JPS60218096A - Boiling water reactor coolant purification system equipment - Google Patents
Boiling water reactor coolant purification system equipmentInfo
- Publication number
- JPS60218096A JPS60218096A JP59075629A JP7562984A JPS60218096A JP S60218096 A JPS60218096 A JP S60218096A JP 59075629 A JP59075629 A JP 59075629A JP 7562984 A JP7562984 A JP 7562984A JP S60218096 A JPS60218096 A JP S60218096A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- coolant
- purification system
- system equipment
- circulation pump
- 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.)
- Granted
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
- Physical Or Chemical Processes And Apparatus (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明状、沸騰水型原子炉の冷却材浄化系設備、さらに
詳細には、原子炉が主蒸気タービン系から切シ離される
、いわゆる原子炉隔離事故発生に際し、原子炉炉内に非
常用冷却水を補給することのできる沸騰水型原子炉用冷
却材浄化系設備の改良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 coolant purification system equipment for a boiling water nuclear reactor, and more particularly to a so-called nuclear reactor in which a nuclear reactor is separated from a main steam turbine system. This invention relates to improvements to coolant purification system equipment for boiling water reactors that can supply emergency cooling water into the reactor in the event of an isolation accident. .
従来型(沸騰水型)原子炉の??岬材浄化系設備を第1
図に示す。Conventional (boiling water) nuclear reactor? ? First installation of Misaki wood purification system
As shown in the figure.
第1図において、原子炉1から吸込管2に取シ出された
冷却材は、再生熱交換器3および非再生熱交換器4によ
って所定温度(約50C)にまで冷却される。非再生熱
交換器4を通過した冷却材は、圧力調節弁5で所定圧力
(約7Kg/−・g)にまで減圧され、その後、ろ過器
6、脱塩器7に導かれて浄化される。ろ過器6、脱塩器
7によって浄化された冷却材は、循環ポンプ8によって
昇圧され、その後、吐出管9および給水管10を経て原
子炉1・内に戻される。なお、吐出管9の途中には、流
量調節弁11が設置され、ておシ、流量調節介11’に
よシ、本系統の流量が一定に制御される。また、原子炉
格納容器12の配管貫通部付近に位置して、吸込管2の
途中には路網容器隔離弁13および14が2個設置され
ている。図中、15は循環ポンプ8を駆動させる電動機
を示している。In FIG. 1, coolant taken out from a nuclear reactor 1 into a suction pipe 2 is cooled to a predetermined temperature (approximately 50 C) by a regenerative heat exchanger 3 and a non-regenerative heat exchanger 4. The coolant that has passed through the non-regenerative heat exchanger 4 is reduced to a predetermined pressure (approximately 7 kg/-.g) by a pressure control valve 5, and then guided to a filter 6 and a demineralizer 7 for purification. . The coolant purified by the filter 6 and the demineralizer 7 is pressurized by the circulation pump 8, and then returned to the reactor 1 through the discharge pipe 9 and the water supply pipe 10. A flow control valve 11 is installed in the middle of the discharge pipe 9, and the flow rate of this system is controlled to be constant by the flow control valve 11'. Further, two network vessel isolation valves 13 and 14 are installed in the middle of the suction pipe 2, located near the piping penetration portion of the reactor containment vessel 12. In the figure, 15 indicates an electric motor that drives the circulation pump 8.
以上の構成において、原子炉1から取り出された約70
Kg/m−gの冷却材は、脱塩器7部分で約3に9/−
・g程度の低運転圧力が得られるよう、圧力調節弁5に
よって大幅に減圧される。そして、その後、循環ポンプ
8によって再び約70Kg/crA・gKまで昇圧され
、原子炉1に戻される。In the above configuration, about 70
Kg/m-g of refrigerant is approximately 3 to 9/- in 7 parts of the demineralizer.
・The pressure is significantly reduced by the pressure control valve 5 so that a low operating pressure of about 100 g is obtained. Then, the pressure is increased again to about 70 kg/crA·gK by the circulation pump 8 and returned to the reactor 1.
