JPH05264774A - Emergency reactor cooling equipment - Google Patents
Emergency reactor cooling equipmentInfo
- Publication number
- JPH05264774A JPH05264774A JP4059865A JP5986592A JPH05264774A JP H05264774 A JPH05264774 A JP H05264774A JP 4059865 A JP4059865 A JP 4059865A JP 5986592 A JP5986592 A JP 5986592A JP H05264774 A JPH05264774 A JP H05264774A
- Authority
- JP
- Japan
- Prior art keywords
- emergency
- reactor
- cooling water
- cooling
- 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.)
- Pending
Links
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F02—COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
- F02B—INTERNAL-COMBUSTION PISTON ENGINES; COMBUSTION ENGINES IN GENERAL
- F02B3/00—Engines characterised by air compression and subsequent fuel addition
- F02B3/06—Engines characterised by air compression and subsequent fuel addition with compression ignition
-
- 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
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子炉の設計事象を超
える苛酷事故時に、非常用炉心冷却系の機能が喪失した
場合に於いても、原子炉圧力容器内へ冷却水を注水する
ことができる非常用原子炉冷却装置に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention is to inject cooling water into a reactor pressure vessel even when the function of the emergency core cooling system is lost during a severe accident that exceeds the design event of the reactor. The present invention relates to an emergency reactor cooling device capable of
【０００２】[0002]
【従来の技術】原子力発電プラントでは、原子炉施設の
故障又は破損に起因して燃料の溶融又は放射性物質の拡
散の抑制あるいは防止の為に、原子炉格納施設及び非常
用炉心冷却系から成る工学的安全施設が設けられてい
る。図３に非常用炉心冷却系の構成を示す。2. Description of the Related Art In a nuclear power plant, an engine consisting of a reactor containment facility and an emergency core cooling system is used to suppress or prevent the melting of fuel or the diffusion of radioactive materials due to the failure or damage of reactor facilities. Safety facilities are provided. Fig. 3 shows the configuration of the emergency core cooling system.
【０００３】その内、非常用炉心冷却系は、万一原子炉
圧力バウンダリの系統配管に、どの様な規模の破断また
は漏洩が生じた場合でも、炉心を十分に冷却し、燃料被
覆管の最高温度を許容値の1200℃以下に制限するよう
に、原子炉炉心から残留熱を除去する為に設けられてい
る。この非常用炉心冷却系は、高圧炉心スプレイ系33、
低圧炉心スプレイ系31、低圧注入系32および自動減圧系
37から機成されている。またこれらの系統は、安全設計
の指針より、動的機器の故障又は通常の所内電源がなく
とも起動又は運転ができるように多重性を持たせ、更に
ミサイル、ジェット力、パイプホイップ等による物理的
影響にも耐える様に物理的分離44を図っている。Among them, the emergency core cooling system sufficiently cools the core of the reactor pressure boundary in case of any scale breakage or leakage in the system piping of the reactor pressure boundary, and the maximum of the fuel cladding tube It is provided to remove residual heat from the reactor core so as to limit the temperature below the allowable value of 1200 ° C. This emergency core cooling system is a high pressure core spray system 33,
Low pressure core spray system 31, low pressure injection system 32 and automatic decompression system
Made from 37. In addition, from the safety design guideline, these systems should have multiplicity so that they can be started or operated even if there is no failure of dynamic equipment or normal on-site power supply.Furthermore, they are physically equipped with missiles, jet power, pipe whips, etc. Physical separation 44 is designed to withstand the effects.
【０００４】このためプラントの電源は、所内電源の他
に、非常用電源として、非常用ディーゼル発電機34，3
5，36が３台設置されている。低圧炉心スプレイ系31，
低圧注入系32は独立した２系統の電源母線及び非常用デ
ィーゼル発電機34，35に接続される。即ち低圧注水系32
に配置されたポンプ２台が１台のディーゼル発電機35
に、残りの低圧注水系32に配置されたポンプ１台と低圧
炉心スプレイ系31に配置されたポンプ１台がもう１台の
ディーゼル発電機34に、高圧炉心スプレイ系33に配置さ
れたポンプは、残りのディーゼル発電機36に接続され
る。また自動減圧系37は、蓄電池38の直流電源に接続さ
れている。Therefore, the power source of the plant is not only the on-site power source but also the emergency diesel generators 34, 3 as the emergency power source.
