JPH11160481A - Emergency auxiliary cooling facility of nuclear power plant - Google Patents
Emergency auxiliary cooling facility of nuclear power plantInfo
- Publication number
- JPH11160481A JPH11160481A JP9325532A JP32553297A JPH11160481A JP H11160481 A JPH11160481 A JP H11160481A JP 9325532 A JP9325532 A JP 9325532A JP 32553297 A JP32553297 A JP 32553297A JP H11160481 A JPH11160481 A JP H11160481A
- Authority
- JP
- Japan
- Prior art keywords
- seawater
- cooling
- pump
- equipment
- pumps
- 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.)
- Pending
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
- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
Description
【0001】[0001]
【発明の属する技術分野】本発明は、原子力発電所に設
置されている残留熱除去設備、その他の非常用機器およ
び発電所の通常運転に必要な常用機器で発生する熱を最
終的な熱の逃し場である海、川、湖、大気などに逃がす
ために設けられた原子力発電所の非常用補機冷却設備に
関する。BACKGROUND OF THE INVENTION The present invention relates to a method for converting the heat generated by a residual heat removal equipment installed in a nuclear power plant, other emergency equipment and common equipment necessary for normal operation of the power plant into a final heat. The present invention relates to an emergency auxiliary cooling system for a nuclear power plant provided to escape to a sea, a river, a lake, the atmosphere, or the like, which is an escape site.
【0002】[0002]
【従来の技術】原子力発電所の非常用補機冷却設備は、
淡水ループの非常用補機冷却水系と海水系の非常用補機
冷却海水系で構成しており、従来の非常用補機冷却設備
は、原子力発電所に設置されている残留熱除去設備、そ
の他の非常用機器および発電所の通常運転に必要な常用
機器で発生する熱を最終的な熱の逃し場である海に逃が
すために設けられた設備である。2. Description of the Related Art An emergency auxiliary cooling system for a nuclear power plant includes:
It consists of a freshwater loop emergency auxiliary equipment cooling water system and a seawater system emergency auxiliary equipment cooling seawater system.Conventional emergency auxiliary equipment cooling equipment consists of residual heat removal equipment installed at nuclear power plants and other equipment. This equipment is provided to release heat generated by emergency equipment and common equipment necessary for normal operation of the power plant to the sea, which is a final heat sink.
【0003】すなわち、原子力発電所の非常用補機冷却
設備は図2に示したように熱交換器4,冷却水供給配管
1,熱交換した冷却水を熱交換器4へ戻す冷却水戻り配
管2および冷却水戻り配管2の途中に設けられた冷却水
ポンプ3からなる閉ループの淡水系の非常用補機冷却水
系Aと、熱交換器4にそれぞれ冷却海水を供給する海水
ポンプ10と冷却海水供給配管11,更に冷却海水供給配管
11間に仕切弁13を配した連絡配管16を接続し、熱交換し
た冷却海水を海に戻す放水配管12からなる海水系の非常
用補機冷却海水系Bとからなっている。この非常用補機
冷却設備は図3に示すように3系統で構成している。That is, as shown in FIG. 2, the emergency auxiliary equipment cooling equipment of a nuclear power plant has a heat exchanger 4, a cooling water supply pipe 1, and a cooling water return pipe for returning the heat-exchanged cooling water to the heat exchanger 4. 2 and a cooling water pump 3 provided in the middle of the cooling water return pipe 2, a closed loop freshwater emergency auxiliary cooling water system A, a seawater pump 10 for supplying cooling seawater to the heat exchanger 4, and a cooling seawater Supply piping 11, and cooling seawater supply piping
A connecting pipe 16 having a gate valve 13 disposed between the connecting pipes 11 is connected to a seawater emergency auxiliary cooling seawater system B comprising a water discharge pipe 12 for returning the heat-exchanged cooling seawater to the sea. This emergency auxiliary equipment cooling equipment is composed of three systems as shown in FIG.
【0004】図2についてさらに詳しく説明すれば、図
2中、符号1,2はそれぞれ非常用補機冷却水系Aの冷
却水が循環する冷却水供給配管および冷却水戻り配管で
あり、冷却水供給配管1は熱交換器4と冷却対象負荷で
ある残留熱除去熱交換器5,その他の非常用機器6,常
用機器7を結び、冷却水戻り配管2はそれぞれの冷却対
象機器から2台並列接続した冷却水ポンプ3を介して熱
交換器4に接続され、全体として閉ループを構成してい
る。FIG. 2 will be described in more detail. In FIG. 2, reference numerals 1 and 2 respectively indicate a cooling water supply pipe and a cooling water return pipe through which the cooling water of the emergency auxiliary equipment cooling water system A circulates. The pipe 1 connects the heat exchanger 4 with the residual heat removing heat exchanger 5 which is the load to be cooled 5, the other emergency equipment 6, and the service equipment 7, and two cooling water return pipes 2 are connected in parallel from each equipment to be cooled. The cooling water pump 3 is connected to the heat exchanger 4 to form a closed loop as a whole.
