JPH0721549B2 - Water quality control system for reactor water supply / water supply system - Google Patents
Water quality control system for reactor water supply / water supply systemInfo
- Publication number
- JPH0721549B2 JPH0721549B2 JP62254752A JP25475287A JPH0721549B2 JP H0721549 B2 JPH0721549 B2 JP H0721549B2 JP 62254752 A JP62254752 A JP 62254752A JP 25475287 A JP25475287 A JP 25475287A JP H0721549 B2 JPH0721549 B2 JP H0721549B2
- Authority
- JP
- Japan
- Prior art keywords
- water
- clad
- reactor
- feed water
- water supply
- 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
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
-
- 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
Description
【発明の詳細な説明】 〔発明の目的〕 （産業上の利用分野） この発明は、原子炉復・給水系の水質制御装置に係り、
特に給水のFe濃度を最適に制御することによって炉水中
のイオン放射能濃度を低減させる原子炉復・給水系の水
質制御装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) [0001] The present invention relates to a water quality control device for a reactor recuperation / water supply system,
In particular, the present invention relates to a water quality control device for a reactor recuperation / feed water system that reduces the ion radioactivity concentration in reactor water by optimally controlling the Fe concentration in the feed water.
（従来の技術） 沸騰水型原子炉（BWR）が適用された原子力発電プラン
トでは、原子炉からの蒸気はタービンに供給され、この
タービンで仕事をした後復水器内で復水となる。この復
水は復水ろ過器および復水脱塩器によって順次浄化され
た後、給水加熱器で加熱され、原子炉に導かれる。(Prior Art) In a nuclear power plant to which a boiling water reactor (BWR) is applied, steam from the nuclear reactor is supplied to a turbine, and after doing work in this turbine, it is condensed in a condenser. This condensate is purified by a condensate filter and a condensate demineralizer in sequence, then heated by a feed water heater, and guided to a nuclear reactor.
このように、従来の原子炉復・給水系においては、復水
ろ過器および復水脱塩器により、給水から鉄を主成分と
するクラッドが除去される。そして、従来は、給水中の
クラッドが少ないほど放射能が少なくなるとの観点か
ら、給水中のクラッドをできる限り少なくするよう考慮
されていた。As described above, in the conventional reactor condensate / feed water system, the condensate filter and the condensate demineralizer remove the clad containing iron as the main component from the feed water. Then, conventionally, from the viewpoint that the less the clad in the water supply is, the less the radioactivity is, it has been considered to reduce the clad in the water supply as much as possible.
（発明が解決しようとする問題点） しかしながら、Ni合金製配管が多用された近年の原子力
発電プラントでは、給水中のクラッドを極端に減少させ
ると、鉄によるイオン放射能（60Co2+）の吸着除去効果
等が低下して、炉水中のイオン放射能濃度が上昇してし
まう。その結果、原子炉内または再循環系統内等にイオ
ン放射能が蓄積し、原子炉等の点検作業時に、作業員が
被曝するおそれがある。そして、この被曝を回避するた
めに、メンテナンスコストが上昇してしまう。(Problems to be solved by the invention) However, in a recent nuclear power plant in which Ni alloy piping is heavily used, when the clad in the feed water is extremely reduced, the ion radioactivity ( 60 Co 2+ ) due to iron is increased. The adsorptive removal effect will decrease, and the ion radioactivity concentration in the reactor water will increase. As a result, ion radioactivity may accumulate in the nuclear reactor or the recirculation system, etc., and workers may be exposed to radiation during inspection work on the nuclear reactor. Then, in order to avoid this exposure, the maintenance cost will increase.
