JPS62274299A - Nuclear power facility - Google Patents
Nuclear power facilityInfo
- Publication number
- JPS62274299A JPS62274299A JP61118028A JP11802886A JPS62274299A JP S62274299 A JPS62274299 A JP S62274299A JP 61118028 A JP61118028 A JP 61118028A JP 11802886 A JP11802886 A JP 11802886A JP S62274299 A JPS62274299 A JP S62274299A
- Authority
- JP
- Japan
- Prior art keywords
- iron
- condensate
- water supply
- iron oxide
- piping
- 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
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 75
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N Iron oxide Chemical compound [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 claims description 64
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 50
- 229910052742 iron Inorganic materials 0.000 claims description 39
- 238000002347 injection Methods 0.000 claims description 23
- 239000007924 injection Substances 0.000 claims description 23
- 238000010612 desalination reaction Methods 0.000 claims description 16
- 238000001914 filtration Methods 0.000 claims description 10
- 238000010248 power generation Methods 0.000 claims description 10
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 22
- 229910052759 nickel Inorganic materials 0.000 description 11
- 239000012510 hollow fiber Substances 0.000 description 10
- 239000012528 membrane Substances 0.000 description 10
- 238000005070 sampling Methods 0.000 description 6
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 4
- 229910052760 oxygen Inorganic materials 0.000 description 4
- 239000001301 oxygen Substances 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 230000003247 decreasing effect Effects 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 239000003456 ion exchange resin Substances 0.000 description 3
- 229920003303 ion-exchange polymer Polymers 0.000 description 3
- 238000011001 backwashing Methods 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 239000010941 cobalt Substances 0.000 description 2
- 229910017052 cobalt Inorganic materials 0.000 description 2
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 230000008021 deposition Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010828 elution Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000010348 incorporation Methods 0.000 description 1
- 150000002505 iron Chemical class 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- 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
- Supply And Distribution Of Alternating Current (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
- Crystals, And After-Treatments Of Crystals (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Separation Using Semi-Permeable Membranes (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】
３、発明の詳細な説明
（発明の目的〕
（産業上の利用分野）
本発明は原子力発電設備に係り、とりわ【」原子炉中の
イオン状放射能濃度および原子炉配管の置換性線源を低
減して放射線被ばくを低減することができる原子力発電
設備に関する。Detailed Description of the Invention 3. Detailed Description of the Invention (Object of the Invention) (Industrial Field of Application) The present invention relates to nuclear power generation equipment, and in particular to the concentration of ionic radioactivity and atoms in a nuclear reactor. The present invention relates to nuclear power generation equipment that can reduce radiation exposure by reducing displaceable radiation sources in reactor piping.
（従来の技術）
復水浄化系にろ過装置と脱塩装置をともに備えたいわゆ
る二重化した。沸騰水型原子ノ〕発電設備では、ろ過装
置および脱塩装置によって復水内の酸化鉄が捕集され、
給水系からの酸化鉄濃度が極端に低下し、原子炉への酸
化鉄持込量が激減した。(Prior art) The condensate purification system is equipped with both a filtration device and a desalination device, which is a so-called duplex system. In boiling water type atomic power generation equipment, iron oxide in condensate is collected by filtration equipment and desalination equipment,
The concentration of iron oxide from the water supply system decreased dramatically, and the amount of iron oxide carried into the reactor was drastically reduced.