Three 5,36 are installed. Low pressure core spray system 31,
The low-pressure injection system 32 is connected to two independent power supply buses and emergency diesel generators 34 and 35. That is, low pressure water injection system 32
Diesel generator with 2 pumps located in 1
, One pump arranged in the remaining low-pressure water injection system 32 and one pump arranged in the low-pressure core spray system 31 are in the other diesel generator 34, and pumps arranged in the high-pressure core spray system 33 are , Connected to the remaining diesel generator 36. The automatic pressure reducing system 37 is connected to the DC power source of the storage battery 38.
【０００５】尚、工学的安全施設ではないが、事故時原
子炉水位を維持するために、原子炉蒸気抽気配管42を介
して原子炉蒸気の一部を用いてタービン41にて駆動され
るポンプを備え、所内電源喪失時、更に非常用交流電源
喪失時においても、長時間運転可能な様に原子炉隔離時
冷却系40が備えられている。Although it is not an engineering safety facility, in order to maintain the reactor water level during an accident, a pump driven by the turbine 41 using a part of the reactor steam through the reactor steam extraction pipe 42. In addition, the reactor isolation cooling system 40 is provided so as to be able to operate for a long time even when the power source in the plant is lost and further the emergency AC power source is lost.
【０００６】[0006]
【発明が解決しようとする課題】前記の様に、非常用炉
心冷却系は、安全設計の考え方により多重性を有してお
り、各系統は、作動試験、機能試験を定期的に実施し、
系統に要求される機能を充分発揮できることを確認して
いる。As described above, the emergency core cooling system has a multiplicity due to the concept of safety design, and each system regularly carries out an operation test and a function test.
It has been confirmed that the functions required for the grid can be fully demonstrated.
【０００７】しかしながら設計基準事象を超える事故に
際して全交流電源が喪失する可能性がある。これを全交
流電源喪失事故と称する。この全交流電源喪失事故は、
何らかの事故により、プラント内の交流電源が喪失し、
且つプラント内非常用ディーゼル発電機全台が起動失敗
し、全交流電源が喪失することをいう。この場合には、
電動機駆動に依存する非常用炉心冷却系は機能を喪失す
る。However, there is a possibility that all AC power supplies will be lost in the event of an accident that exceeds the design basis event. This is called an all AC power loss accident. This all AC power loss accident,
AC power in the plant was lost due to some accident,
Moreover, it means that all the emergency diesel generators in the plant have failed to start and all AC power is lost. In this case,
The emergency core cooling system, which relies on motor drive, loses function.
【０００８】但し、特定期間内であれば、プラントの交
流電源に依存せず作動可能な原子炉隔離時冷却系40があ
り炉心冷却は維持できる。しかしながら交流電源が復活
されない場合は、直流電源の枯渇により、原子炉隔離時
冷却系40は機能を喪失し、炉心冷却が不可能となり、炉
心損傷に到る可能性があるという課題がある。However, within the specific period, there is the reactor isolation cooling system 40 that can operate without depending on the AC power source of the plant, and core cooling can be maintained. However, if the AC power supply is not restored, the reactor isolation cooling system 40 loses its function due to exhaustion of the DC power supply, core cooling becomes impossible, and core damage may occur.
【０００９】本発明は上記の点を考慮してなされたもの
で、非常用炉心冷却系が使用不可となる全交流電源喪失
時においても、原子炉圧力容器内に冷却水を注入するこ
とができる非常時原子炉冷却装置を提供することを目的
としている。The present invention has been made in consideration of the above points, and it is possible to inject cooling water into the reactor pressure vessel even when all AC power supplies are lost, which renders the emergency core cooling system unusable. It is intended to provide an emergency reactor cooling device.