この発明は、上記事実を考慮してなされたものであり、
原子炉内等におけるイオン放射能の蓄積量を減少させ
て、原子炉等の点検作業時における作業員の被曝を低減
することができる原子炉復・給水系の水質制御装置を提
供することを目的とする。The present invention has been made in consideration of the above facts,
An object of the present invention is to provide a water quality control device for a reactor water supply / water supply system that can reduce the amount of ion radioactivity accumulated in a nuclear reactor, etc., and reduce the exposure of workers during inspection work on the nuclear reactor, etc. And
（問題点を解決するための手段） この発明は、原子力発電プラントの復水ろ過器に中空糸
膜フィルタが適用された原子炉復・給水系の給水の水質
を制御する原子炉復・給水系の水質制御装置において、
上記復水ろ過器の逆洗水受タンクに連結されて逆洗水中
に含まれるクラッドを貯蔵するクラッド貯蔵タンクと、
高圧給水ポンプの下流側に設けられて給水中のFe・Ni比
を検出する水質検出器と、この検出器に接続され、Fe・
Ni比が所定値以下になったときに上記クラッド貯蔵タン
ク中のクラッドを給水中に混入させるコントローラとを
有して構成されたものである。(Means for Solving Problems) The present invention relates to a reactor condensate / water supply system for controlling the water quality of the reactor condensate / water supply system in which a hollow fiber membrane filter is applied to a condensate filter of a nuclear power plant. In the water quality control device of
A clad storage tank connected to the backwash water receiving tank of the condensate filter to store the clad contained in the backwash water,
A water quality detector that is installed on the downstream side of the high-pressure water supply pump and detects the Fe / Ni ratio in the feed water, and is connected to this detector.
And a controller that mixes the clad in the clad storage tank with the feed water when the Ni ratio falls below a predetermined value.
（作用） したがって、この発明に係る原子炉復・給水系の水質制
御装置は、逆洗水受タンクに含まれるクラッドを原子炉
へ供給される給水中に混入させることにより、Fe・Ni比
を所定値以上に維持して鉄によるイオン放射能の吸着効
果を促進させ、炉水中のイオン放射能濃度を低減させる
ものである。(Operation) Therefore, the water quality control device of the reactor recuperation / feed water system according to the present invention can reduce the Fe / Ni ratio by mixing the clad contained in the backwash water receiving tank into the feed water supplied to the reactor. It is maintained above a predetermined value to promote the adsorption effect of iron ion activity by iron and reduce the ion activity concentration in the reactor water.
（実施例） 以下、この発明の実施例を図面に基づいて説明する。Embodiment An embodiment of the present invention will be described below with reference to the drawings.
第１図はこの発明に係る原子炉復・給水系の水質制御装
置が適用された原子炉復・給水系を示す系統図である。FIG. 1 is a system diagram showing a reactor return / water supply system to which a water quality control device for a reactor return / water supply system according to the present invention is applied.
原子炉１で発生した蒸気は、高圧タービン３および低圧
タービン５へ順次供給され、これらのタービン3,5で仕
事をする。その後、蒸気は、復水器７で復水となる。復
水は、復水ポンプ９によって、復水ろ過器11および腹水
脱塩器13へ順次供給されて浄化される。浄化された復水
は、低圧給水ポンプ15へ導かれて給水となり、給水加熱
器17で加熱された後高圧給水ポンプ19へ導かれる。給水
は、高圧給水ポンプ19で昇圧されて原子炉１へ供給され
る。The steam generated in the nuclear reactor 1 is sequentially supplied to the high pressure turbine 3 and the low pressure turbine 5, and the turbines 3 and 5 work. After that, the steam becomes condensed water in the condenser 7. The condensate is sequentially supplied to the condensate filter 11 and the ascites demineralizer 13 by the condensate pump 9 to be purified. The purified condensate is guided to the low-pressure feed pump 15 to become feed water, heated by the feed heater 17, and then introduced to the high-pressure feed pump 19. The water supply is pressurized by the high-pressure water supply pump 19 and supplied to the reactor 1.
