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JPH0577280B2 - - Google Patents
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JPH0577280B2 - - Google Patents

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Publication number
JPH0577280B2
JPH0577280B2 JP62093647A JP9364787A JPH0577280B2 JP H0577280 B2 JPH0577280 B2 JP H0577280B2 JP 62093647 A JP62093647 A JP 62093647A JP 9364787 A JP9364787 A JP 9364787A JP H0577280 B2 JPH0577280 B2 JP H0577280B2
Authority
JP
Japan
Prior art keywords
filtration
condensate
resin
slurry
outlet
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
Application number
JP62093647A
Other languages
Japanese (ja)
Other versions
JPS63259499A (en
Inventor
Taku Ootani
Hiroshi Nagai
Masayuki Arai
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Ebara Corp
Toshiba Corp
Original Assignee
Ebara Corp
Toshiba Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Ebara Corp, Toshiba Corp filed Critical Ebara Corp
Priority to JP62093647A priority Critical patent/JPS63259499A/en
Publication of JPS63259499A publication Critical patent/JPS63259499A/en
Publication of JPH0577280B2 publication Critical patent/JPH0577280B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Treatment Of Water By Ion Exchange (AREA)
  • Networks Using Active Elements (AREA)
  • Filters And Equalizers (AREA)

Description

【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所の復水ろ過脱塩装置に係
り、とりわけクラツド鉄除去率を適切に制御する
ことができる原子力発電所の復水ろ過脱塩装置に
関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Field of Application) The present invention relates to a condensate filtration desalination device for a nuclear power plant, and particularly to a nuclear power plant capable of appropriately controlling the crud iron removal rate. Concerning condensate filtration and desalination equipment.

(従来の技術) 第6図に原子力発電所の概略系統図を示す。第
6図において、原子炉圧力容器21の一次水より
発生した主蒸気はタービン22へ導かれ、タービ
ン22を駆動した後復水器23へ導かれて復水と
なる。この復水は低圧復水ポンプ24により、復
水ろ過脱塩装置25および復水脱塩装置26から
なる復水浄化系に運ばれる。この復水浄化系でプ
ラント構成材料の腐蝕により発生し一次水に混入
されたクラツド鉄は除去される。このクラツド鉄
は一般に粒子状の金属不純物から形成されてい
る。
(Prior art) Figure 6 shows a schematic system diagram of a nuclear power plant. In FIG. 6, main steam generated from primary water in a reactor pressure vessel 21 is led to a turbine 22, and after driving the turbine 22, is led to a condenser 23 and becomes condensed water. This condensate is transported by a low-pressure condensate pump 24 to a condensate purification system consisting of a condensate filtration and demineralization device 25 and a condensate demineralization device 26 . In this condensate purification system, crud iron that is generated due to corrosion of plant constituent materials and mixed into the primary water is removed. This clad iron is generally formed from particulate metal impurities.

ここで、クラツドとは不溶解性固形分(全成
分)をいい、クラツド鉄とは不溶解性固形分のう
ち鉄分のみをいう。
Here, clad refers to the insoluble solid content (all components), and clad iron refers to only the iron content of the insoluble solid content.

その後、復水は高圧復水ポンプ27によつて給
水加熱器28に運ばれ、そこで、加熱されて給水
ポンプ29により原子炉圧力容器21へ給水とし
て移送され原子炉水30となる。
Thereafter, the condensate is conveyed to the feedwater heater 28 by the high-pressure condensate pump 27, heated there, and transferred as feedwater to the reactor pressure vessel 21 by the feedwater pump 29 to become reactor water 30.

原子炉水30の一部は、原子炉水浄化ポンプ3
6により原子炉水浄化系ろ過脱塩装置34に移送
されて浄化される。また原子炉圧力容器21には
燃料プール冷却浄化系ろ過脱塩装置35が接続さ
れている。これらによつて原子炉水30の不純物
濃度はプラント安定状態では略一定となる。
A part of the reactor water 30 is supplied to the reactor water purification pump 3
6, the water is transferred to the reactor water purification system filtration desalination device 34 and purified. Further, a fuel pool cooling purification system filtration desalination device 35 is connected to the reactor pressure vessel 21 . Due to these, the impurity concentration of the reactor water 30 becomes approximately constant in a stable state of the plant.