【００１０】[0010]
【課題を解決するための手段】上記目的を達成するため
に、本発明においては、原子炉非常時冷却用の冷却水量
を有し、かつ消火時に必要な冷却水量を貯蔵した貯留水
タンクと、原子炉内に配設された給水スパージャに一端
を接続した非常用炉心冷却水配管と、前記貯留水タンク
と消火設備とを接続する消火設備配管と、この消火設備
配管に介挿され前記貯留水タンクからの冷却水を加圧す
るポンプと、このポンプを駆動するディーゼル駆動機
と、このディーゼル駆動機を起動する蓄電池と、前記消
火設備配管と前記非常用炉心冷却水配管とを接続し原子
炉非常時に非常用炉心冷却水配管に貯留水タンクからの
冷却水を導く系統接続配管とから成ることを特徴とする
非常時原子炉冷却装置を提供する。In order to achieve the above object, in the present invention, there is provided a storage water tank having a cooling water amount for emergency cooling of a nuclear reactor and storing an amount of cooling water necessary for extinguishing a fire. An emergency core cooling water pipe having one end connected to a water supply sparger arranged in a nuclear reactor, a fire extinguisher pipe connecting the stored water tank and a fire extinguisher, and the stored water inserted in the fire extinguisher pipe A pump that pressurizes the cooling water from the tank, a diesel drive machine that drives this pump, a storage battery that starts this diesel drive machine, the fire extinguishing equipment piping and the emergency core cooling water piping are connected, and a reactor emergency There is provided an emergency reactor cooling device characterized by comprising a system connection pipe for guiding cooling water from a stored water tank to an emergency core cooling water pipe.
【００１１】[0011]
【作用】このように構成することにより、貯留水タンク
に、原子炉非常時冷却用の冷却水量かつ消火時に必要な
冷却水量が貯蔵される。この貯留水タンクと消火設備と
を接続している消化設備配管と、原子炉内の給水スパー
ジャに接続される非常用炉心冷却水配管とが、系統接続
配管にて連通されている。前記消火設備配管に介挿され
たポンプをディーゼル発電機にて駆動することにより貯
留水タンクからの冷却水を非常用炉心冷却水配管に導入
することができる。With this structure, the amount of cooling water for emergency cooling of the reactor and the amount of cooling water necessary for extinguishing the fire are stored in the stored water tank. A fire extinguishing equipment pipe that connects the stored water tank and the fire extinguishing equipment and an emergency core cooling water pipe that is connected to a feed water sparger in the reactor are connected by a system connecting pipe. By driving a pump inserted in the fire extinguishing equipment pipe with a diesel generator, the cooling water from the stored water tank can be introduced into the emergency core cooling water pipe.
【００１２】このため全交流電源が喪失し、非常用炉心
冷却系が使用不能な場合においても、専用の蓄電池から
ディーゼル駆動機を起動し、ディーゼル駆動ポンプによ
り冷却水を貯留水タンクから原子炉圧力容器及び原子炉
格納容器に冷却水を注水することができる。Therefore, even when all the AC power is lost and the emergency core cooling system cannot be used, the diesel drive machine is started from the dedicated storage battery and the cooling water is supplied from the reservoir tank to the cooling water by the diesel drive pump. Cooling water can be poured into the vessel and the containment vessel.
【００１３】[0013]
【実施例】以下、図面を参照して本発明の一実施例につ
いて説明する。図１は本発明による非常時原子炉冷却装
置の一実施例を示す系統図である。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 is a system diagram showing an embodiment of an emergency reactor cooling device according to the present invention.
【００１４】原子炉非常時冷却用の冷却水量を有しかつ
消火時に必要な冷却水量を貯蔵した貯蔵水タンク１が水
源として設置されている。一方原子炉圧力容器19には、
給水スパージャ18が内蔵され、原子炉格納容器15には、
スプレイヘッダ17が内蔵されている。このスプレイヘッ
ダ17と前記給水スパージャ18には非常用炉心冷却水配管
10が接続されている。前記貯留水タンク１から消火設備
26へは、消火設備配管２にて連結されている。この消火
設備配管２と前記非常用炉心冷却水配管10とを接続し、
原子炉非常時に非常用炉心冷却水配管10に貯留水タンク
１からの冷却水を導く系統接続配管６が接続されてい
る。A stored water tank 1 having a quantity of cooling water for emergency cooling of a nuclear reactor and storing a quantity of cooling water necessary for extinguishing a fire is installed as a water source. On the other hand, in the reactor pressure vessel 19,
The water supply sparger 18 is built in, and the reactor containment vessel 15
The spray header 17 is built in. The spray header 17 and the water supply sparger 18 have emergency core cooling water piping.
10 are connected. Fire extinguishing equipment from the stored water tank 1
Fire extinguishing equipment pipe 2 is connected to 26. This fire extinguishing equipment pipe 2 and the emergency core cooling water pipe 10 are connected,
A system connection pipe 6 for guiding the cooling water from the stored water tank 1 is connected to the emergency core cooling water pipe 10 in the event of a nuclear reactor emergency.