上記復水ろ過器11は、中空糸膜フィルタをろ過装置とし
て採用したものである。この復水ろ過器により、復水中
の鉄を主成分とするクラッドが好適に除去され、復水は
ほとんど純水に近い状態となる。また、復水ろ過器11に
は逆洗水受タンク21が接続され、復水ろ過器11の逆洗後
の逆洗水が貯留される。この逆洗水中には多量のクラッ
ドが含まれる。したがって、逆洗水受タンク21に貯留さ
れた逆洗水の殆どは、廃液処理系に導かれて処理され
る。The condensate filter 11 employs a hollow fiber membrane filter as a filtering device. By this condensate filter, the clad containing iron as the main component in the condensate is preferably removed, and the condensate becomes almost like pure water. Further, a backwash water receiving tank 21 is connected to the condensate filter 11, and the backwash water after backwashing the condensate filter 11 is stored. This backwash water contains a large amount of clad. Therefore, most of the backwash water stored in the backwash water receiving tank 21 is guided to the waste liquid treatment system for treatment.
上述のような原子炉復・給水系に水質制御装置23が設置
される。この水質制御装置23はクラッド貯蔵タンク25、
クラッド導入系27、水質検出器29およびコントローラ31
を有して構成される。The water quality control device 23 is installed in the reactor water supply / water supply system as described above. This water quality control device 23 is a clad storage tank 25,
Cladding introduction system 27, water quality detector 29 and controller 31
Is configured.
クラッド貯蔵タンク25は、逆洗水受タンク21に連結され
て、逆洗水中に含まれるクラッドを貯蔵する。また、ク
ラッド導入系27はクラッド貯蔵タンク25に連結され、他
端が低圧給水ポンプ15および給水加熱器17間の給水配管
に接続される。このクラッド導入系27には、クラッド貯
蔵タンク25の側から順次クラッド供給ポンプ33およびク
ラッド供給弁35が配設されて、クラッド貯蔵タンク25中
のクラッドを給水中に混入可能とする。The clad storage tank 25 is connected to the backwash water receiving tank 21 and stores the clad contained in the backwash water. The clad introducing system 27 is connected to the clad storage tank 25, and the other end is connected to a water supply pipe between the low-pressure water supply pump 15 and the water supply heater 17. In the clad introducing system 27, a clad supply pump 33 and a clad supply valve 35 are sequentially arranged from the side of the clad storage tank 25 so that the clad in the clad storage tank 25 can be mixed into the feed water.
水質検出器29は、原子炉復・給水系の高圧給水ポンプ19
の下流側に設けられる。またこの水質検出器29は、濁度
計37、イオンクロマト計38および処理部39から構成され
る。濁度計37は、原子炉１へ供給される給水中のクラッ
ド濃度を測定し、このクラッド濃度からFe濃度を検出す
る。イオンクロマト計38は、原子炉１へ供給される給水
中のNi濃度を検出する。処理部39は、濁度計37およびイ
オンクロマト計38からのFe濃度およびNi濃度からFe・Ni
比（Fe/Ni）を算出し、その算出値をコントローラ31へ
出力する。The water quality detector 29 is a high-pressure water supply pump 19 for the reactor return / water supply system.
Is provided on the downstream side of. The water quality detector 29 is composed of a turbidimeter 37, an ion chromatograph 38, and a processing unit 39. The turbidity meter 37 measures the clad concentration in the feed water supplied to the reactor 1, and detects the Fe concentration from this clad concentration. The ion chromatograph 38 detects the Ni concentration in the feed water supplied to the reactor 1. The processing unit 39 uses the Fe concentration and the Ni concentration from the turbidimeter 37 and the ion chromatograph 38 to determine the Fe.
The ratio (Fe / Ni) is calculated, and the calculated value is output to the controller 31.