なお、第1図には、上記した冷却材浄化系設備以外に、
原子炉隔離事故に際して原子炉1に非常用冷却水を補給
する、いわゆる原子炉隔離時冷却系設備も示されている
。原子炉−随時冷却系は、蒸気管16、蒸気加減弁17
、復水貯蔵タンク18、注、水管19、注水ポンプ20
および注水ポンプ駆動用タービン21によって構成され
ておシ、原子炉1が主蒸気タービン系から切シ離される
ような原子炉隔離事故が発生した場合、循環ポンプ8は
、格納容器隔離弁13.14の閉鎖信号によって強制的
にトリップ(OFF)させられる。すなわち、原子炉隔
離事故が発生し、原子炉1内の7水位が異常に低下する
ような事態が生じた場合はそれ以上の水位低下を防止す
べく、原子炉1から・・外部に流出する冷却材の全てに
ついて、各配管系の格納容器隔離弁を自動閉鎖する工夫
がなされているが、冷却材浄化系にあっては、図面に符
号13および14で示す格納容器隔離弁がこれに骸幽し
、格納容器隔離弁13.14は、原子炉1内の水位異常
低下信号によって自動的に閉鎖される。In addition to the above-mentioned coolant purification system equipment, Figure 1 also shows:
Also shown is a so-called reactor isolation cooling system facility that supplies emergency cooling water to the reactor 1 in the event of a reactor isolation accident. The reactor-occasional cooling system includes a steam pipe 16 and a steam control valve 17.
, condensate storage tank 18, water pipe 19, water injection pump 20
In the event of a reactor isolation accident in which the reactor 1 is separated from the main steam turbine system, the circulation pump 8 is configured by the containment vessel isolation valve 13. It is forcibly tripped (OFF) by the closing signal of. In other words, if a reactor isolation accident occurs and the water level inside the reactor 1 drops abnormally, the water will flow out of the reactor 1 to the outside in order to prevent the water level from dropping any further. For all coolant systems, measures have been taken to automatically close the containment vessel isolation valves of each piping system, but in the coolant purification system, the containment vessel isolation valves indicated by numerals 13 and 14 in the drawing are replaced by this system. The containment vessel isolation valves 13 and 14 are automatically closed by an abnormally low water level signal in the reactor 1.
上記のようにして、格納容器隔離弁13.14が閉鎖さ
れると、循環ポンプ8は、原子炉1からの吸込流路を断
たれることになるので、これら格納容器隔離弁13.1
4の閉鎖信号によって当該ポンプ8も強制的にトリップ
させられる。As described above, when the containment vessel isolation valves 13.14 are closed, the circulation pump 8 is cut off from the suction flow path from the reactor 1, so these containment vessel isolation valves 13.1
4, the pump 8 is also forced to trip.
また、循環ポンプ8の吸込圧力が異常に低下するような
事態発生に備えて、当該ポンプ8を保護する見地から、
循環ポンプ8自身の吸込圧力低下信号によっても、ポン
プ8は強制的にトリップさせられる。In addition, from the standpoint of protecting the circulation pump 8 in case the suction pressure of the circulation pump 8 abnormally decreases,
The pump 8 is also forcibly tripped by the suction pressure drop signal of the circulation pump 8 itself.
上記のようにして、循環ポンプ8が強制的にトリップさ
せられると、原子炉発生蒸気によシ、タービン21が駆
動される。タービ22↓が駆動されると、注水ポンプ2
0が起動し、復水貯蔵タン・り18内の貯留水を、注水
管19を介して原子炉1に補給するものであって、この
ようにして、原子炉1内の水位が一定に保たれる。When the circulation pump 8 is forcibly tripped as described above, the turbine 21 is driven by the reactor generated steam. When the turbine 22↓ is driven, the water injection pump 2
0 is started, and the water stored in the condensate storage tank 18 is supplied to the reactor 1 via the water injection pipe 19. In this way, the water level in the reactor 1 is maintained constant. drooping
しかして、上記した補給水配管系設備の注水ポンプ20
は、大気開放タンクである復水貯蔵タンク18内の貯留
水を原子炉1に注水するものであるから、その注水圧は
、既述した冷却材浄化系の゛吐出管9内を流れる冷却材
圧力と同様、約70に9/−・gKfで昇圧する必要が
あシ、その全揚程は、約800mと非常に大きくなるが
、上記した原子炉隔離時冷却系設備は、万一の原子炉隔
離事故を想定して設けられた非常用の設備でありつて、
原子炉通常運転時には全く使用されない。Therefore, the water injection pump 20 of the above-mentioned make-up water piping system equipment
Since this is for injecting water stored in the condensate storage tank 18, which is a tank open to the atmosphere, into the reactor 1, the water injection pressure is equal to that of the coolant flowing in the discharge pipe 9 of the coolant purification system described above. As with the pressure, it is necessary to increase the pressure by 9/- gKf to approximately 70, and the total lift is approximately 800 m, which is extremely large, but the above-mentioned reactor isolation cooling system equipment is It is an emergency facility set up in anticipation of an isolation accident.