そのため、酸化鉄が原子炉内にて放射化されで生じる放
ｆｊ４性物質（以下沈積性線源と略す）は微減し、それ
による被ばく饋も減少した。しかし、酸化鉄が減少した
ために給水系及び原子炉系のステレンス鋼等からの腐食
溶出するニッケル、コバルトを酸化鉄で捕かくして燃料
棒表面上に付着しつづけることができなくなった。この
ため、原子炉水中のイオン状放射性物質を高めることに
なり、それらが原子炉−次系配管の運転中に形成される
酸化皮膜にとり込まれ（以下置換性線源と略す）放射！
！聞率を上昇させることになった。As a result, the amount of fj4 radioactive materials (hereinafter referred to as deposition sources) generated when iron oxide is activated in the nuclear reactor has decreased slightly, and the resulting radiation exposure has also decreased. However, due to the decrease in iron oxide, it is no longer possible to trap the nickel and cobalt corroded and eluted from the stainless steel of the water supply system and nuclear reactor system with iron oxide and continue to adhere to the surface of the fuel rods. For this reason, the amount of ionic radioactive substances in the reactor water increases, and they are incorporated into the oxide film formed during the operation of the reactor-subsystem piping (hereinafter referred to as a displacement source), causing radiation!
! It was decided to increase the listening rate.
この対策として、復水ろ過装置として粉末イオン交換樹
脂（以下ＦＤと略寸）を用いている沸騰水型原子力発電
設備では、ＦＤのバイパスまたはＦＤの粉末イオン交換
樹脂のルーズプリコート等を行ない復水脱塩装置への酸
化鉄負荷を高め、復水脱塩＠置出口から復水系酸化鉄を
リークする状態にしている。このようにして酸化鉄濃度
を給水系においてニッケル対鉄濃度比が１／２以下とな
るようコントロールし、給水系から原子炉へ酸化鉄を注
入している。As a countermeasure to this problem, in boiling water nuclear power generation facilities that use powdered ion exchange resin (hereinafter referred to as FD) as a condensate filtration device, bypassing the FD or loosely precoating the FD with powdered ion exchange resin is performed to condensate water. The iron oxide load on the desalination equipment is increased and condensate iron oxide is leaked from the condensate desalination outlet. In this way, the iron oxide concentration is controlled so that the nickel to iron concentration ratio is 1/2 or less in the water supply system, and iron oxide is injected from the water supply system into the reactor.
ここでニッケル対鉄濃度比の１／２以下という数字は、
原子炉内の腐食溶出してイオン状となったニッケル、コ
バルトを酸化鉄が捕獲し燃料棒表面へ十分付着維持する
ことができる値である。このように燃料棒表面へニッケ
ル等を十分付着維持することができれば、原子炉水中の
イオン状放射能ｍ度を低下でき、原子炉配管の酸化皮膜
への放射能とり込みの低減すなわちａ換牲線源が低減で
きる。Here, the number of 1/2 or less of the nickel to iron concentration ratio is
This is a value that allows iron oxide to capture nickel and cobalt that have become ionized due to corrosion elution in the reactor and maintain sufficient adhesion to the fuel rod surface. If it is possible to maintain sufficient adhesion of nickel etc. to the surface of the fuel rods in this way, it is possible to reduce the ionic radioactivity in the reactor water, and to reduce the incorporation of radioactivity into the oxide film of the reactor piping. Radiation sources can be reduced.
＜発明が解決しようとする問題点〉
しかし、このようなＦＤバイパス等によるニッケル対鉄
１１痩化コントロールは、個々の原子力発電設備によっ
て復水中の酸化鉄濃度が異なったり、ＦＤ、復水脱塩装
置の酸化鉄除去性能が異なることにより、必ずしも任意
に可能となっておらず、かつ復水ｌＢ２塩＠置装の酸化
鉄負荷を高めた結果、復水脱塩装置の樹脂を汚すという
問題が生じている。<Problems to be solved by the invention> However, the control of nickel-to-iron 11 thinning through FD bypass, etc. is difficult because the concentration of iron oxide in condensate varies depending on individual nuclear power generation facilities, and when FD and condensate desalination Due to differences in the iron oxide removal performance of the equipment, this is not necessarily possible arbitrarily, and as a result of increasing the iron oxide load on the condensate lB2 salt @ equipment, there is a problem of contamination of the resin in the condensate desalination equipment. It is occurring.