コントローラ31は、水質検出器29の処理部39に電気的に
接続されるとともに、クラッド導入系27のクラッド供給
ポンプ33およびクラッド供給弁35にも同様に接続され
る。そして、このコントローラ31は、処理部39にて算出
されたFe/Niが所定値（例えば約５。この値はプラント
運転歴によって変わる。）以下のときに、クラッド供給
弁35へ開信号を出力し、クラッド供給ポンプ33へ起動信
号を出力して、クラッド貯蔵タンク25中のクラッドを給
水中に混入させるよう設けられる。また、この場合、ク
ラッドは一点鎖線で示すように、給水を経ずに直接原子
炉１に供給されても良い。クラッド供給弁35の弁開度
は、処理部39にて算出されたFe/Niの値とFe/Niの所定値
との差に基づいて調整される。The controller 31 is electrically connected to the processing unit 39 of the water quality detector 29, and is also connected to the clad supply pump 33 and the clad supply valve 35 of the clad introduction system 27 in the same manner. Then, the controller 31 outputs an open signal to the clad supply valve 35 when the Fe / Ni calculated by the processing unit 39 is below a predetermined value (for example, about 5; this value changes depending on the plant operation history). Then, a start signal is output to the clad supply pump 33 so that the clad in the clad storage tank 25 is mixed into the water supply. Further, in this case, the clad may be directly supplied to the nuclear reactor 1 without water supply, as indicated by a chain line. The valve opening of the clad supply valve 35 is adjusted based on the difference between the value of Fe / Ni calculated by the processing unit 39 and the predetermined value of Fe / Ni.
上述のようにFe/Niを所定値以上に維持するのは次の理
由による。給水中のFe/Niと炉水中のイオン放射能（60C
o2+）濃度との関係は、例えば運転初期には第２図に示
すように、Fe/Niが約５よりも低い領域では炉水中のイ
オン放射性濃度が高いが、給水中のFe/Niが約５以上の
ときは炉水柱のイオン放射性濃度が著しく低くなる。そ
こで、給水中のFe/Niを約５以上に維持して、炉水中の
イオン放射性濃度を低く抑えるためである。The reason why Fe / Ni is maintained above a predetermined value as described above is as follows. Fe / Ni in feed water and ion radioactivity in reactor water ( 60 C
o 2+ ) concentration, for example, in the initial stage of operation, as shown in Fig. 2, the ion radioactivity concentration in the reactor water is high in the region where Fe / Ni is lower than about 5, but the Fe / Ni concentration in the feed water is high. When the value is about 5 or more, the ion radioactivity concentration in the reactor water column becomes extremely low. Therefore, the Fe / Ni content in the feed water is maintained at about 5 or more to keep the ion radioactive concentration in the reactor water low.
次に、作用効果を説明する。Next, the function and effect will be described.
原子炉１へ供給される給水のFe/Niが水質検出器29によ
って所定値以下であると検出されたときに、コントロー
ラ31はクラッド導入系27を介して、クラッド貯蔵タンク
25からのクラッドを給水中へ混入する。これにより給水
中のFe濃度が上昇し、給水中のFe/Niを所定値以上に維
持することができる。When Fe / Ni of the feed water supplied to the reactor 1 is detected by the water quality detector 29 to be equal to or lower than a predetermined value, the controller 31 causes the clad storage tank via the clad introduction system 27.
Mix the clad from 25 into the water supply. As a result, the Fe concentration in the feed water increases, and Fe / Ni in the feed water can be maintained at a predetermined value or higher.
給水中のFe/Niを所定値以上にすることによって、炉水
中において、 Ni2+＋Fe2O3＋H2O→NiFe2O4＋2H+ ……60 Co2+＋Fe2O3＋H2O→60CoFe2O4＋2H+ …… で示される反応が進行する。これらの式，で示され
るように、炉水中でイオン放射能（60Co2+）が鉄により
吸着除去されるため、炉水中のイオン放射能濃度が低減
される。その結果、原子炉内および再循環系統内におけ
るイオン放射能の蓄積量を減少することができ、原子炉
等の点検作業時における作業員の被曝を低減することが
できる。By setting Fe / Ni in the feed water to a predetermined value or higher, Ni 2+ + Fe 2 O 3 + H 2 O → NiFe 2 O 4 + 2H + …… 60 Co 2+ + Fe 2 O 3 + H 2 O → The reaction indicated by 60 CoFe 2 O 4 + 2H + ... proceeds. As shown in these equations, since the ion radioactivity ( 60 Co 2+ ) is adsorbed and removed by iron in the reactor water, the ion radioactivity concentration in the reactor water is reduced. As a result, it is possible to reduce the amount of accumulated ion radioactivity in the reactor and the recirculation system, and to reduce the radiation exposure of workers during inspection work of the reactor and the like.