【0005】残留熱除去熱交換器5の冷却水戻り配管2
には弁8が設置され、常用機器7の冷却水供給配管1お
よび戻り配管2には弁9が設置されている。海水系の非
常用補機冷却海水系Bについては、それぞれの熱交換器
4には海水ポンプ10とを結ぶ冷却海水供給配管11と放水
配管12が接続され、更に冷却海水供給配管11間に仕切弁
13を配した連絡配管16を接続している。[0005] The cooling water return pipe 2 of the residual heat removal heat exchanger 5
A valve 8 is installed in the cooling water supply pipe 1 and the return pipe 2 of the common equipment 7. For the seawater system emergency auxiliary cooling seawater system B, each heat exchanger 4 is connected to a cooling seawater supply pipe 11 and a water discharge pipe 12 connecting a seawater pump 10, and is further partitioned between the cooling seawater supply pipes 11. valve
A connecting pipe 16 in which 13 is arranged is connected.
【0006】図2中、符号17は切替弁装置で、この切替
弁装置17は熱交換器4を介して非常用補機冷却水系Aを
循環する冷却水と熱交換器4をバイパスして循環する冷
却水の流量をバランスさせるためのものである。In FIG. 2, reference numeral 17 denotes a switching valve device. The switching valve device 17 circulates the cooling water circulating through the emergency accessory cooling water system A via the heat exchanger 4 and bypasses the heat exchanger 4. The purpose is to balance the flow rate of the cooling water.
【0007】原子力発電所においては、図3に示すよう
に、このような構成の非常用補機冷却設備が3系統タイ
ライン18で接続されており、事故時に対する設計上の除
熱性能として各系統とも50%の除熱能力を有している。
すなわち、3系統のうち2系統にて所要除熱能力を満足
する設計としている。In a nuclear power plant, as shown in FIG. 3, the emergency auxiliary equipment cooling system having such a configuration is connected by a three-system tie line 18, and as a design heat removal performance in the event of an accident, Both systems have a heat removal capacity of 50%.
That is, the design is such that two of the three systems satisfy the required heat removal capability.
【0008】これは、1系統が何らかの事象により故障
した場合でも残りの設備で機能を満足させるという原子
力プラントにおける安全設計の基本的な考え方である単
一故障基準に従っているものである。[0008] This is based on a single failure criterion, which is a basic concept of safety design in a nuclear power plant, in that even if one system fails due to some event, the function is satisfied with the remaining equipment, which is a basic concept of safety design in a nuclear power plant.
【0009】このような構成からなる非常用補機冷却設
備において、冷却水ポンプ3により冷却水供給配管1,
冷却水戻り配管2内を循環する冷却水は、熱交換器4で
冷却され冷却水供給配管1を介し冷却対象負荷である残
留熱除去熱交換器5,その他の非常用機器6,常用機器
7に供給される。In the emergency auxiliary equipment cooling system having such a configuration, the cooling water supply pipes 1 and
The cooling water circulating in the cooling water return pipe 2 is cooled by the heat exchanger 4 and is cooled via the cooling water supply pipe 1 as a load to be cooled, a residual heat removal heat exchanger 5, other emergency equipment 6, a regular equipment 7. Supplied to
【0010】冷却対象機器を冷却し昇温した冷却水は冷
却水戻り配管2および冷却水ポンプ3を介して再び熱交
換器4に戻される。昇温された冷却水は海水ポンプ10に
より冷却海水供給配管11を介して熱交換器4に供給され
る海水により熱交換し放水配管12より最終的な熱の逃し
場である海に放出される。The cooling water, which has cooled the equipment to be cooled and raised in temperature, is returned to the heat exchanger 4 again through the cooling water return pipe 2 and the cooling water pump 3. The heated cooling water is heat-exchanged by the seawater supplied to the heat exchanger 4 via the cooling seawater supply pipe 11 by the seawater pump 10 and is discharged from the water discharge pipe 12 to the sea, which is a final heat release area. .
【0011】このような構成において、非常用補機冷却
海水設備は、通常運転中は各系列共にポンプ1台,熱交
換器1基が運転され、事故時においては各系列共にポン
プ2台,熱交換器2基の全台の運転が必要となってい
る。In such a configuration, the emergency auxiliary equipment cooling seawater system operates one pump and one heat exchanger in each system during normal operation, and two pumps and heat exchangers in each system during an accident. The operation of all two exchangers is required.
【0012】[0012]
【発明が解決しようとする課題】非常用補機冷却設備の
機器は定期的な保守点検を実施する。従来の構成では各
系列共通常運転時冷却水はポンプ3を1台,海水ポンプ
10を1台,熱交換器4を1基が予備となっており、実質
的には保守点検可能であるが、非常用系の場合、この予
備の冷却水ポンプ3,海水ポンプ10,熱交換器4は非常
時に対する待機設備である。The equipment of the emergency auxiliary equipment cooling equipment undergoes regular maintenance and inspection. In the conventional configuration, the cooling water during normal operation for each series is one pump 3 and the seawater pump
One unit 10 and one heat exchanger 4 are spares, which can be practically maintained and inspected. However, in the case of an emergency system, this spare cooling water pump 3, seawater pump 10, heat exchange The vessel 4 is a standby facility for an emergency.
【0013】万一、通常運転中に保守点検を実施して、
冷却水ポンプ3,海水ポンプ10および熱交換器4を隔離
中に事故が発生した場合は、除熱能力が不足するため、
通常運転中の保守点検は基本的に許されていない。In the unlikely event that a maintenance check is performed during normal operation,
If an accident occurs while the cooling water pump 3, seawater pump 10 and heat exchanger 4 are isolated, the heat removal capacity is insufficient,
Maintenance inspection during normal operation is basically not allowed.