本発明はこのような点を考慮してなされたものであり、
復水脱塩装置に負担をかけることなく、しかも給水系に
おいてニッケル対鉄１１ｒ！ｉ比を任意ｍ度に確実にコ
ントロールすることができる原子力発電設備を提供する
ことを目的とする。The present invention has been made in consideration of these points,
Nickel to iron 11r in the water supply system without putting a burden on the condensate desalination equipment! It is an object of the present invention to provide a nuclear power generation facility that can reliably control the i ratio to an arbitrary m degree.
（問題点を解決するための手段）
本発明は、原子炉蒸気がタービンを回転させて生じた復
水内の酸化鉄を捕集する復水ろ過フィルタに、復水系配
管を介して復水脱塩装置が接続され、前記復水脱塩装置
に原子炉への給水を送る給水系配管が接続された原子力
発電設備であって、前記復水ろ過フィルタに酸化鉄注入
憬を調整する鉄注入装置を鉄骨配管で接続し、前記鉄注
入装置の鉄注入配管を眞記給水系配管に接続し、前：［
ｌ！復水ろ過フィルタで捕集した酸化鉄を前記給水系配
管に注入するように構成したことを特徴としている。(Means for Solving the Problems) The present invention provides condensate removal through condensate system piping to a condensate filtration filter that collects iron oxide in condensate generated when reactor steam rotates a turbine. A nuclear power generation facility to which a salt device is connected and a water supply system piping for supplying water to the reactor is connected to the condensate desalination device, the iron injection device adjusting iron oxide injection into the condensate filtration filter. Connect with steel piping, and connect the iron injection piping of the iron injection device to the water supply system piping.
l! The present invention is characterized in that the iron oxide collected by the condensate filter is injected into the water supply system piping.
（作 用）
本発明によれば、鉄注入装置によって酸化鉄を任意ｍ給
水系配管に注入することができるので、給水系における
ニッケル対鉄濃度を任意濃度に確実にコントロールする
ことがひきる。(Function) According to the present invention, since iron oxide can be injected into any m of water supply system piping using the iron injection device, it is possible to reliably control the nickel-to-iron concentration in the water supply system to any desired concentration.
（実施例） 以下図面を参照して本発明の詳細な説明する。(Example) The present invention will be described in detail below with reference to the drawings.
図は本発明による原子力発電設備の一実施例を示す概略
系統図である。The figure is a schematic system diagram showing an embodiment of nuclear power generation equipment according to the present invention.
原子炉１には主蒸気弁２を有する主蒸気管３が接続され
、この主蒸気管３はタービン４に接続され、タービン４
の下方には復水器５が設けられている。復水器５には復
水ポンプ６、復水ろ過フィルタとしての役割を果たす中
空糸膜フィルタ８、および復水脱塩装置９が順次復水系
配管７を介して接続されている。また復水脱塩装置９に
は給水加熱器１２が給水系配管１０を介して接続され、
またこの給水系配管１０は原子炉１に接続されるととも
に、給水系配管１０には給水酸素注入装置１１および給
水サンプリング袋間１４が接続されている。A main steam pipe 3 having a main steam valve 2 is connected to the reactor 1, and this main steam pipe 3 is connected to a turbine 4.
A condenser 5 is provided below. A condensate pump 6, a hollow fiber membrane filter 8 serving as a condensate filtration filter, and a condensate desalination device 9 are sequentially connected to the condenser 5 via a condensate system piping 7. Further, a feed water heater 12 is connected to the condensate desalination device 9 via a water feed system piping 10.
Further, this water supply system piping 10 is connected to the nuclear reactor 1, and to the water supply system piping 10, a water supply oxygen injection device 11 and a water supply sampling bag gap 14 are connected.