この原子力発電所では、ろ過脱塩装置として復
水ろ過脱塩装置25、原子炉水浄化系ろ過脱塩装
置34および燃料プール冷却浄化系ろ過脱塩装置
35が設けられている。このうち復水ろ過脱塩装
置25は、復水ろ過器32を複数並列に配置して
なり、さらにバイパス弁33を有するものであ
る。
This nuclear power plant is provided with a condensate filtration and desalination device 25, a reactor water purification system filtration and desalination device 34, and a fuel pool cooling and purification system filtration and desalination device 35 as filtration and desalination devices. Among these, the condensate filtration and demineralization device 25 includes a plurality of condensate filters 32 arranged in parallel, and further includes a bypass valve 33.

第7図でさらに復水ろ過装置25について詳述
する。
The condensate filtration device 25 will be further explained in detail in FIG.

スラリ作成タンク9で粉末カチオン樹脂および
粉末アニオン樹脂より作成された粉末樹脂スラリ
はエゼクタ10に吸上げられ、プリコートポンプ
11で復水ろ過器2内に装着されたエレメント8
上にプリコートされる。エレメント8は目の細い
単層のステンレス製金網で、この外表面に粉末樹
脂がプリコートされる。
Powdered resin slurry created from powdered cation resin and powdered anionic resin in slurry creation tank 9 is sucked up by ejector 10, and is transferred to element 8 installed in condensate filter 2 by precoat pump 11.
precoated on top. Element 8 is a fine-mesh, single-layer stainless wire mesh, the outer surface of which is pre-coated with powdered resin.

クラツド鉄を含んだ復水は復水入口6より復水
ろ過器2内に流入し、プリコート層を有するエレ
メント8を通過してクラツド鉄が除去され、その
後復水は復水出口7より流出する。
Condensate containing crud iron flows into the condensate filter 2 from the condensate inlet 6, passes through an element 8 having a precoat layer to remove the crud iron, and then the condensate flows out from the condensate outlet 7. .

そして、この復水ろ過装置25におけるろ過メ
カニズムとしては差圧上昇特性に関するろ過メカ
ニズムのモデルが考えられていた。第8図はプリ
コート層を有するエレメントの拡大図であり、第
9図は従来のろ過メカニズムを示す図であり第8
図のA部の状態を示す。
As the filtration mechanism in this condensate filtration device 25, a model of filtration mechanism related to differential pressure increase characteristics has been considered. FIG. 8 is an enlarged view of an element having a precoat layer, and FIG. 9 is a diagram showing a conventional filtration mechanism.
The state of part A in the figure is shown.

第8図および第9図に示すように、従来は差圧
特性のみによつてろ過メカニズムを考えていた。
そしてこのように差圧特性のみによつて考えたろ
過メカニズムでは、例えば第7図において復水ク
ラツド鉄濃度が10PPbであるのに対し、ある時
期出口クラツド鉄濃度が1PPbであつたり、ま
たある時期出口クラツド鉄濃度′が3PPbであつ
たりする現象を解明することができず、その対応
等も不明であつた。
As shown in FIGS. 8 and 9, the filtration mechanism has conventionally been considered only based on differential pressure characteristics.
In a filtration mechanism considered only based on differential pressure characteristics, for example, in Figure 7, the condensate clad iron concentration is 10 PPb, while the outlet clad iron concentration is 1 PPb at a certain time, and at another time. It was not possible to elucidate the phenomenon in which the outlet clad iron concentration was around 3PPb, and the countermeasures were also unclear.