【0014】冷却水ポンプ3,海水ポンプ10および熱交
換器4のうち、特に海水ポンプ10は海水系の動的機器で
あり、付着した海生物の除去,海水腐食箇所の補修等、
健全性確保のために積極的な保守点検が必要となり、そ
の保守点検期間も長く必要としている。Among the cooling water pump 3, the seawater pump 10, and the heat exchanger 4, the seawater pump 10 is a dynamic device of a seawater system, and is used to remove attached sea creatures, repair seawater corroded parts, and the like.
Active maintenance is required to ensure soundness, and the maintenance and inspection period is also long.
【0015】通常運転中に海水ポンプ10を保守点検して
いる時に原子炉事故が発生した場合について、図4を引
用して説明する。図4は図2における非常用補機冷却海
水系Bを示しており、図4中符号にa,bを付している
のは第1の系列と第2の系列の機器,配管を区別するた
めであり、aを第1とし、bを第2とする。A case where a reactor accident occurs during maintenance and inspection of the seawater pump 10 during normal operation will be described with reference to FIG. FIG. 4 shows the emergency auxiliary equipment cooling seawater system B in FIG. 2, and reference numerals a and b in FIG. 4 denote equipment and piping of the first system and the second system. This is because a is the first and b is the second.
【0016】第1の海水ポンプ10aを保守点検する場
合、第1の海水ポンプ吐出弁15aを閉止して第1の海水
ポンプ10aを隔離するとともに、仕切弁13は通常閉止状
態であり、第2の海水ポンプ10bは第2の海水ポンプ吐
出配管14b,第2の海水供給配管11bを介して第2の海
水熱交換器4bに冷却海水を供給している。また、第2
の熱交換器4bで熱交換した冷却海水は第2の海水放水
配管12bを通して海に放水する。When performing maintenance and inspection of the first seawater pump 10a, the first seawater pump discharge valve 15a is closed to isolate the first seawater pump 10a, and the gate valve 13 is normally closed and the second seawater pump 10a is closed. The seawater pump 10b supplies cooling seawater to the second seawater heat exchanger 4b via a second seawater pump discharge pipe 14b and a second seawater supply pipe 11b. Also, the second
The cooling seawater heat-exchanged by the heat exchanger 4b is discharged to the sea through the second seawater discharge pipe 12b.
【0017】この時、原子炉事故が発生した場合、第1
および第2の海水ポンプ10a,10bは予備を持っていな
いため、通常運転状態の除熱能力しかなく、原子炉事故
による所要除熱量を冷却することができない。なお、第
2の海水ポンプ10bを保守点検する場合についても同様
の事象となる。At this time, if a nuclear reactor accident occurs, the first
Further, since the second seawater pumps 10a and 10b do not have a spare, they have only a heat removal capability in a normal operation state, and cannot cool a required heat removal amount due to a nuclear reactor accident. The same applies to the case where the maintenance and inspection of the second seawater pump 10b is performed.
【0018】このため、第1および第2の海水ポンプ10
a,10bの保守点検は原子力発電所の定期検査(以下、
定検と記す)時の限られた期間に実施することにしてい
るが、第1および第2の海水ポンプ10a,10bの点検は
長い時間を要し、定検日数の決定要因となっており、定
検日数の短縮を考えた場合、海水ポンプの点検時期を定
検期間以外の通常運転中に実施することが望まれてい
る。For this reason, the first and second seawater pumps 10
The maintenance and inspection of a and 10b are the periodic inspection of the nuclear power plant
Inspection of the first and second seawater pumps 10a and 10b takes a long time, and is a deciding factor in the number of regular inspection days. In view of reducing the number of regular inspection days, it is desired that the inspection of the seawater pump be performed during normal operation other than the regular inspection period.
【0019】本発明は上記課題を解決するためになされ
たもので、通常運転中に海水ポンプの保守点検を行うこ
とができるようにして定検期間を短縮し、信頼性の高い
原子力発電所の非常用補機冷却設備を提供することにあ
る。SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and enables maintenance and inspection of a seawater pump to be performed during normal operation, thereby shortening a regular inspection period and providing a highly reliable nuclear power plant. An object of the present invention is to provide emergency auxiliary equipment cooling equipment.
【0020】[0020]
【課題を解決するための手段】請求項1の発明は、第1
および第2の熱交換器により冷却された冷却水を冷却対
象機器である残留熱除去熱交換器、その他の非常用機器
および常用機器へ供給する冷却水供給配管と、前記残留
熱除去熱交換器、その他の非常用機器および常用機器で
熱交換した冷却水を前記第1および第2の熱交換器へ戻
す冷却水戻り配管および前記冷却水戻り配管に設けられ
た冷却水ポンプよりなる閉ループの淡水系と、前記第1
および第2の熱交換器にそれぞれ冷却海水を供給する第
1および第2の海水ポンプと第1および海水供給配管
と、この第1および第2の冷却海水供給配管間に第1の
仕切弁を配した連絡配管を接続し、前記第1および第2
の熱交換器で熱交換した冷却海水を海に戻す第1および
第2の放水配管からなる海水系で構成する非常用補機冷
却設備において、前記連絡配管間に第1と第2の仕切弁
を設置し、前記第1の仕切弁と第2の仕切弁の間に第3
の吐出配管を分岐接続し、この第3の吐出配管に第3の
海水ポンプを吐出弁を介して第3の海水ポンプを接続し
てなることを特徴とする。According to the first aspect of the present invention, there is provided the following:
And a cooling water supply pipe for supplying cooling water cooled by the second heat exchanger to a residual heat removal heat exchanger to be cooled, other emergency equipment and service equipment, and the residual heat removal heat exchanger. , A closed loop fresh water comprising a cooling water return pipe for returning the cooling water heat exchanged by the other emergency equipment and the service equipment to the first and second heat exchangers, and a cooling water pump provided on the cooling water return pipe System and the first
First and second seawater pumps for supplying cooling seawater to the first and second heat exchangers, first and second seawater supply pipes, and a first gate valve between the first and second cooling seawater supply pipes. Connecting the connected communication pipes, the first and second
In the emergency auxiliary cooling system comprising a seawater system comprising first and second water discharge pipes for returning the cooling seawater heat exchanged by the heat exchanger to the sea, first and second gate valves are provided between the communication pipes. Is installed, and a third valve is provided between the first gate valve and the second gate valve.