It is not used at all during normal reactor operation.
本発明は、原子炉配管系の簡素化をはかるべく、種々検
討の結果なされたものであって、その目的とするところ
は、原子炉隔離事故発生に際し、原子炉炉内に非常用冷
却水を補給する機能を、冷却・材浄化系設備に併せ持た
せることによシ、従来独立系として存在していた原子炉
隔離時冷却系設備の布設を省略することができ、プラン
ト建設工程の簡略化と建設工費の節減化とを同時にはか
ることのできる、改良された沸騰水型原子炉用冷却材浄
化系設備を提供しようとするものである。The present invention was developed as a result of various studies in order to simplify the reactor piping system, and its purpose is to provide emergency cooling water within the reactor in the event of a reactor isolation accident. By combining the replenishment function with the cooling and material purification system equipment, it is possible to omit the installation of the reactor isolation cooling system equipment, which previously existed as an independent system, simplifying the plant construction process. The purpose of the present invention is to provide improved coolant purification system equipment for boiling water reactors, which can simultaneously reduce construction costs.
上記目的を達成するため、本発明は、原子炉から取シ出
した冷却材を熱交換器で冷却し、ろ過脱塩器で浄化した
後、循環ポンプで昇圧して再度原子炉に戻す構造の沸騰
水型原子炉用冷却材浄化系設備において、上記循環ポン
プの冷却材吸込側に、原子炉隔離時当該原子炉炉内に冷
却水を補給する補給水配管系を接続してなることを特徴
とするものである。In order to achieve the above object, the present invention has a structure in which the coolant taken out from the nuclear reactor is cooled by a heat exchanger, purified by a filtration demineralizer, and then pressurized by a circulation pump and returned to the reactor again. Coolant purification system equipment for a boiling water reactor, characterized in that a make-up water piping system for replenishing cooling water into the reactor during reactor isolation is connected to the coolant suction side of the circulation pump. That is.
、五ご工::::−;:::J:::::炉用冷却材浄
化系設備の一実施例を示す配管系統説明図で、第1図と
同一符号は同一部分、22は循環ポンプ8の冷却材吸込
側と復水貯蔵タンク18との間を接続した非常用冷却水
注水管を示し、注水管22の途中には、逆止弁タイプの
注水弁23が設置されているものであって、上記注水弁
23の上流側、すなわち復水貯蔵タンク1B側には、常
時復水貯蔵タンク18側からの押込圧力(約2.5Kg
/cr/I−g)が加わっている。一方、注水弁23の
下流側の圧力、すなわち循環ポンプ8の吸込圧力は、圧
力調節弁5の働きによシ、通常的3Kf/−・gの圧力
に制御されている。したがって、注水弁23の上流側と
下流側との圧力差から、原子炉通常運転中、循環ポンプ
8の吸込源は、常に原子炉1側を選択し、復水貯蔵タン
ク18側から冷却水を吸い込むようなことはない。, Gogoko::::-;:::J:::::: This is a piping system explanatory diagram showing an example of furnace coolant purification system equipment, where the same reference numerals as in Figure 1 indicate the same parts, and 22 indicates An emergency cooling water injection pipe is shown that connects the coolant suction side of the circulation pump 8 and the condensate storage tank 18, and a check valve type water injection valve 23 is installed in the middle of the water injection pipe 22. The upstream side of the water injection valve 23, that is, the condensate storage tank 1B side, is constantly under pressure (approximately 2.5 kg) from the condensate storage tank 18 side.
/cr/I-g) has been added. On the other hand, the pressure on the downstream side of the water injection valve 23, that is, the suction pressure of the circulation pump 8, is controlled to a normal pressure of 3 Kf/-.g by the action of the pressure regulating valve 5. Therefore, due to the pressure difference between the upstream and downstream sides of the water injection valve 23, during normal reactor operation, the suction source of the circulation pump 8 always selects the reactor 1 side, and coolant is supplied from the condensate storage tank 18 side. There is no such thing as inhalation.