一方、原子炉水30の放射能レベルを下げるに
は、原子炉水30に持込むクラツド鉄量を低くし
ただけでは効果がなく、適切なクラツド鉄量を原
子炉水30に混入させる必要がある。このために
も、復水ろ過脱塩装置25の出口クラツド鉄量を
適切かつ正確に制御することが必要とされてい
る。しかしながら、従来の復水ろ過脱塩装置25
ではスラリ作成条件が画一的であり、出口クラツ
ド鉄濃度を適切かつ正確に制御することはできな
かつた。
On the other hand, in order to reduce the radioactivity level of the reactor water 30, simply reducing the amount of crud iron brought into the reactor water 30 is not effective; it is necessary to mix an appropriate amount of crud iron into the reactor water 30. . For this purpose as well, it is necessary to appropriately and accurately control the amount of clad iron at the outlet of the condensate filtration and desalination device 25. However, the conventional condensate filtration and desalination equipment 25
However, slurry preparation conditions were uniform, and it was not possible to appropriately and accurately control the outlet clad iron concentration.

また、原子炉30に持込むクラツド鉄量を制御
するためには、原子炉水浄化系ろ過脱塩装置34
および燃料プール冷却浄化系ろ過脱塩装置35の
出口クラツド鉄濃度を制御することが必要である
が、復水ろ過脱塩装置25と同様スラリ作成条件
が画一的であり、出口クラツド鉄濃度を制御する
ことができなかつた。
In addition, in order to control the amount of crud iron brought into the reactor 30, the reactor water purification system filtration desalination device 34
It is necessary to control the outlet clad iron concentration of the fuel pool cooling and purification system filtration desalination device 35, but as with the condensate filtration desalination device 25, slurry creation conditions are uniform, and the outlet clad iron concentration is controlled. I couldn't control it.

本発明はこのような点を考慮してなされたもの
であり、原子力発電所に設けられたろ過脱塩装置
の出口クラツド鉄濃度を適切に制御することがで
きる、原子力発電所のろ過脱塩装置を提供するこ
とを目的とする。
The present invention has been made in consideration of these points, and provides a filtration desalination device for a nuclear power plant that can appropriately control the concentration of iron cladding at the outlet of the filtration desalination device installed in a nuclear power plant. The purpose is to provide

〔発明の構成〕[Structure of the invention]

(問題点を解決するための手段) 本発明は、スラリ作成タンク内で粉末カチオン
樹脂および粉末アニオン樹脂より作成された粉末
樹脂スラリをろ過器内のエレメントにプリコート
し、このろ過器内に復水を通してクラツド鉄を除
去するよう構成した原子力発電所のろ過脱塩装置
であつて、前記スラリ作成タンクに粉末カチオン
樹脂および粉末アニオン樹脂の投入量を適宜制御
する自動投入装置を設け、さらに前記スラリ作成
タンクに自動変速機により駆動される撹拌機を設
置し、この自動変速機に撹拌回転数および撹拌時
間を制御する自動制御装置を接続したことを特徴
としている。
(Means for Solving the Problems) The present invention involves pre-coating a powder resin slurry made from a powder cation resin and a powder anion resin in a slurry preparation tank onto an element in a filter, and condensing water into the filter. The filtration desalination equipment for a nuclear power plant is configured to remove crud iron through the slurry preparation tank, and the slurry preparation tank is provided with an automatic feeding device for appropriately controlling the amount of powdered cation resin and powdered anion resin added. It is characterized in that a stirrer driven by an automatic transmission is installed in the tank, and an automatic control device that controls the stirring rotation speed and stirring time is connected to the automatic transmission.

(作用) 自動投入装置によつて、粉末カチオン樹脂およ
び粉末アニオン樹脂の混合比を変え、また自動制
御装置によつて自動変速機で駆動される撹拌機の
回転数と撹拌時間を変えることによつて、エレメ
ントへのプリコート状態を変化させてろ過脱塩装
置の出口クラツドを鉄濃度を制御することができ
る。
(Function) By changing the mixing ratio of the powdered cation resin and powdered anion resin by the automatic feeding device, and by changing the rotation speed and stirring time of the stirrer driven by the automatic transmission by the automatic control device. Therefore, it is possible to control the iron concentration in the outlet cladding of the filtration/desalination device by changing the precoat state on the element.