And a third seawater pump connected to the third discharge pipe via a discharge valve.
【0021】請求項2の発明は、前記第3の海水ポンプ
を含め、1系統当たり前記第1から第3の海水ポンプ3
台を定期的に切り替えて、前記3台の海水ポンプを1台
ずつ運転する切り替え系路を設けてなることを特徴とす
る。According to a second aspect of the present invention, there is provided the first to third seawater pumps 3 per system including the third seawater pump.
The system is characterized in that a switching system for periodically switching the units and operating the three seawater pumps one by one is provided.
【0022】請求項3の発明は、前記1系統当たり第1
から第3の海水ポンプ3台のうち、何れか1台の海水ポ
ンプを保守点検している場合、残りの2台で原子炉事故
時における必要冷却海水量を確保できるように配管系路
を設けてなることを特徴とする。According to a third aspect of the present invention, the first system comprises
If one of the three third seawater pumps is being maintained and inspected, a piping system is provided so that the remaining two can secure the required amount of cooling seawater during a reactor accident. It is characterized by becoming.
【0023】請求項4の発明は、前記第1から第3の海
水ポンプのうち何れか1台ずつを運転機、待機機および
予備機とし、原子炉事故に伴う前記予備機起動の際、通
常の前記待機機が起動失敗した場合、前記予備機に起動
信号を送り起動させる電気回路を設けてなることを特徴
とする。本発明によれば、事故時においても海水ポンプ
に予備を有することができるため、通常運転中に海水ポ
ンプの保守点検を実施できる。According to a fourth aspect of the present invention, any one of the first to third seawater pumps is used as an operating unit, a standby unit and a standby unit. An electric circuit is provided for sending a start signal to the standby unit when the standby unit fails to start. According to the present invention, the seawater pump can have a spare even in the event of an accident, so that maintenance and inspection of the seawater pump can be performed during normal operation.
【0024】すなわち、本発明によると、1系統当たり
海水冷却の熱交換器が2基,海水ポンプが3台設置さ
れ、通常運転中は海水ポンプ1台,海水熱交換器1基が
運転される。このため、事故時に対する待機機としては
海水ポンプ2台,海水熱交換器1基が準備される。した
がって、海水ポンプについては、1台余分に予備を持っ
ているため、通常運転中において海水ポンプの保守点検
を実施しても系統の機能を満足することができる。That is, according to the present invention, two heat exchangers for cooling seawater and three seawater pumps are installed per system, and one seawater pump and one seawater heat exchanger are operated during normal operation. . For this reason, two seawater pumps and one seawater heat exchanger are prepared as standby machines in the event of an accident. Therefore, since the seawater pump has one extra spare, the function of the system can be satisfied even if the maintenance and inspection of the seawater pump is performed during the normal operation.
【0025】[0025]
【発明の実施の形態】本発明に係る原子力発電所の非常
用補機冷却設備の実施の形態を図1を参照して説明す
る。図1は本発明の一実施の形態を示す非常用補機冷却
設備のうちの非常用補機冷却海水系の系統概略図であ
る。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a cooling system for emergency auxiliary equipment of a nuclear power plant according to the present invention will be described with reference to FIG. FIG. 1 is a schematic system diagram of an emergency auxiliary equipment cooling seawater system in the emergency auxiliary equipment cooling equipment showing one embodiment of the present invention.
【0026】海水冷却の第1と第2の熱交換器4a,4
bに冷却海水を供給するために、第1および第2の海水
ポンプ10a,10bには第1と第2の海水ポンプ吐出弁15
a,15bを設置した海水ポンプ吐出配管14a,14b,14
cが接続され、海水供給配管11a,11bを介して第1と
第2の熱交換器4a,4bが接続し、第1と第2の熱交
換器4a,4bで熱交換された冷却海水を海に放出する
ために放水配管12a,12bが接続している。海水系の非
常用補機冷却海水系1系統にはこのように構成した設備
が2系列設置されている。First and second heat exchangers 4a, 4 for cooling seawater
In order to supply cooling seawater to the first and second seawater pumps 10a and 10b, first and second seawater pump discharge valves 15 are provided.
a, 15b installed seawater pump discharge piping 14a, 14b, 14
c is connected, the first and second heat exchangers 4a, 4b are connected via seawater supply pipes 11a, 11b, and the cooling seawater heat-exchanged in the first and second heat exchangers 4a, 4b is Water discharge pipes 12a and 12b are connected for discharge to the sea. In a seawater-based emergency auxiliary cooling seawater system, two lines of such equipment are installed.