これに対し、原子炉隔離事故が発生し、格納容器隔離弁
13.14が自動閉鎖された場合は、従来と異なって循
環ポンプ8をトリップすることなく、そのまま循環ポン
プ8の運転を継続すると、原子炉1との間の流路を断た
れた循環ポンプ8の吸込圧力は、尚初の圧力(約3Kf
/−・g)から徐々に低下し始める。そして、循環ポン
プ8の吸込圧力が、非常用冷却水注水管22の注水弁2
3に加えられている押込圧力(復水貯蔵タンク18側か
ら加えられている約Z5Kf/−・gの押込圧力)よシ
も低下すると、循環ポンプ8の吸込源は、原子炉1側か
ら復水貯蔵タンク18側に自動的に切シ替シ、循環ポン
プ8は、注水管22を介して復水貯蔵タンク18からの
冷却水を吸い込み、原子炉1に冷却水を補給することが
できる。On the other hand, if a reactor isolation accident occurs and the containment vessel isolation valves 13 and 14 are automatically closed, unlike conventional methods, if the circulation pump 8 continues to operate without tripping, The suction pressure of the circulation pump 8 whose flow path with the reactor 1 was cut off is still the original pressure (approximately 3Kf).
/-・g) begins to gradually decrease. Then, the suction pressure of the circulation pump 8 is adjusted to the water injection valve 2 of the emergency cooling water injection pipe 22.
When the indentation pressure applied to 3 (approximately Z5Kf/-.g indentation pressure applied from the condensate storage tank 18 side) also decreases, the suction source of the circulation pump 8 is drawn from the condensate from the reactor 1 side. Automatically switching to the water storage tank 18 side, the circulation pump 8 can suck in cooling water from the condensate storage tank 18 through the water injection pipe 22 and replenish the reactor 1 with cooling water.
第3図に本発明の他の実施例を示す。FIG. 3 shows another embodiment of the invention.
第3図の実施例においては、循環ポンプ8の駆動源を、
原子炉発生蒸気によって駆動されるタービン24とした
場合について例示したものであって、この構成によれば
、電気系統が故障した場合であってき、原子炉発生蒸気
を利用して循環ポンプ8を駆動することができ、ポンプ
駆動源の多様化をはかる−ことができる。In the embodiment shown in FIG. 3, the driving source of the circulation pump 8 is
This is an example of the case where the turbine 24 is driven by reactor generated steam. According to this configuration, when the electrical system fails, the circulation pump 8 is driven using the reactor generated steam. This makes it possible to diversify pump drive sources.
第4図に本発明のさらに他の実施例を示す。FIG. 4 shows still another embodiment of the present invention.
第4図の実施例においては、循環ポンプの駆動源をディ
ーゼル機関25とした場合について例示したものであっ
て、この構成によれば、第3図の実施例と同様、電気系
統が故障した場合であっても、ディーゼル機関25を利
用して循環ポンプ8を駆動することができ、これまたポ
ンプ駆動源の多様化をはかることができる。In the embodiment shown in FIG. 4, a case is illustrated in which the driving source of the circulation pump is a diesel engine 25. According to this configuration, as in the embodiment shown in FIG. Even in this case, the circulation pump 8 can be driven using the diesel engine 25, and the pump driving source can also be diversified.
〔発明の効果〕
以上詳述したように、本発明によれば、原子炉隔離事故
発生に際し、原子炉炉内に非常用冷却水を補給する機能
を、冷却材浄化系設備に併せ持たせることにより、従来
独立系として存在していた原子炉隔離時冷却系設備の布
設を省略することができ、プラント建設工程の簡略化と
建設工費の節減化とを同時にはかることのできる、改良
された沸騰水型原子炉用冷却材浄化系設備を得ることが
できる。[Effects of the Invention] As detailed above, according to the present invention, the coolant purification system equipment can also have the function of replenishing emergency cooling water into the reactor in the event of a reactor isolation accident. The improved boiling system eliminates the need to install the reactor isolation cooling system, which previously existed as an independent system, and simultaneously simplifies the plant construction process and reduces construction costs. Coolant purification system equipment for water reactors can be obtained.