(実施例) 以下、図面を参照して本発明の実施例について
説明する。第1図乃至第5図は本発明による原子
力発電所のろ過脱塩装置の一実施例を示す図であ
り、原子力発電所の復水ろ過脱塩装置として用い
られたものである。
(Example) Hereinafter, an example of the present invention will be described with reference to the drawings. FIGS. 1 to 5 are diagrams showing an embodiment of a filtration and desalination apparatus for a nuclear power plant according to the present invention, which is used as a condensate filtration and desalination apparatus for a nuclear power plant.

第1図において、復水ろ過脱塩装置1は、スラ
リ作成タンク9内において粉末カチオン樹脂15
および粉末アニオン樹脂16より作成された粉末
スラリをエゼクタ10によつて吸上げて、プリコ
ートポンプ11で復水ろ過器2内に装着されたエ
レメント8上にプリコートし、復水を復水入口6
より復水ろ過器2内に流入させてクラツド鉄を除
去し、その後腹水出口7より流出させて構成され
ている。
In FIG. 1, the condensate filtration and desalination apparatus 1 includes a powder cation resin 15 in a slurry preparation tank 9.
A powder slurry made from powder anion resin 16 is sucked up by an ejector 10, precoated onto an element 8 installed in a condensate filter 2 by a precoat pump 11, and the condensate is transferred to a condensate inlet 6.
The condensate is allowed to flow into the condensate filter 2 to remove crud iron, and then flows out from the ascites outlet 7.

粉末カチオン樹脂15および粉末アニオン樹脂
16は、それぞれカチオンタンク15aおよびア
ニオンタンク16a内に一時的に貯留され、投入
量制御器17によつてスラリ作成タンク9への粉
末カチオン樹脂15および粉末アニオン樹脂16
の投入量が適宜制御される。これらカチオンタン
ク15a、アニオンタンク16aおよび投入量制
御器17で自動投入装置が構成される。
The powder cation resin 15 and the powder anion resin 16 are temporarily stored in a cation tank 15a and an anion tank 16a, respectively, and are supplied to the slurry preparation tank 9 by the input amount controller 17.
The amount of input is controlled appropriately. The cation tank 15a, the anion tank 16a, and the amount controller 17 constitute an automatic feeding device.

また、スラリ作成タンク9内には自動変速機1
3により駆動される撹拌機12が設置され、この
自動変速機13に撹拌回転数および撹拌時間を制
御する自動制御装置14が接続されている。
In addition, an automatic transmission 1 is installed in the slurry preparation tank 9.
3 is installed, and an automatic control device 14 that controls the stirring rotation speed and stirring time is connected to this automatic transmission 13.

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.

まず、スラリ作成タンク9に規定レベルまで純
水が張られ、粉末アニオン樹脂16がスラリ作成
タンク9に規定量投入される。この場合、投入量
制御器17によつてアニオンタンク16aの出口
が開閉操作されて、粉末アニオン樹脂16の投入
量が制御される。次に撹拌機12でスラリ作成タ
ンク9内が撹拌され、粉末カチオン樹脂15が粉
末アニオン樹脂16と同様投入量制御器17によ
つて、スラリ作成タンク9に規定量投入される。
First, the slurry preparation tank 9 is filled with pure water to a specified level, and a specified amount of powdered anion resin 16 is put into the slurry preparation tank 9. In this case, the input amount controller 17 opens and closes the outlet of the anion tank 16a to control the input amount of the powdered anion resin 16. Next, the inside of the slurry making tank 9 is stirred by the stirrer 12, and a prescribed amount of the powdered cationic resin 15 and the powdered anionic resin 16 are put into the slurry making tank 9 by the amount controller 17.

このように、投入量制御器17によつて粉末カ
チオン樹脂15と粉末アニオン樹脂16の投入量
および混合比を自動的に制御することができる。
また自動制御装置14によつて、自動変速機13
によつて駆動される撹拌機12の回転数および撹
拌時間を自動的に制御することができる。
In this way, the input amount controller 17 can automatically control the input amounts and mixing ratio of the powdered cation resin 15 and the powdered anion resin 16.
Further, the automatic transmission 13 is controlled by the automatic control device 14.
The rotation speed and stirring time of the stirrer 12 driven by the stirrer 12 can be automatically controlled.

