in closing the valve 13.
以上のように、本実施例においては、燃料プー
ル補給水系，燃料プール冷却系，原子炉残留熱除
去系それぞれの系統機能の健全性と信頼性は十分
確保可能である。 As described above, in this embodiment, the soundness and reliability of the system functions of the fuel pool make-up water system, fuel pool cooling system, and reactor residual heat removal system can be sufficiently ensured.
また、停止時冷却モード作動中の炉水が、従来
のごとく、燃料プール冷却補助ライン３４の広範
囲にわたり充満することがなく、しかも建物内の
低位に集中して配管，弁等があるために、建物内
高位部で、パトロール，保守点検，分解等を実施
する作業員の被曝の低減，遮蔽物量の削減に効果
がある。 In addition, reactor water during shutdown cooling mode does not fill a wide area of the fuel pool cooling auxiliary line 34 as in the past, and is concentrated in the lower part of the building where there are pipes, valves, etc. It is effective in reducing radiation exposure for workers who perform patrols, maintenance inspections, disassembly, etc. in high-level parts of buildings, and in reducing the amount of shielding.
このように、建物内高位部に設置されていた原
子残留熱除去系の燃料プール冷却補助ライン３４
を削除することにより、配管，サポート，保温等
の物量を大巾に削減することが可能となり、合理
的系統設備となる効果がある。加えて、物量の削
減により、通路性や保守点検性の改善など周辺ス
ペースの有効利用によるスペース改善の効果があ
る。 In this way, the fuel pool cooling auxiliary line 34 of the atomic residual heat removal system, which was installed in a high part of the building,
By eliminating this, it becomes possible to greatly reduce the amount of piping, supports, heat insulation, etc., which has the effect of making the system more rational. In addition, by reducing the amount of materials, there is an effect of improving space by making effective use of surrounding space, such as improving passageability and ease of maintenance and inspection.
本発明によれば、原子炉残留熱除去系の燃料プ
ール冷却補助ラインを削除でき、配管，配管サポ
ート，保温，遮蔽材等を著しく低減可能となり、
合理的な系統構成の経済的なプラントが得られ
る。
According to the present invention, it is possible to eliminate the fuel pool cooling auxiliary line of the reactor residual heat removal system, and it is possible to significantly reduce the number of piping, piping supports, heat insulation, shielding materials, etc.
An economical plant with a rational system configuration can be obtained.
また、原子炉残留熱除去系の燃料プール冷却補
助ラインを削除することにより、従来のそのライ
ン付近でのパトロール，保守点検，検査作業等で
作業員が受けていた被曝低減の効果がある。さら
に新たなスペースが確保でき、通路性の改善，配
置条件の緩和等，スペース性の改善効果がある。 In addition, by eliminating the fuel pool cooling auxiliary line of the reactor residual heat removal system, it has the effect of reducing the radiation exposure that workers were previously exposed to during patrols, maintenance inspections, inspections, etc. near that line. Furthermore, new space can be secured, which has the effect of improving space efficiency, such as improving passage and easing layout conditions.
第１図は本発明による燃料プール給水系統を備
えた補給水系，原子炉残留熱除去系，燃料プール
冷却系を示す系統図、第２図は従来の補給水系，
原子炉残留熱除去系，燃料プール冷却系を示す系
統図である。
１……サプレツシヨンチヤンバ、２……サプレ
ツシヨンチヤンバ隔離弁、３……ポンプ、４……
熱交換器、５……配管、６……熱交換器出口ライ
ン、７……熱交換器出口仕切弁、８……復水貯蔵
タンク、９……ポンプ吸込側弁、１０……燃料プ
ール補給水ポンプ、１１……ポンプ吐出側逆止
弁、１２……配管、１３……遠隔操作可能電動
弁、１４……スキマーサージタンク、１５……ス
キマーサージタンク下流側仕切弁、１６……燃料
プール冷却補助用残留熱除去系タイライン、１７
……仕切弁、１８……燃料プール、１９……燃料
プール補給水ポンプ吐出管、２０……熱交換器、
２１……タイライン、２２……タイライン仕切
弁、２３……仕切弁、２４……ポンプ、２５……
原子炉建物、２６……原子炉格納容器、２７……
原子炉圧力容器、２８……再循環系ポンプ、２９
……再循環系配管、３０……原子炉建物床、３１
……燃料プール冷却系熱交換器、３２……燃料プ
ール冷却系ろ過脱塩装置、３３……燃料プール冷
却系ポンプ、３４……燃料プール冷却補助ライ
ン。
Fig. 1 is a system diagram showing a make-up water system, a reactor residual heat removal system, and a fuel pool cooling system equipped with a fuel pool water supply system according to the present invention, and Fig. 2 shows a conventional make-up water system,
FIG. 2 is a system diagram showing a reactor residual heat removal system and a fuel pool cooling system. 1...Suppression chamber, 2...Suppression chamber isolation valve, 3...Pump, 4...