ここで、中空糸膜フィルタ８は、復水中のクラッド（酸
化鉄）を除去するものであり、復水脱塩装置９は、復水
中のイオン不純物を除去するためのものであり、給水酸
素注入装置１１は給水加熱器１２および給水中の腐食抑
制のために酸素を注入する装置である。給水サンプリン
グ装置１４は給水中の鉄Ｑ度およびニッケル濃度を測定
するためのものである。Here, the hollow fiber membrane filter 8 is for removing crud (iron oxide) in condensate, and the condensate desalination device 9 is for removing ionic impurities in condensate. The device 11 is a feed water heater 12 and a device for injecting oxygen to suppress corrosion in the feed water. The water supply sampling device 14 is for measuring the iron Q degree and nickel concentration in the water supply.
また、中空糸膜フィルタ８に鉄注入装首１３が鉄受配管
２２を介して接続され、この鉄注入装置１３の出側の鉄
注入配管２３は給水加熱器１２の出側の給水系配管１０
に接続されている。この鉄注入装置１３は、鉄量タンク
１５、循環ポンプ１６、循環調整弁１８、循環サンプリ
ング装置１つ、および鉄注入調整弁２０が循環配管１７
によって接続されて構成されている。Further, an iron injection neck 13 is connected to the hollow fiber membrane filter 8 via an iron receiving pipe 22, and the iron injection pipe 23 on the outlet side of the iron injection device 13 is connected to the water supply system pipe 10 on the outlet side of the feed water heater 12.
It is connected to the. This iron injection device 13 includes an iron amount tank 15, a circulation pump 16, a circulation adjustment valve 18, one circulation sampling device, and an iron injection adjustment valve 20 that is connected to a circulation pipe 17.
are connected and configured by.
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。Next, the operation of this embodiment having such a configuration will be explained.
原子炉１で発生した蒸気は、主蒸気弁２から主蒸気管３
およびタービン４を経て復水器５′ｒ″復水となる。こ
の復水は復水ポンプ６を経て中空糸膜フィルタ８に流入
し、この中空糸膜フィルタ８によって復水中の酸化鉄は
ほとんど捕集される。その後復水は、復水脱塩装置９を
通り、復水中の酸化鉄がほぼ１００％除去されて、給水
系を経て原子炉１に戻る。この間給水系配管１０に接続
された給水酸素注入装置による給水への酸素注入によっ
て給水系での腐食が抑制される。The steam generated in the reactor 1 is transferred from the main steam valve 2 to the main steam pipe 3.
The condensate passes through the turbine 4 and becomes condensate in the condenser 5'r''.This condensate flows into the hollow fiber membrane filter 8 through the condensate pump 6, and the hollow fiber membrane filter 8 removes most of the iron oxide in the condensate. After that, the condensate passes through the condensate desalination device 9, where almost 100% of the iron oxide in the condensate is removed, and returns to the reactor 1 via the water supply system.During this time, the condensate is connected to the water supply system piping 10. Corrosion in the water supply system is suppressed by injecting oxygen into the water supply using a water supply oxygen injection device.
この場合、給水内の鉄濃度は給水サンプリング装置１４
によって確認することができるが、通常０．５ｐｐｂ程
度以下の極低レベルに維持されている。In this case, the iron concentration in the feed water is determined by the feed water sampling device 14.
However, it is usually maintained at an extremely low level of about 0.5 ppb or less.
中空糸膜フィルタ８によって捕集された酸化鉄は、中空
糸膜フィルタ８を逆洗することによって、鉄受配管２２
を通って給水鉄注入装置１３の鉄量タンク１５に収！！
され、この鉄量タンク１５で水中に貯えられる。この場
合、循環ポンプ１６が運転され、酸化鉄含有水が循環配
管１７内を循環する。この循環水の酸化鉄濃度は循環サ
ンプリング装置１９で測定される。The iron oxide collected by the hollow fiber membrane filter 8 is transferred to the iron receiving pipe 22 by backwashing the hollow fiber membrane filter 8.
Through it, it is stored in the iron amount tank 15 of the water supply iron injection device 13! !