この復水ろ過脱塩装置を用いた場合、出口クラ
ツド鉄濃度およびろ過メカニズムについて以下の
ような結果が判明した。
When this condensate filtration and desalination equipment was used, the following results were found regarding the outlet clad iron concentration and the filtration mechanism.

まず、復水ろ過脱塩装置のろ過メカニズムにつ
いては、出口クラツド鉄濃度および差圧特性につ
いてのろ過メカニズムのモデルが判明した。これ
を第2図に示す。
First, regarding the filtration mechanism of the condensate filtration and desalination equipment, a model of the filtration mechanism with respect to outlet clad iron concentration and differential pressure characteristics was found. This is shown in FIG.

すなわち、第2図においてろ過メカニズムは電
気化学的吸着→飽和→純体積ろ過→飽和→表面ろ
過→飽和と推定でき、また差圧上昇に関連して出
口クラツド鉄濃度の変化が説明しうることがわか
つた。
That is, in Figure 2, the filtration mechanism can be assumed to be electrochemical adsorption → saturation → pure volume filtration → saturation → surface filtration → saturation, and the change in outlet clad iron concentration can be explained in relation to the increase in differential pressure. I understand.

この実績例を第3図に示す。 An example of this performance is shown in Figure 3.

また、この出口クラツド鉄濃度の変化は、第4
図に示すように3種のパターンに分類される。そ
して、この出口クラツド鉄濃度を制御させるため
には、粉末樹脂スラリの混合比(C=粉末カチオ
ン樹脂量/A=粉末アニオン樹脂量)と粉末樹脂
フロツクの沈降特性を把握すれば良いことがわか
つた。粉末樹脂フロツクの沈降特性は、一般的に
はV=ある時間(約15〜20分)後のスラリ沈降体
積をV0=初期のスラリ体積で割つたV/V0で把
握することができ、またこのV/V0は任意の混
合比に対して撹拌機の撹拌時間および回転数を変
えることによつて変化させることができる。
In addition, this change in the outlet clad iron concentration is due to the fourth
As shown in the figure, it is classified into three types of patterns. In order to control the outlet clad iron concentration, it was found that it is necessary to understand the mixing ratio of the powdered resin slurry (C = amount of powdered cation resin / A = amount of powdered anionic resin) and the sedimentation characteristics of the powdered resin floc. Ta. The sedimentation characteristics of powdered resin flocs can generally be understood as V/ V0 , where V=slurry sedimentation volume after a certain time (approximately 15 to 20 minutes) divided by V0 =initial slurry volume. Moreover, this V/V 0 can be changed by changing the stirring time and rotation speed of the stirrer for any mixing ratio.

第5図に、混合比とV/V0をパラメータとし
た復水ろ過器2の平均出口クラツド鉄濃度と運転
日数の関係の一例を示す。例えば、復水ろ過器2
の平均出口クラツド鉄濃度を0.8PPbとしたい場
合、混合比C/A=6/1V/V0≒0.5とすれば良
い。その際運転日数は約29日となる。
FIG. 5 shows an example of the relationship between the average outlet clad iron concentration of the condensate filter 2 and the number of operating days using the mixing ratio and V/V 0 as parameters. For example, condensate filter 2
If you want to set the average outlet clad iron concentration to 0.8PPb, the mixing ratio C/A=6/1V/V 0 ≒0.5 should be used. In that case, the number of operating days will be approximately 29 days.

第5図において、( )内下段は所定のV/V0
値を示し、上段はそのV/V0値に達するまでの
スラリ撹拌時間であり、撹拌機12の回転数を上
昇させるかまたは撹拌翼の面積を増加することに
より撹拌時間の短縮を図ることができる。所定の
V/V0値に達した場合、撹拌機12は自動制御
器14により自動変速機13の駆動が停止され
る。
In Figure 5, the lower part in parentheses indicates the predetermined V/V 0
The upper row shows the slurry stirring time until reaching the V/V 0 value, and the stirring time can be shortened by increasing the rotation speed of the stirrer 12 or increasing the area of the stirring blades. can. When the predetermined V/V 0 value is reached, the automatic controller 14 stops the agitator 12 from driving the automatic transmission 13 .