Heat exchanger, 5... Piping, 6... Heat exchanger outlet line, 7... Heat exchanger outlet gate valve, 8... Condensate storage tank, 9... Pump suction side valve, 10... Fuel pool replenishment Water pump, 11... Pump discharge side check valve, 12... Piping, 13... Remotely controllable electric valve, 14... Skimmer surge tank, 15... Skimmer surge tank downstream gate valve, 16... Fuel pool Residual heat removal system tie line for cooling assistance, 17
... Gate valve, 18 ... Fuel pool, 19 ... Fuel pool makeup water pump discharge pipe, 20 ... Heat exchanger,
21... Tie line, 22... Tie line gate valve, 23... Gate valve, 24... Pump, 25...
Reactor building, 26... Reactor containment vessel, 27...
Reactor pressure vessel, 28...Recirculation system pump, 29
... Recirculation system piping, 30 ... Reactor building floor, 31
...Fuel pool cooling system heat exchanger, 32...Fuel pool cooling system filtration desalination device, 33...Fuel pool cooling system pump, 34...Fuel pool cooling auxiliary line.
Claims (1)
燃料プール内の冷却水の一部が失われたときに常
用燃料プール水補給水系から冷却水の補給を受け
るスキマーサージタンクと燃料プール水を冷却す
る熱交換器とを含む燃料プール冷却系と、原子炉
停止時に残留熱を除去する一方で計画取出し量以
上の使用済燃料を燃料プールに貯蔵する非常の場
合に前記スキマーサージタンク出口から分岐させ
たプール水を冷却する熱交換器を含む複数系列の
原子炉残留熱除去系と、復水貯蔵タンクとその復
水を送り出す燃料プール補給水ポンプとそこから
燃料プールに復水を導くポンプ吐出管とを含み燃
料プール内の冷却水の一部が失われしかも前記常
用燃料プール水補給水系が使用できないときに燃
料プールに冷却水を補給する燃料プール補給水系
とからなる燃料プール給水系統において、 前記燃料プール補給水ポンプの作動中は閉じる
インターロツクを備えた遠隔操作弁を介して、一
系列の前記原子炉残留熱除去系の熱交換器出口仕
切弁下流と燃料プール補給水ポンプの吐出側に設
置された逆止弁の下流とを接続する配管を設け、 前記遠隔操作弁の開閉により、復水貯蔵タンク
から燃料プールへの冷却水補給と残留熱除去系か
ら燃料プールへのプール水の戻りとに前記吐出管
を切換え使用することを特徴とする燃料プール給
水系統。 ２ 特許請求の範囲第１項において、 前記一系列を除いた原子炉残留熱除去系の熱交
換器出口から仕切弁を介して前記遠隔操作弁上流
に連絡ラインを設け、各系列の仕切弁の切換えに
より、いずれかひとつの系列が残留熱除去運転中
にも他の系列の残留熱除去系を燃料プールのプー
ル水の冷却に用いることを特徴とする燃料プール
給水系統。[Scope of Claims] 1. A skimmer surge tank that is connected to a fuel pool via a skimmer and receives cooling water from a regular fuel pool water supply system when a portion of the cooling water in the fuel pool is lost; and a fuel tank. a fuel pool cooling system including a heat exchanger for cooling pool water; and a skimmer surge tank for storing spent fuel in the fuel pool in excess of the planned withdrawal amount while removing residual heat when the reactor is shut down. A multiple series reactor residual heat removal system including a heat exchanger that cools the pool water branched from the outlet, a condensate storage tank, a fuel pool make-up water pump that sends out the condensate, and a condensate from there to the fuel pool. a fuel pool water supply system that replenishes cooling water to the fuel pool when a part of the cooling water in the fuel pool is lost and the regular fuel pool water makeup water system cannot be used; In the system, a series of downstream heat exchanger outlet gate valves of the reactor residual heat removal system and the fuel pool make-up water pump are connected through a remote control valve with an interlock that closes when the fuel pool make-up water pump is in operation. A pipe is installed to connect downstream of the check valve installed on the discharge side of the fuel tank, and by opening and closing the remote control valve, cooling water is supplied from the condensate storage tank to the fuel pool, and from the residual heat removal system to the fuel pool. A fuel pool water supply system characterized in that the discharge pipe is used selectively for returning pool water. 2. In claim 1, a communication line is provided from the heat exchanger outlet of the reactor residual heat removal system other than the one series to the upstream of the remote control valve via the gate valve, A fuel pool water supply system characterized in that, by switching, even when one of the series is in residual heat removal operation, the residual heat removal system of the other series is used for cooling the pool water of the fuel pool.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60022397A JPS61181994A (en) | 1985-02-07 | 1985-02-07 | Fuel pool feedwater system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60022397A JPS61181994A (en) | 1985-02-07 | 1985-02-07 | Fuel pool feedwater system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61181994A JPS61181994A (en) | 1986-08-14 |
| JPH0511592B2 true JPH0511592B2 (en) | 1993-02-15 |
Family
ID=12081527
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60022397A Granted JPS61181994A (en) | 1985-02-07 | 1985-02-07 | Fuel pool feedwater system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61181994A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008232880A (en) * | 2007-03-22 | 2008-10-02 | Toshiba Corp | Fuel pool cooling facility, and fuel pool cooling method |
| JP6084389B2 (en) * | 2012-07-31 | 2017-02-22 | 株式会社東芝 | Water injection equipment and reactor system |
-
1985
- 1985-02-07 JP JP60022397A patent/JPS61181994A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61181994A (en) | 1986-08-14 |
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