【0027】第1および第2の海水供給配管11a,11b
同士を結ぶ連絡配管16には、第1の仕切弁13aと第2の
仕切弁13bが2個設置され、第1と第2の仕切弁13a,
13b間には、第3の海水ポンプ10cが接続された第3の
海水ポンプ吐出配管14cが分岐接続され、同様に海水ポ
ンプ吐出配管14には第3の海水ポンプ吐出弁15cが設置
されている。本実施の形態に係る原子力発電所の非常用
補機冷却設備では、このような構成の非常用補機冷却海
水系が図3に示したように3系統で構成している。First and second seawater supply pipes 11a, 11b
Two first gate valves 13a and two second gate valves 13b are installed in the connecting pipe 16 connecting the first and second gate valves 13a and 13a.
A third seawater pump discharge pipe 14c to which a third seawater pump 10c is connected is branched and connected between 13b. Similarly, a third seawater pump discharge valve 15c is installed in the seawater pump discharge pipe 14. . In the emergency accessory cooling system for a nuclear power plant according to the present embodiment, the emergency accessory cooling seawater system having such a configuration is configured by three systems as shown in FIG.
【0028】つぎに本実施の形態の作用を説明する。こ
のような構成からなる非常用補機冷却海水系において、
通常運転中に第1から第3の海水ポンプ10a,10b,10
cを3台保守点検する場合、およびその時原子炉事故が
発生した場合について系統の運転状態を説明する。Next, the operation of the present embodiment will be described. In the emergency auxiliary equipment cooling seawater system having such a configuration,
During normal operation, the first to third seawater pumps 10a, 10b, 10
The operation state of the system will be described for maintenance and inspection of three units c and when a reactor accident occurs at that time.
【0029】まず、第1の海水ポンプ10aを保守点検す
る場合、第1の海水ポンプ吐出弁15aを閉止して第1の
海水ポンプ10aを隔離するとともに、第1の仕切弁13a
開放,第2の仕切弁13b閉止とし、第3の海水ポンプ10
cは第3の海水ポンプ吐出配管14c,連絡配管16,第1
の海水供給配管11aを介して第1の熱交換器4aに冷却
海水を供給可能な状態とし、第2の海水ポンプ10bは第
2の海水ポンプ吐出配管14b,第2の海水供給配管11b
を介して第2の海水熱交換器4bに冷却海水を供給可能
な状態とする。First, when performing maintenance and inspection of the first seawater pump 10a, the first seawater pump discharge valve 15a is closed to isolate the first seawater pump 10a, and the first gate valve 13a.
Open the second gate valve 13b and close the third seawater pump 10
c is the third seawater pump discharge pipe 14c, connecting pipe 16,
The first sea exchanger 4a is supplied with cooling seawater via the seawater supply pipe 11a, and the second seawater pump 10b is connected to the second seawater pump discharge pipe 14b and the second seawater supply pipe 11b.
Through which the cooling seawater can be supplied to the second seawater heat exchanger 4b.
【0030】通常運転時においては第2および第3の海
水ポンプ10b,10cのうち何れか1台を運転して所要の
除熱を行う。なお、第1および第2の熱交換器4a,4
bで熱交換した冷却海水は第1および第2の海水放水配
管12a,12bを通して海に放水する。During normal operation, one of the second and third seawater pumps 10b and 10c is operated to perform required heat removal. The first and second heat exchangers 4a, 4
The cooling seawater heat-exchanged in step b is discharged into the sea through the first and second seawater discharge pipes 12a and 12b.
【0031】この時、原子炉事故が発生した場合、第2
の海水ポンプ10bは第2の熱交換器4bに、また、第3
の海水ポンプ10cは第1の熱交換器4aに冷却海水を供
給可能な状態となっているため、待機している第1また
は第2の海水ポンプ10bまたは10cの起動により事故時
の所要除熱量を除熱可能となる。At this time, if a nuclear reactor accident occurs,
Seawater pump 10b is connected to the second heat exchanger 4b and
Since the seawater pump 10c is in a state capable of supplying cooling seawater to the first heat exchanger 4a, the required heat removal amount at the time of the accident by the activation of the standby first or second seawater pump 10b or 10c. Can be removed.
【0032】次に第2の海水ポンプ10bを保守点検する
場合、第2の海水ポンプ吐出弁15bを閉止して第2の海
水ポンプ10bを隔離するとともに、第2の仕切弁13b開
放,第1の仕切弁13a閉止とし、第1の海水ポンプ10a
は第1の海水ポンプ吐出配管14a,第1の海水供給配管
11aを介して第1の熱交換器4aに冷却海水を供給可能
な状態とし、第3の海水ポンプ10cは第3の海水ポンプ
吐出配管14c,連絡配管16,第2の海水供給配管11bを
介して第2の熱交換器4bに冷却海水を供給可能な状態
とする。Next, when performing maintenance and inspection of the second seawater pump 10b, the second seawater pump discharge valve 15b is closed to isolate the second seawater pump 10b, the second gate valve 13b is opened, and the first seawater pump 10b is opened. The gate valve 13a is closed and the first seawater pump 10a is closed.