このように粉末カチオン樹脂および粉末アニオ
ン樹脂の混合比を変え、また撹拌機12の回転数
と撹拌翼の面積を変化させてV/V0値を変えて
スラリ作成条件を変えることにより、復水ろ過器
2の出口クラツド鉄濃度(すなわち復水ろ過脱塩
装置1の出口クラツド鉄濃度)を適切に制御する
ことができる。また、復水ろ過脱塩装置1の出口
クラツド鉄濃度の変化曲線も制御することができ
る。
In this way, by changing the mixing ratio of the powdered cation resin and powdered anionic resin, and also by changing the rotation speed of the stirrer 12 and the area of the stirring blades, changing the V/V 0 value and changing the slurry creation conditions, the condensate The clad iron concentration at the outlet of the filter 2 (that is, the clad iron concentration at the outlet of the condensate filtration and desalination apparatus 1) can be appropriately controlled. Moreover, the change curve of the clad iron concentration at the outlet of the condensate filtration and desalination apparatus 1 can also be controlled.

このように本実施例によれば、復水ろ過脱塩装
置1の出口クラツド鉄濃度の制御が容易にできる
ので、復水ろ過脱塩装置1の入口水質の性状が変
化した場合でも出口クラツド濃度の制御を迅速か
つ容易に達成できる。また、必要に応じて復水ろ
過脱塩装置1の出口クラツド鉄濃度の制御を行う
ことができるので、原子炉水へ持ち込むクラツド
鉄量の制御が容易となり、原子力発電所の放射能
レベルを低減し従事者被曝線量の低減を図ること
ができる。
In this way, according to this embodiment, the outlet clad iron concentration of the condensate filtration and desalination apparatus 1 can be easily controlled, so even if the quality of the inlet water of the condensate filtration and desalination apparatus 1 changes, the outlet clad iron concentration can be controlled. can be quickly and easily controlled. In addition, the concentration of crud iron at the outlet of the condensate filtration and desalination equipment 1 can be controlled as necessary, making it easier to control the amount of crud iron brought into the reactor water, thereby reducing the radioactivity level at the nuclear power plant. Therefore, it is possible to reduce the radiation dose of workers.