The iron content tank 15 stores the iron in water. In this case, the circulation pump 16 is operated, and the iron oxide-containing water circulates in the circulation pipe 17. The iron oxide concentration of this circulating water is measured by a circulation sampling device 19.
一方、給水サンプリング装置１４によってニッケルおよ
び鉄濃度を確認し、給水系におけるニッケル対鉄濃度比
が１／２となるよう鉄注入調整弁２０を開度調整して、
必要な酸化鉄を給水内に注入する。On the other hand, the nickel and iron concentrations are confirmed by the water supply sampling device 14, and the opening of the iron injection regulating valve 20 is adjusted so that the nickel to iron concentration ratio in the water supply system is 1/2.
Inject the necessary iron oxide into the water supply.
このように本実施例によれば、給水系におけるニッケル
一対鉄濃度比を１／２以Ｆに確実にコントロールするこ
とができる。また中空糸膜フィルタ８で捕集した酸化鉄
は、鉄注入装置１３に送られるので、復水脱塩装置９に
対する酸化鉄の負荷を減少することができる。さらにま
た、復水ろ過装置として粉末イオン交換樹脂（ＦＤ＞で
はなく中空糸膜フィルタ８を用いているので、逆洗によ
る酸化鉄の収集が容易にできる。As described above, according to this embodiment, the ratio of nickel to iron concentration in the water supply system can be reliably controlled to 1/2 or more. Further, since the iron oxide collected by the hollow fiber membrane filter 8 is sent to the iron injection device 13, the load of iron oxide on the condensate desalination device 9 can be reduced. Furthermore, since the hollow fiber membrane filter 8 is used as the condensate filtration device instead of the powdered ion exchange resin (FD), iron oxide can be easily collected by backwashing.
〔発明の効果〕 ゛
以上説明したように本発明によれば給水系におけるニッ
ケル対鉄濃度比を任意ＷＪ度に確実にコントロールする
ことができる。また復水脱塩装置に対する酸化鉄の負荷
を減少させることができる。[Effects of the Invention] As explained above, according to the present invention, the nickel to iron concentration ratio in the water supply system can be reliably controlled to any WJ degree. Further, the load of iron oxide on the condensate desalination equipment can be reduced.
このことによって、原子炉水中のイオン状放射能濃度を
低減して、原子炉−次系配管に形成される酸化皮膜にと
り込まれる放射能を低減することができ、置換性線源を
低減できる。By this, it is possible to reduce the ionic radioactivity concentration in the reactor water, reduce the radioactivity incorporated into the oxide film formed on the sub-reactor system piping, and reduce the amount of displaceable radiation sources.
図は本発明による原子力発電設備の一実施例を示す概略
系統図である。
１・・・原子炉、４・・・タービン、５・・・復水器、
７・・・復水系配管、８・・・中空糸膜フィルタ、９・
・・復水脱塩装置、１０・・・給水系配管、１３・・・
鉄注入装置、１５・・・鉄量タンク、１６・・・循環ポ
ンプ、１７・・・循環配管、１８・・・循環調整弁、２
０・・・鉄注入調整弁、２２・・・鉄受配管、２３・・
・鉄注入配管。The figure is a schematic system diagram showing an embodiment of nuclear power generation equipment according to the present invention. 1... Nuclear reactor, 4... Turbine, 5... Condenser,
7... Condensate system piping, 8... Hollow fiber membrane filter, 9...
...Condensate desalination equipment, 10...Water supply system piping, 13...
Iron injection device, 15... Iron amount tank, 16... Circulation pump, 17... Circulation piping, 18... Circulation adjustment valve, 2
0... Iron injection adjustment valve, 22... Iron receiving pipe, 23...
・Iron injection piping.