Is the first seawater pump discharge pipe 14a, the first seawater supply pipe
A state in which cooling seawater can be supplied to the first heat exchanger 4a via the first sea exchanger 11a is provided, and the third seawater pump 10c is connected via the third seawater pump discharge pipe 14c, the communication pipe 16, and the second seawater supply pipe 11b. To a state where cooling seawater can be supplied to the second heat exchanger 4b.
【0033】通常運転時においては第1および第3海水
ポンプ10a,10cのうち何れか1台を運転して所要の除
熱を行う。なお、第1および第2の熱交換器4a,4b
で熱交換した冷却海水は第1および第2の海水放水配管
12a,12bを介して海に放水する。During normal operation, one of the first and third seawater pumps 10a and 10c is operated to perform required heat removal. The first and second heat exchangers 4a, 4b
Cooling seawater heat-exchanged in the first and second seawater discharge pipes
Water is discharged into the sea via 12a and 12b.
【0034】この時、原子炉事故が発生した場合、海水
ポンプ10aは第1の熱交換器4aに、また、第3の海水
ポンプ10cは第2の熱交換器4bに冷却海水を供給可能
な状態となっているため、待機している第1または第3
の海水ポンプ10aまたは10cの起動により事故時の所要
除熱量を除熱可能となる。At this time, if a reactor accident occurs, the seawater pump 10a can supply cooling seawater to the first heat exchanger 4a, and the third seawater pump 10c can supply cooling seawater to the second heat exchanger 4b. The first or third waiting
By starting the seawater pump 10a or 10c, the required heat removal at the time of an accident can be removed.
【0035】最後に第3の海水ポンプ10cを保守点検す
る場合、第3の海水ポンプ吐出弁15cを閉止して第3の
海水ポンプ10cを隔離するとともに、第1および第2の
仕切弁13a,13b共に閉止とし、第1の海水ポンプ10a
は第1の海水ポンプ吐出配管14a,第1の海水供給配管
11aを介して第1の熱交換器4aに冷却海水を供給可能
な状態とし、第2の海水ポンプ10bは第2の海水ポンプ
吐出配管14b,第2の海水供給配管11bを介して第2の
熱交換器4bに冷却海水を供給可能な状態とする。Finally, when performing maintenance and inspection of the third seawater pump 10c, the third seawater pump discharge valve 15c is closed to isolate the third seawater pump 10c, and the first and second gate valves 13a, 13a. 13b is closed and the first seawater pump 10a
Is the first seawater pump discharge pipe 14a, the first seawater supply pipe
The first sea exchanger 4a can be supplied with cooling seawater via the first sea exchanger 11a, and the second seawater pump 10b is connected to the second seawater pump discharge pipe 14b and the second seawater supply pipe 11b via the second seawater supply pipe 11b. The cooling seawater can be supplied to the heat exchanger 4b.
【0036】通常運転時においては第1および第2の海
水ポンプ10a,10bのうち何れか1台を運転して所要の
除熱を行う。なお、第1および第2の熱交換器4a,4
bで熱交換した冷却海水は第1および第2の海水放水配
管12a,12bを介して海に放水する。During normal operation, one of the first and second seawater pumps 10a and 10b is operated to perform required heat removal. The first and second heat exchangers 4a, 4
The cooling seawater heat-exchanged in b is discharged to the sea via the first and second seawater discharge pipes 12a and 12b.
【0037】この時、原子炉事故が発生した場合、第1
の海水ポンプ10aは第1の熱交換器4aに、また、第2
の海水ポンプ10bは第2の熱交換器4bに冷却海水を供
給可能な状態となっているため、待機している第1また
は第2の海水ポンプ10aまたは10bの起動により事故時
の所要除熱量を除熱可能となる。At this time, if a nuclear reactor accident occurs, the first
Seawater pump 10a is connected to the first heat exchanger 4a and
Since the seawater pump 10b is in a state capable of supplying cooling seawater to the second heat exchanger 4b, the required heat removal amount at the time of the accident due to the activation of the standby first or second seawater pump 10a or 10b. Can be removed.
【0038】上記実施の形態において、第3の海水ポン
プ10cを含め、1系統当たり第1から第3の海水ポンプ
10a,10b,10c3台を定期的に切り替えて、前記3台
の海水ポンプを1台ずつ運転する切り替え系路を設ける
こともできる。In the above embodiment, the first to third seawater pumps per system including the third seawater pump 10c
It is also possible to provide a switching system for periodically switching the three units 10a, 10b and 10c and operating the three seawater pumps one by one.
【0039】また、1系統当たり第1から第3の海水ポ
ンプ10a,10b,10c3台のうち、何れか1台の海水ポ
ンプを保守点検している場合、残りの2台で原子炉事故
時における必要冷却海水量を確保できるように配管系路
を設けることもできる。When any one of the first to third seawater pumps 10a, 10b, and 10c per system is under maintenance and inspection, the remaining two pumps are used when a reactor accident occurs. A piping system can be provided so that the required amount of cooling seawater can be secured.
【0040】さらに、前記第1から第3の海水ポンプの
うち何れか1台ずつを運転機、待機機および予備機と
し、原子炉事故に伴う前記予備機起動の際、通常の前記
待機機が起動失敗した場合、前記予備機に起動信号を送
り起動させる電気回路を設けることもできる。Further, any one of the first to third seawater pumps is used as an operating unit, a standby unit and a standby unit, and when the standby unit is started due to a reactor accident, the normal standby unit is used. If the start-up fails, an electric circuit for sending a start-up signal to the standby unit and starting up may be provided.