【００１５】前記消火設備配管２には、ポンプ３が介挿
され、前記貯留水タンク１からの冷却水が加圧される。
このポンプ３を駆動するため、ディーゼル駆動機４が設
置され、このディーゼル駆動機４を起動するための蓄電
池５が備えられている。この蓄電池５は通常時には所内
電源にて充電される。A pump 3 is inserted in the fire extinguishing equipment pipe 2 to pressurize the cooling water from the stored water tank 1.
In order to drive the pump 3, a diesel drive machine 4 is installed, and a storage battery 5 for starting the diesel drive machine 4 is provided. The storage battery 5 is normally charged by the on-site power supply.
【００１６】前記消火設備配管２には、ポンプ３をバイ
パスするバイパス配管９が連通されている。このバイパ
ス配管９には、ポンプ３起動時、逆流防止のために、逆
止弁８、仕切弁７が配置されている。A bypass pipe 9 for bypassing the pump 3 is connected to the fire extinguishing equipment pipe 2. A check valve 8 and a sluice valve 7 are arranged in the bypass pipe 9 to prevent backflow when the pump 3 is started.
【００１７】前記系統接続配管６には、隔離弁14，14が
介挿され、一方は原子炉圧力容器１９の給水スパージャ
１８に接続され、他方は原子炉格納容器15のスプレイヘ
ッダ17に接続されている。更にこの非常用冷却水配管10
は、原子炉圧力容器19の基礎である図示しないペデスタ
ル内を冷却するためにも使用される。Isolation valves 14 and 14 are inserted in the system connection pipe 6, one of which is connected to a water supply sparger 18 of a reactor pressure vessel 19 and the other of which is connected to a spray header 17 of a reactor containment vessel 15. ing. Furthermore, this emergency cooling water piping 10
Is also used to cool the pedestal (not shown) that is the basis of the reactor pressure vessel 19.
【００１８】前記原子炉圧力容器19の給水スパージャ18
には注水配管13が接続され、原子炉格納容器15のスプレ
イヘッダ17には注水配管12が接続されている。この注水
配管12，13には隔離機能を有する隔離弁11，16が介挿さ
れている。この給水スパージャ18には、原子炉圧力を速
かに低下させる自動減圧装置20が設置されている。次に
このような構成からなる本実施例の作用について説明す
る。通常運転時においては、各隔離弁11，14，16が全閉
とされている。ディーゼル駆動機４は停止している。Water supply sparger 18 of the reactor pressure vessel 19
Is connected to a water injection pipe 13, and the spray header 17 of the reactor containment vessel 15 is connected to a water injection pipe 12. Isolation valves 11 and 16 having an isolation function are inserted in the water injection pipes 12 and 13. The water supply sparger 18 is provided with an automatic decompression device 20 that rapidly reduces the reactor pressure. Next, the operation of this embodiment having such a configuration will be described. During normal operation, each isolation valve 11, 14, 16 is fully closed. The diesel drive unit 4 is stopped.
【００１９】全交流電源が喪失し、非常用炉心冷却系が
使用不能となったと仮定する。この場合隔離弁14を手動
により全開すると共に、ディーゼル駆動機３を蓄電池５
により起動させ、ポンプ３を運転する。このポンプ３に
より貯留水タンク１の冷却水を消化設備配管２、系統接
続配管６、非常用炉心冷却配管10を介して原子炉格納容
器15、原子炉圧力容器19内に注水する。Assume that the AC power supply is lost and the emergency core cooling system is disabled. In this case, the isolation valve 14 is fully opened manually and the diesel driver 3 is connected to the storage battery 5
And the pump 3 is operated. The pump 3 injects the cooling water of the stored water tank 1 into the reactor containment vessel 15 and the reactor pressure vessel 19 through the digestion equipment pipe 2, the system connection pipe 6, and the emergency core cooling pipe 10.
【００２０】また蓄電池５が何らかの故障でディーゼル
駆動機４が起動できない場合は、自動減圧装置20を手動
にて開放し、原子炉圧力を速かに減圧させ、貯留水タン
ク１の静水圧を利用し、バスパス配管９を介して原子炉
圧力容器19に注水も可能となる。When the diesel drive unit 4 cannot be started due to some failure of the storage battery 5, the automatic decompression device 20 is manually opened to rapidly reduce the reactor pressure, and the hydrostatic pressure of the stored water tank 1 is used. Then, it becomes possible to inject water into the reactor pressure vessel 19 via the bus path pipe 9.