また、原子炉復・給水系に新たに鉄を注入するのではな
く、逆洗水受タンク21からのクラッドを利用し、クラッ
ド注入を閉じた系で行なうことから、原子力発電プラン
ト全体のクラッド総量を増加させることなく、給水中の
鉄濃度を制御することができる。さらに、系統外から鉄
を注入しないので、この注入した鉄が給水加熱器等へ付
着するおそれも少ない。In addition, instead of newly injecting iron into the reactor recovery / water supply system, the cladding from the backwash water receiving tank 21 is used, and the cladding is injected in a closed system. The iron concentration in the water supply can be controlled without increasing Furthermore, since iron is not injected from outside the system, the injected iron is less likely to adhere to the feed water heater or the like.
また、中空糸膜フィルタから構成される復水ろ過器で浄
化されてほぼ純水に近い状態となった給水にクラッドを
混入するので、給水中のFe濃度つまりFe/Niの制御を極
めて容易に行なうことができる。In addition, since the clad is mixed with the feed water that has been purified by the condensate filter made up of the hollow fiber membrane filter and has become a state close to pure water, it is extremely easy to control the Fe concentration in the feed water, that is, Fe / Ni. Can be done.
なお、上記実施例では、クラッド注入系27の他端が、原
子炉復・給水系の低圧給水ポンプ15および給水加熱器17
間に接続されたものにつき説明したが、このクラッド導
入系27の他端を給水加熱器17および高圧給水ポンプ19間
に接続させてもよい。この他の実施例の場合には、前記
実施例の効果に比べ、給水加熱器17内にほぼ純水状態の
給水を流すことになるので、給水加熱器17の故障等を低
減でき、保守点検を容易化できる。In the above embodiment, the other end of the clad injection system 27 is connected to the low pressure feed pump 15 and the feed water heater 17 of the reactor return / feed water system.
Although the one connected between the above is described, the other end of the clad introducing system 27 may be connected between the feed water heater 17 and the high-pressure feed pump 19. In the case of this other embodiment, compared to the effect of the above-mentioned embodiment, since the feed water in the substantially pure water state is made to flow in the feed water heater 17, it is possible to reduce the trouble of the feed water heater 17, and to perform maintenance and inspection. Can be facilitated.
以上のように、この発明に係る原子炉復・給水系の水質
制御装置によれば、中空糸膜フィルタを用いた復水ろ過
器の逆洗水受タンクに連結され、逆洗水中に含まれるク
ラッドを貯蔵するクラッド貯蔵タンクと、高圧給水ポン
プの下流側に設けられて給水中のFe・Ni比を検出する水
質検出器と、この検出器に接続され、Fe・Ni比が所定値
以下になったときにクラッド貯蔵タンク中のクラッドを
給水中に混入させるコントローラとを有して構成される
ことから、逆洗水受タンクから混入されるクラッドによ
り給水中のFe・Ni比を所定値以上に維持して、Feによる
イオン放射能の吸着除去効果を促進させ、炉水中のイオ
ン放射能濃度を低減することができる。その結果、原子
炉内におけるイオン放射能の蓄積量を減少させることが
でき、原子炉等の点検作業時における作業員の被曝を低
減することができる。As described above, according to the water quality control device for the reactor condensate / feed water system according to the present invention, it is connected to the backwash water receiving tank of the condensate filter using the hollow fiber membrane filter and is included in the backwash water. A clad storage tank that stores the clad, a water quality detector that is installed downstream of the high-pressure feed pump to detect the Fe / Ni ratio in the feed water, and is connected to this detector so that the Fe / Ni ratio falls below a specified value. When it becomes a clad, it is configured with a controller that mixes the clad in the clad storage tank into the feed water.Therefore, the clad mixed from the backwash water receiving tank keeps the Fe / Ni ratio in the feed water above a specified value. It is possible to accelerate the adsorption and removal effect of ion radioactivity by Fe and reduce the ion radioactivity concentration in the reactor water. As a result, it is possible to reduce the amount of accumulated ion radioactivity in the nuclear reactor, and to reduce the exposure of workers during inspection work of the nuclear reactor and the like.