【0041】通常運転中において第1から第3の海水ポ
ンプ10a,10b,10cの保守を実施していない場合、す
なわち1系統当たり第1から第3の海水ポンプ10a,10
b,10cの3台が運転可能な状態においては、1台が運
転機,1台が待機機,1台が予備機となる。When the maintenance of the first to third seawater pumps 10a, 10b, 10c is not carried out during the normal operation, that is, the first to third seawater pumps 10a, 10a, 10
In a state where three units b and 10c are operable, one unit is an operating unit, one unit is a standby unit, and one unit is a standby unit.
【0042】ここで、第1の海水ポンプ10aを運転機,
第2の海水ポンプ10bを待機機,第3の海水ポンプ10c
を予備機とすれば、原子炉事故が発生した場合、待機機
の第2の海水ポンプ10bに対して起動信号が送られる
が、起動失敗した場合、更に予備となっている第3の海
水ポンプ10cに対して待機機の第2の海水ポンプ10bの
起動失敗を検知して起動信号を送る電気回路を設けるこ
とにより、事故時に対しても1台の予備を有することと
なる。Here, the first seawater pump 10a is operated by an operating machine,
The second seawater pump 10b is used as a standby machine, and the third seawater pump 10c is used.
Is a standby unit, a start signal is sent to the second seawater pump 10b of the standby unit in the event of a nuclear reactor accident. By providing an electric circuit for detecting the failure of activation of the second seawater pump 10b of the stand-by unit for 10c and transmitting an activation signal, it is possible to have one spare even in the event of an accident.
【0043】しかして、上記実施の形態によれば、各系
統にそれぞれ海水ポンプ1台と付属する配管および弁を
設置することにより、通常運転中の海水ポンプの保守点
検が可能となるとともに、その時原子炉事故が発生して
も系統の機能を維持することができるとともに、海水ポ
ンプの予備が増えることにより信頼性の向上にも繋が
る。According to the above embodiment, by installing one seawater pump and associated piping and valves in each system, maintenance and inspection of the seawater pump during normal operation becomes possible. Even if a nuclear reactor accident occurs, the function of the system can be maintained, and more spare water pumps will lead to improved reliability.
【0044】[0044]
【発明の効果】本発明によれば、各系統にそれぞれ海水
ポンプ1台と付属する配管および弁を設置することによ
り通常運転中に海水ポンプの保守点検を行うことができ
る原子力発電所の補機冷却設備を提供することができ
る。According to the present invention, by installing a seawater pump and associated pipes and valves in each system, it is possible to perform maintenance and inspection of the seawater pump during normal operation. Cooling equipment can be provided.
【0045】これにより、海水ポンプの保守作業がプラ
ント定検時ではなく、通常運転中に実施できるため、定
検期間の短縮が可能となるとともに、海水ポンプの予備
が増えることにより信頼性の高い原子力発電所の非常用
補機冷却設備を提供することができる。As a result, the maintenance work of the seawater pump can be performed not during the regular inspection of the plant but during the normal operation, so that the period of the regular inspection can be shortened and the reliability of the seawater pump can be increased by increasing the number of spare water pumps. An emergency auxiliary equipment cooling system for a nuclear power plant can be provided.
【図1】本発明に係る原子力発電所の非常用補機冷却設
備の実施の形態を説明するための系統図。FIG. 1 is a system diagram for explaining an embodiment of an emergency accessory cooling system for a nuclear power plant according to the present invention.
【図2】従来の原子力発電所の非常用補機冷却設備を示
す系統図。FIG. 2 is a system diagram showing a conventional emergency auxiliary equipment cooling facility of a nuclear power plant.
【図3】図2における非常用補機冷却設備を3系統接続
した例を示す系統図。FIG. 3 is a system diagram showing an example in which three systems of emergency auxiliary equipment cooling equipment in FIG. 2 are connected.
【図4】図2における非常用補機冷却海水系の課題を説
明するための系統図。FIG. 4 is a system diagram for explaining the problem of the emergency auxiliary equipment cooling seawater system in FIG. 2;
1…冷却水供給配管、2…冷却水戻り配管、3…冷却水
ポンプ、4…熱交換器、4a…第1の熱交換器、4b…
第2の熱交換器、5…残留熱除去熱交換器、6…その他
の非常用機器、7…常用機器、8…弁、9…弁、10…海
水ポンプ、10a…第1の海水ポンプ、10b…第2の海水
ポンプ、10c…第3の海水ポンプ、11…海水供給配管、
12…放水配管、13…仕切弁、14…海水ポンプ吐出配管、
15…海水ポンプ吐出弁、16…連絡配管、17…切替弁装
置、18…タイライン。DESCRIPTION OF SYMBOLS 1 ... Cooling water supply piping, 2 ... Cooling water return piping, 3 ... Cooling water pump, 4 ... Heat exchanger, 4a ... First heat exchanger, 4b ...
Second heat exchanger, 5 ... Residual heat removal heat exchanger, 6 ... Other emergency equipment, 7 ... Service equipment, 8 ... Valve, 9 ... Valve, 10 ... Seawater pump, 10a ... First seawater pump, 10b: second seawater pump, 10c: third seawater pump, 11: seawater supply pipe,
12 ... water discharge pipe, 13 ... gate valve, 14 ... seawater pump discharge pipe,
15 ... seawater pump discharge valve, 16 ... connection piping, 17 ... switching valve device, 18 ... tie line.