第1図は従来型(沸騰水型)原子炉の冷却材浄化系設備
とL子炉隔離時冷却系設備との配管系統説明図、第2図
は本発明に係る沸騰水型原子炉用冷却材浄化系設備の一
実施例を示す配管系統説明図、第3図は本発明の他の実
施例を示す冷却材浄化系設備の配管系統説明図、第4図
は本発明のさらに他の実施例を示す冷却材浄化系設備の
配管系統説明図である。
1・・・原子炉、2・・・吸込管、3・・・再生熱交換
器、4・・・非再生熱交換器、5・・・圧力調節弁、6
・・・ろ過器、7・・・脱塩器、8・・・循環ボ、ンプ
、9・・・吐出管、10・・・給水管、11・・・流量
調節弁、12・・・原子炉格納容器、13および14・
・・格納容器隔離弁、15・・・電動機、22・・・非
常用冷却水注水管、23・・・注水弁、24・・・ター
ビン、25・・・ディーゼル機関。
代理人 弁理士 長崎博男
(ほか1名)
$l 目
第 2 固
$J12]
第4 口Fig. 1 is an explanatory diagram of the piping system of the coolant purification system equipment and L reactor isolation cooling system equipment of a conventional (boiling water type) nuclear reactor, and Fig. 2 is a cooling system for boiling water reactors according to the present invention. Fig. 3 is an explanatory diagram of a piping system showing one embodiment of the material purification system equipment, Fig. 3 is an explanatory diagram of the piping system of the coolant purification system equipment showing another embodiment of the present invention, and Fig. 4 is an explanatory diagram of the piping system of the coolant purification system equipment showing another embodiment of the present invention. It is an explanatory diagram of a piping system of a coolant purification system equipment showing an example. DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 2... Suction pipe, 3... Regenerative heat exchanger, 4... Non-regenerative heat exchanger, 5... Pressure control valve, 6
...Filter, 7...Demineralizer, 8...Circulation pump, 9...Discharge pipe, 10...Water supply pipe, 11...Flow rate control valve, 12...Atom Reactor containment vessel, 13 and 14・
...Containment vessel isolation valve, 15...Electric motor, 22...Emergency cooling water injection pipe, 23...Water injection valve, 24...Turbine, 25...Diesel engine. Agent Patent attorney Hiroo Nagasaki (and 1 other person) $l 2nd firm $J12] 4th mouth
Claims (1)
、ろ過脱塩器で浄化した後、循環ポンプで昇圧して再度
原子炉に戻す構造の沸騰水型原子炉用冷却材浄化系設備
において、上記循環ポンプの冷却材吸込側に、原子炉隔
離時当骸原子炉炉内に冷却水を補給する補給水配管系を
接続してなることを特徴とする沸騰水型原子炉の冷却材
浄化系設備。 2、特許請求の範囲第1項記載の発明において、循環水
・プの駆動源を、原子炉発竺蒸気によって駆動されるタ
ービンとした沸騰水型原子炉の冷却材浄化系設備。 3、特許請求の範囲第1項記載の発明において、循環ポ
ンプの駆動源をディーゼル機関とした沸騰水型原子炉の
冷却材浄化系設備。[Claims] 10. Coolant purification system equipment for boiling water reactors that has a structure in which the coolant taken out of the reactor is cooled with a heat exchanger, purified with a filtration demineralizer, then boosted with a circulation pump and returned to the reactor again. A coolant for a boiling water reactor, characterized in that a make-up water piping system for replenishing cooling water into the nuclear reactor during reactor isolation is connected to the coolant suction side of the circulation pump. Purification system equipment. 2. Coolant purification system equipment for a boiling water reactor, in which the driving source for the circulating water is a turbine driven by reactor steam. 3. Coolant purification system equipment for a boiling water nuclear reactor in which a diesel engine is used as a driving source for a circulation pump in the invention set forth in claim 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59075629A JPS60218096A (en) | 1984-04-13 | 1984-04-13 | Boiling water reactor coolant purification system equipment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59075629A JPS60218096A (en) | 1984-04-13 | 1984-04-13 | Boiling water reactor coolant purification system equipment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60218096A true JPS60218096A (en) | 1985-10-31 |
| JPH0454915B2 JPH0454915B2 (en) | 1992-09-01 |
Family
ID=13581721
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59075629A Granted JPS60218096A (en) | 1984-04-13 | 1984-04-13 | Boiling water reactor coolant purification system equipment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60218096A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011107001A (en) * | 2009-11-19 | 2011-06-02 | Hitachi-Ge Nuclear Energy Ltd | Emergency core cooling system |
-
1984
- 1984-04-13 JP JP59075629A patent/JPS60218096A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011107001A (en) * | 2009-11-19 | 2011-06-02 | Hitachi-Ge Nuclear Energy Ltd | Emergency core cooling system |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0454915B2 (en) | 1992-09-01 |
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