なお、本実施例において、復水ろ過脱塩装置に
ついて適用した例を示したが、これに限らず本発
明によるろ過脱塩装置を原子炉水浄化系ろ過脱塩
装置または燃料プール冷却浄化系ろ過脱塩装置に
適用することもできる。
In addition, in this embodiment, an example in which the filtration and desalination apparatus according to the present invention is applied is shown, but the present invention is not limited to this, and the filtration and desalination apparatus of the present invention can be applied to a reactor water purification system filtration and desalination apparatus or a fuel pool cooling purification system filtration. It can also be applied to desalination equipment.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、必要に応じてろ過脱塩装置の
出口クラツド鉄濃度の制御を容易に行うことがで
きる。このため原子炉水へ持込むクラツド鉄量の
制御が容易となり、原子力発電所の放射能レベル
を低減して従業者被曝線量の低減を図ることがで
きる。
According to the present invention, it is possible to easily control the clad iron concentration at the outlet of the filtration and desalination equipment as required. Therefore, it becomes easy to control the amount of crud iron brought into the reactor water, and it is possible to reduce the radioactivity level in the nuclear power plant and reduce the radiation exposure of workers.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本発明によるろ過脱塩装置の一実施例
である復水ろ過脱塩装置を示す図であり、第2図
は復水ろ過脱塩装置の出口クラツド鉄濃度変化の
ろ過メカニズムを示す図、第3図は出口クラツド
鉄濃度と差圧特性を示す図、第4図はスラリ作成
条件と出口クラツド鉄濃度の関係を示す図、第5
図は樹脂の混合比とV/V0をパラメータとした
出口クラツド鉄濃度と運転日数の関係を示す図、
第6図は原子力発電所の概略系統図、第7図は従
来の復水ろ過脱塩装置を示す図、第8図は従来の
復水ろ過脱塩装置のプリコート層を有するエレメ
ントの拡大図、第9図は従来の復水ろ過脱塩装置
のろ過メカニズムを示す図である。 1……復水ろ過脱塩装置、2……復水ろ過器、
8……エレメント、9……スラリ作成タンク、1
2……撹拌機、13……自動変速機、14……自
動制御装置、15……粉末カチオン樹脂、15a
……カチオンタンク、16……粉末アニオン樹
脂、16a……アニオンタンク、17……投入量
制御器。
Fig. 1 is a diagram showing a condensate filtration desalination device which is an embodiment of the filtration desalination device according to the present invention, and Fig. 2 shows the filtration mechanism of the change in clad iron concentration at the outlet of the condensate filtration desalination device. Figure 3 is a diagram showing the outlet cladding iron concentration and differential pressure characteristics, Figure 4 is a diagram showing the relationship between slurry preparation conditions and outlet cladding iron concentration, and Figure 5 is a diagram showing the relationship between the slurry preparation conditions and the outlet cladding iron concentration.
The figure shows the relationship between the outlet clad iron concentration and the number of operating days, with the resin mixing ratio and V/V 0 as parameters.
FIG. 6 is a schematic diagram of a nuclear power plant, FIG. 7 is a diagram showing a conventional condensate filtration desalination device, and FIG. 8 is an enlarged view of an element having a precoat layer of a conventional condensate filtration desalination device. FIG. 9 is a diagram showing the filtration mechanism of a conventional condensate filtration and desalination apparatus. 1... Condensate filtration desalination device, 2... Condensate filter,
8...Element, 9...Slurry creation tank, 1
2... Stirrer, 13... Automatic transmission, 14... Automatic control device, 15... Powder cation resin, 15a
... Cation tank, 16 ... Powdered anion resin, 16a ... Anion tank, 17 ... Input amount controller.

Claims (1)

【特許請求の範囲】[Claims] 1 スラリ作成タンク内で粉末カチオン樹脂およ
び粉末アニオン樹脂より作成された粉末樹脂スラ
リをろ過器内のエレメントにプリコートし、この
ろ過器内に復水を通してクラツド鉄を除去するよ
う構成した原子力発電所のろ過脱塩装置におい
て、前記スラリ作成タンクに粉末カチオン樹脂お
よび粉末アニオン樹脂の投入量を適宜制御する自
動投入装置を設け、さらに前記スラリ作成タンク
に自動変速機により駆動される撹拌機を設置し、
この自動変速機に撹拌回転数および撹拌時間を制
御する自動制御装置を接続したことを特徴とする
原子力発電所のろ過脱塩装置。
1. A nuclear power plant configured to pre-coat an element in a filter with a powder resin slurry made from a powder cation resin and a powder anion resin in a slurry preparation tank, and pass condensate through the filter to remove crud iron. In the filtration desalination apparatus, the slurry creation tank is provided with an automatic charging device that appropriately controls the amount of powdered cation resin and powdered anion resin, and the slurry creation tank is further equipped with an agitator driven by an automatic transmission,
A filtration desalination device for a nuclear power plant, characterized in that an automatic control device for controlling stirring rotation speed and stirring time is connected to this automatic transmission.
JP62093647A 1987-04-16 1987-04-16 Filtering desalting device for nuclear power plant Granted JPS63259499A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62093647A JPS63259499A (en) 1987-04-16 1987-04-16 Filtering desalting device for nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62093647A JPS63259499A (en) 1987-04-16 1987-04-16 Filtering desalting device for nuclear power plant

Publications (2)

Publication Number Publication Date
JPS63259499A JPS63259499A (en) 1988-10-26
JPH0577280B2 true JPH0577280B2 (en) 1993-10-26

Family

ID=14088162

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62093647A Granted JPS63259499A (en) 1987-04-16 1987-04-16 Filtering desalting device for nuclear power plant

Country Status (1)

Country Link
JP (1) JPS63259499A (en)

Also Published As

Publication number Publication date
JPS63259499A (en) 1988-10-26

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