【００２１】このように本実施例によれば、全交流電源
が喪失し、非常用炉心冷却系が使用不能な場合において
も、原子炉圧力容器又は原子炉格納容器内へ冷却水を供
給することができる。次に本発明の第２実施例を図２を
参照して説明する。なお図２において、図１と同一部分
については同一符号を付し、その部分の構成の説明は省
略する。As described above, according to this embodiment, even if all the AC power supplies are lost and the emergency core cooling system cannot be used, the cooling water is supplied into the reactor pressure vessel or the reactor containment vessel. You can Next, a second embodiment of the present invention will be described with reference to FIG. In FIG. 2, the same parts as those in FIG. 1 are designated by the same reference numerals, and the description of the structure of those parts will be omitted.
【００２２】この第２の実施例においては、第１の実施
例で使用した貯留水タンク１と原子炉建屋23内に設けた
非常用タンク25が併設された構成と成っている。この非
常用タンク25の出口配管27は、バイパス配管９の逆止弁
８の下流側に接続されている。この出口配管27にも逆止
弁28が介挿されている。前記非常用タンク25には、原子
炉建屋23より冷却水を補給が可能なようにホース接続口
21、止弁22を介して入口配管24が接続されている。In the second embodiment, the reservoir water tank 1 used in the first embodiment and the emergency tank 25 provided in the reactor building 23 are provided side by side. The outlet pipe 27 of the emergency tank 25 is connected to the bypass pipe 9 downstream of the check valve 8. A check valve 28 is also inserted in the outlet pipe 27. The emergency tank 25 has a hose connection port so that cooling water can be supplied from the reactor building 23.
An inlet pipe 24 is connected via a stop valve 21 and a stop valve 22.
【００２３】この第２の実施例によれば、非常用タンク
25は、貯留水タンク１より耐震設計において上位に分類
されている。このため全交流電源が規定の地震により喪
失したとしても、非常用タンク25は健在であり利用が可
能である。また原子炉建屋23外のホース接続口21を用い
ることにより、非常用タンク25の冷却水量を必要最少限
におさえることもできる。According to this second embodiment, the emergency tank
25 is ranked higher in the seismic design than the stored water tank 1. Therefore, even if all the AC power supplies are lost due to the specified earthquake, the emergency tank 25 is still alive and usable. Further, by using the hose connection port 21 outside the nuclear reactor building 23, the amount of cooling water in the emergency tank 25 can be suppressed to a necessary minimum.
【００２４】[0024]
【発明の効果】以上説明したように、本発明に係る非常
時原子炉冷却装置によれば、非常用炉心冷却系が使用不
能となる全交流電源喪失時においても、原子炉圧力容器
内に冷却水を注入することができ、安全性を格段に高め
ることができる。As described above, according to the emergency reactor cooling system of the present invention, even if the AC power supply is lost, the reactor pressure vessel is cooled even when the emergency core cooling system becomes unusable. Water can be injected, and safety can be greatly improved.
【図１】本発明の第１の実施例である非常時原子炉冷却
装置の構成を示す系統図。FIG. 1 is a system diagram showing a configuration of an emergency reactor cooling device according to a first embodiment of the present invention.
【図２】本発明の第２の実施例である非常時原子炉冷却
装置の構成を示す系統図。FIG. 2 is a system diagram showing a configuration of an emergency reactor cooling system according to a second embodiment of the present invention.
【図３】従来の非常用炉心冷却系の構成を示す系統図。FIG. 3 is a system diagram showing a configuration of a conventional emergency core cooling system.