Claims (1)
鉄を捕集する復水ろ過フィルタに、復水系配管を介して
復水脱塩装置が接続され、前記復水脱塩装置に原子炉へ
の給水を送る給水系配管が接続された原子力発電設備に
おいて、前記復水ろ過フィルタに酸化鉄注入量を調整す
る鉄注入装置を鉄受配管で接続し、前記鉄注入装置の鉄
注入配管を前記給水系配管に接続し、前記復水ろ過フィ
ルタで捕集した酸化鉄を前記給水系配管に注入するよう
に構成したことを特徴とした原子力発電設備。A condensate desalination device is connected via condensate system piping to a condensate filtration filter that collects iron oxide in condensate generated when reactor steam rotates a turbine. In a nuclear power generation facility to which a water supply system piping for supplying water to the reactor is connected, an iron injection device for adjusting the amount of iron oxide injection is connected to the condensate filtration filter by an iron receiving piping, and the iron injection piping of the iron injection device is connected to the iron injection device. is connected to the water supply system piping, and the iron oxide collected by the condensate filtration filter is injected into the water supply system piping.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61118028A JPH0634087B2 (en) | 1986-05-22 | 1986-05-22 | Nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61118028A JPH0634087B2 (en) | 1986-05-22 | 1986-05-22 | Nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62274299A true JPS62274299A (en) | 1987-11-28 |
| JPH0634087B2 JPH0634087B2 (en) | 1994-05-02 |
Family
ID=14726269
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61118028A Expired - Lifetime JPH0634087B2 (en) | 1986-05-22 | 1986-05-22 | Nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0634087B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH05126991A (en) * | 1991-10-30 | 1993-05-25 | Ebara Corp | Injecting method for iron into primary coolant system in bwr type nuclear power plant |
-
1986
- 1986-05-22 JP JP61118028A patent/JPH0634087B2/en not_active Expired - Lifetime
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH05126991A (en) * | 1991-10-30 | 1993-05-25 | Ebara Corp | Injecting method for iron into primary coolant system in bwr type nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0634087B2 (en) | 1994-05-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS61111500A (en) | Method of reducing radioactivity of nuclear power plant | |
| JP2982517B2 (en) | Operating method of boiling water nuclear power plant and boiling water nuclear power plant | |
| JP3149738B2 (en) | Boiling water nuclear power plant and operating method thereof | |
| JPS62274299A (en) | Nuclear power facility | |
| JPS63103999A (en) | Method and device for inhibiting adhesion of radioactive substance | |
| JP3156113B2 (en) | Water quality control method and device | |
| JP3289679B2 (en) | Water quality control method for boiling water nuclear power plant | |
| JPS6179194A (en) | Reactor water feeder | |
| JPS63229394A (en) | Nuclear power generating facility | |
| JP3083629B2 (en) | Nuclear power plant | |
| JP2021120662A (en) | Radioactive waste liquid treatment system and method for treating radioactive waste liquid | |
| JPH0631815B2 (en) | Nuclear power plant water supply system | |
| JPS63149598A (en) | Oxidation processing method after chemical decontamination of nuclear power plant | |
| JP4518695B2 (en) | Condensate treatment system and operation method thereof | |
| JPS61213693A (en) | Condensate and feedwater system for nuclear power plant | |
| JPH01185493A (en) | Boiling water type nuclear power plant | |
| JPH02134596A (en) | Chlorine concentration control of feed water for nuclear power station | |
| JPS642919B2 (en) | ||
| JPS61186897A (en) | Feed water facility for nuclear reactor | |
| JP2005049173A (en) | Processing method for radioactive ion-exchange resin and processing apparatus thereby | |
| JPS5855899A (en) | Reactor coolant cleanup system | |
| JP3309784B2 (en) | Water quality control method for boiling water nuclear power plant | |
| JPH05215892A (en) | Feed water iron concentration control device | |
| JP3081149B2 (en) | Method for reducing impurity elution from condensate desalination unit of BWR type nuclear power plant | |
| JPH05288893A (en) | Control method of concentration of chromium of boiling water nuclear power plant |