第１図はこの発明に係る原子炉復・給水系の水質制御装
置が適用された原子炉復・給水系を示す系統図、第２図
は給水中のFe/Niと炉水中のイオン放射能濃度との関係
を示すグラフである。 １……原子炉、３……高圧タービン、５……低圧タービ
ン、７……復水器、11……復水ろ過器、17……給水加熱
器、19……高圧給水ポンプ、21……逆洗水受タンク、23
……水質制御装置、25……クラッド貯蔵タンク、27……
クラッド導入系、29……水質検出器、31……コントロー
ラ。FIG. 1 is a system diagram showing a reactor recuperation / water supply system to which a water quality control system for a reactor recuperation / supply water system according to the present invention is applied, and FIG. It is a graph which shows the relationship with a density. 1 ... Reactor, 3 ... High-pressure turbine, 5 ... Low-pressure turbine, 7 ... Condenser, 11 ... Condensate filter, 17 ... Feed water heater, 19 ... High-pressure feed pump, 21 ... Backwash water receiving tank, 23
...... Water quality control device, 25 …… Clad storage tank, 27 ……
Cladding system, 29 ... Water quality detector, 31 ... Controller.
Claims (3)
膜フィルタが適用された原子炉復・給水系の給水の水質
を制御する原子炉復・給水系の水質制御装置において、
上記復水ろ過器の逆洗水受タンクに連結されて逆洗水中
に含まれるクラッドを貯蔵するクラッド貯蔵タンクと、
高圧給水ポンプの下流側に設けられて給水中のFe・Ni比
を検出する水質検出器と、この検出器に接続され、Fe・
Ni比が所定値以下になったときに上記クラッド貯蔵タン
ク中のクラッドを給水中に混入させるコントローラとを
有することを特徴とする原子炉復・給水系の水質制御装
置。1. A water quality control device for a nuclear reactor condensate / water supply system, wherein a hollow fiber membrane filter is applied to a condensate filter of a nuclear power plant to control the water quality of the reactor condensate / water supply system.
A clad storage tank connected to the backwash water receiving tank of the condensate filter to store the clad contained in the backwash water,
A water quality detector that is installed on the downstream side of the high-pressure water supply pump and detects the Fe / Ni ratio in the feed water, and is connected to this detector.
A water quality control device for a reactor return / feed water system, comprising: a controller for mixing the clad in the clad storage tank into the feed water when the Ni ratio falls below a predetermined value.
クラッドを、給水加熱器の上流側の給水中に混入させる
特許請求の範囲第１項記載の原子炉復・給水系の水質制
御装置。2. The water quality control device for a reactor recuperation / feed water system according to claim 1, wherein the controller mixes the clad in the clad storage tank into the feed water on the upstream side of the feed water heater.
クラッドを給水加熱器の下流側の給水中に混入させる特
許請求の範囲第１項記載の原子炉復・給水系の水質制御
装置。3. The water quality control device for a reactor recuperation / feed water system according to claim 1, wherein the controller mixes the clad in the clad storage tank into the feed water on the downstream side of the feed water heater.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62254752A JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62254752A JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0198998A JPH0198998A (en) | 1989-04-17 |
| JPH0721549B2 true JPH0721549B2 (en) | 1995-03-08 |
Family
ID=17269387
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62254752A Expired - Lifetime JPH0721549B2 (en) | 1987-10-12 | 1987-10-12 | Water quality control system for reactor water supply / water supply system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0721549B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3653609B2 (en) * | 1998-10-16 | 2005-06-02 | 株式会社日立製作所 | Nuclear power plant and its operating method |
-
1987
- 1987-10-12 JP JP62254752A patent/JPH0721549B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0198998A (en) | 1989-04-17 |
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