１…貯留水タンク ２…消火設備配管 ３…ポンプ ４…ディーゼル駆動機 ５…蓄電池 ６…系統接続配管 10…非常用炉心冷却水配管 18…給水スパージャ 19…原子炉圧力容器 26…消火設備 25…非常用タンク 1 ... Reserved water tank 2 ... Fire extinguisher piping 3 ... Pump 4 ... Diesel drive machine 5 ... Storage battery 6 ... System connection piping 10 ... Emergency core cooling water piping 18 ... Water supply sparger 19 ... Reactor pressure vessel 26 ... Fire extinguishing equipment 25 ... Emergency tank
Claims (1)
つ消火時に必要な冷却水量を貯蔵した貯留水タンクと、
原子炉内に配設された給水スパージャに一端を接続した
非常用炉心冷却水配管と、前記貯留水タンクと消火設備
とを接続する消火設備配管と、この消火設備配管に介挿
され前記貯留水タンクからの冷却水を加圧するポンプ
と、このポンプを駆動するディーゼル駆動機と、このデ
ィーゼル駆動機を起動する蓄電池と、前記消火設備配管
と前記非常用炉心冷却水配管とを接続し原子炉非常時に
非常用炉心冷却水配管に貯留水タンクからの冷却水を導
く系統接続配管とから成ることを特徴とする非常時原子
炉冷却装置。1. A stored water tank having a cooling water amount for emergency cooling of a nuclear reactor and storing a cooling water amount necessary for extinguishing a fire,
An emergency core cooling water pipe having one end connected to a water supply sparger arranged in a nuclear reactor, a fire extinguisher pipe connecting the stored water tank and a fire extinguisher, and the stored water inserted in the fire extinguisher pipe A pump that pressurizes the cooling water from the tank, a diesel drive machine that drives this pump, a storage battery that starts this diesel drive machine, the fire extinguishing equipment piping and the emergency core cooling water piping are connected, and the reactor emergency An emergency reactor cooling device characterized by comprising a system connection pipe for guiding cooling water from a stored water tank to an emergency core cooling water pipe at times.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4059865A JPH05264774A (en) | 1992-03-17 | 1992-03-17 | Emergency reactor cooling equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4059865A JPH05264774A (en) | 1992-03-17 | 1992-03-17 | Emergency reactor cooling equipment |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05264774A true JPH05264774A (en) | 1993-10-12 |
Family
ID=13125499
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4059865A Pending JPH05264774A (en) | 1992-03-17 | 1992-03-17 | Emergency reactor cooling equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05264774A (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006283996A (en) * | 2005-03-31 | 2006-10-19 | Jfe Steel Kk | Cooling system of induction heating device |
| JP2008194118A (en) * | 2007-02-09 | 2008-08-28 | Chugoku Electric Power Co Inc:The | Power plant recovering air receiver drain trap by simple method |
| KR101241142B1 (en) * | 2011-09-09 | 2013-03-19 | 세화엠피(주) | Sea to fresh water system for reactor emergency cooling in nuclear power plant |
| KR101281351B1 (en) * | 2011-07-25 | 2013-07-02 | 한국수력원자력 주식회사 | Assistant DC Power Supplying Apparatus for Nuclear Power Plant and Method thereof |
| JP2014055951A (en) * | 2012-09-13 | 2014-03-27 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for alternate rpv energy removal path |
| JP2016027350A (en) * | 2015-11-02 | 2016-02-18 | 元浩 岡田 | Nuclear power plant system |
| JP2016045121A (en) * | 2014-08-25 | 2016-04-04 | 日立Ｇｅニュークリア・エナジー株式会社 | Boiling-water nuclear power plant |
-
1992
- 1992-03-17 JP JP4059865A patent/JPH05264774A/en active Pending
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006283996A (en) * | 2005-03-31 | 2006-10-19 | Jfe Steel Kk | Cooling system of induction heating device |
| JP2008194118A (en) * | 2007-02-09 | 2008-08-28 | Chugoku Electric Power Co Inc:The | Power plant recovering air receiver drain trap by simple method |
| KR101281351B1 (en) * | 2011-07-25 | 2013-07-02 | 한국수력원자력 주식회사 | Assistant DC Power Supplying Apparatus for Nuclear Power Plant and Method thereof |
| KR101241142B1 (en) * | 2011-09-09 | 2013-03-19 | 세화엠피(주) | Sea to fresh water system for reactor emergency cooling in nuclear power plant |
| JP2014055951A (en) * | 2012-09-13 | 2014-03-27 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for alternate rpv energy removal path |
| JP2016045121A (en) * | 2014-08-25 | 2016-04-04 | 日立Ｇｅニュークリア・エナジー株式会社 | Boiling-water nuclear power plant |
| US10446279B2 (en) | 2014-08-25 | 2019-10-15 | Hitachi-Ge Nuclear Energy, Ltd. | Boiling water type nuclear power plant |
| JP2016027350A (en) * | 2015-11-02 | 2016-02-18 | 元浩 岡田 | Nuclear power plant system |
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