Claims (4)
れた冷却水を冷却対象機器である残留熱除去熱交換器、
その他の非常用機器および常用機器へ供給する冷却水供
給配管と、前記残留熱除去熱交換器、その他の非常用機
器および常用機器で熱交換した冷却水を前記第1および
第2の熱交換器へ戻す冷却水戻り配管および前記冷却水
戻り配管に設けられた冷却水ポンプよりなる閉ループの
淡水系と、前記第1および第2の熱交換器にそれぞれ冷
却海水を供給する第1および第2の海水ポンプと第1お
よび海水供給配管と、この第1および第2の冷却海水供
給配管間に第1の仕切弁を配した連絡配管を接続し、前
記第1および第2の熱交換器で熱交換した冷却海水を海
に戻す第1および第2の放水配管からなる海水系で構成
する非常用補機冷却設備において、前記連絡配管間に第
1と第2の仕切弁を設置し、前記第1の仕切弁と第2の
仕切弁の間に第3の吐出配管を分岐接続し、この第3の
吐出配管に第3の海水ポンプを吐出弁を介して第3の海
水ポンプを接続してなることを特徴とする原子力発電所
の非常用補機冷却設備。A cooling water cooled by the first and second heat exchangers;
A cooling water supply pipe for supplying other emergency equipment and service equipment, and the first and second heat exchangers for the residual heat removal heat exchanger and the cooling water heat exchanged by the other emergency equipment and service equipment; And a closed loop freshwater system comprising a cooling water pump provided in the cooling water return pipe and the first and second heat exchangers for supplying cooling seawater to the first and second heat exchangers, respectively. A seawater pump, first and second seawater supply pipes, and a communication pipe having a first gate valve disposed between the first and second cooling seawater supply pipes are connected, and heat is supplied to the first and second heat exchangers. In an emergency auxiliary cooling system comprising a seawater system including first and second water discharge pipes for returning exchanged cooling seawater to the sea, first and second gate valves are installed between the communication pipes, The third valve between the first gate valve and the second gate valve An emergency auxiliary equipment cooling facility for a nuclear power plant, comprising a branch connection of a discharge pipe, and a third seawater pump connected to the third discharge pipe via a discharge valve. .
たり前記第1から第3の海水ポンプ3台を定期的に切り
替えて、前記3台の海水ポンプを1台ずつ運転する切り
替え系路を設けてなることを特徴とする請求項1記載の
原子力発電所の非常用補機冷却設備。2. A switching system for periodically switching the three first to third seawater pumps per system, including the third seawater pump, and operating the three seawater pumps one by one. 2. The emergency auxiliary equipment cooling system for a nuclear power plant according to claim 1, further comprising:
ンプ3台のうち、何れか1台の海水ポンプを保守点検し
ている場合、残りの2台で原子炉事故時における必要冷
却海水量を確保できるように配管系路を設けてなること
を特徴とする請求項1ないし2記載の原子力発電所の非
常用補機冷却設備。3. In the case where one of the first to third seawater pumps is maintained and inspected for each of the three seawater pumps, the required cooling seawater at the time of a reactor accident is used for the remaining two pumps. 3. An emergency auxiliary equipment cooling system for a nuclear power plant according to claim 1, wherein a piping system is provided so as to secure an amount.
れか1台ずつを運転機、待機機および予備機とし、原子
炉事故に伴う前記予備機起動の際、通常の前記待機機が
起動失敗した場合、前記予備機に起動信号を送り起動さ
せる電気回路を設けてなることを特徴とする請求項1な
いし3記載の原子力発電所の非常用補機冷却設備。4. One of the first to third seawater pumps is set as an operation unit, a standby unit and a standby unit, and when the standby unit is started in response to a nuclear reactor accident, the normal standby unit is used. 4. An emergency auxiliary equipment cooling system for a nuclear power plant according to claim 1, further comprising an electric circuit for sending a start signal to said standby unit when the start-up fails, and for starting said standby unit.
Priority Applications (1)
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JP9325532A JPH11160481A (en) | 1997-11-27 | 1997-11-27 | Emergency auxiliary cooling facility of nuclear power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
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JP9325532A JPH11160481A (en) | 1997-11-27 | 1997-11-27 | Emergency auxiliary cooling facility of nuclear power plant |
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Family
ID=18177936
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Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007033102A (en) * | 2005-07-25 | 2007-02-08 | Toshiba Corp | Modification method for emergency auxiliary machinery cooling system |
CN111933321A (en) * | 2020-07-17 | 2020-11-13 | 中核核电运行管理有限公司 | Heavy water reactor radioactive waste liquid discharge loop system and method |
-
1997
- 1997-11-27 JP JP9325532A patent/JPH11160481A/en active Pending
Cited By (3)
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---|---|---|---|---|
JP2007033102A (en) * | 2005-07-25 | 2007-02-08 | Toshiba Corp | Modification method for emergency auxiliary machinery cooling system |
CN111933321A (en) * | 2020-07-17 | 2020-11-13 | 中核核电运行管理有限公司 | Heavy water reactor radioactive waste liquid discharge loop system and method |
CN111933321B (en) * | 2020-07-17 | 2024-06-07 | 中核核电运行管理有限公司 | Heavy water pile radioactive waste liquid discharge loop system and method |
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