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JP2821167B2 - Water-cooled direct cycle nuclear power plant - Google Patents
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JP2821167B2 - Water-cooled direct cycle nuclear power plant - Google Patents

Water-cooled direct cycle nuclear power plant

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Publication number
JP2821167B2
JP2821167B2 JP1075152A JP7515289A JP2821167B2 JP 2821167 B2 JP2821167 B2 JP 2821167B2 JP 1075152 A JP1075152 A JP 1075152A JP 7515289 A JP7515289 A JP 7515289A JP 2821167 B2 JP2821167 B2 JP 2821167B2
Authority
JP
Japan
Prior art keywords
iron
water
concentration
cooling water
power plant
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 - Fee Related
Application number
JP1075152A
Other languages
Japanese (ja)
Other versions
JPH01316692A (en
Inventor
誠 長瀬
大和 朝倉
元昭 宇多村
俊介 内田
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP1075152A priority Critical patent/JP2821167B2/en
Publication of JPH01316692A publication Critical patent/JPH01316692A/en
Application granted granted Critical
Publication of JP2821167B2 publication Critical patent/JP2821167B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は水冷却直接サイクル型原子力プラントに係わ
り、炉水中の放射性腐食生成物の濃度を一層低減するの
に好適な原子力プリントと冷却水中の鉄濃度制御方法に
関する。
Description: FIELD OF THE INVENTION The present invention relates to a water-cooled direct cycle nuclear power plant, and more particularly to a nuclear print and a cooling water suitable for reducing the concentration of radioactive corrosion products in reactor water. It relates to a method for controlling iron concentration.

〔従来の技術〕[Conventional technology]

従来の給水中の腐食生成物の濃度制御方法は、特開昭
61−79194号公報に記載されているように給水中のFe/Ni
濃度比を2〜10に保つことによつて炉水中の58Co・60Co
イオン濃度を低くするように制御しようとするものであ
つた。しかしがながら、ニツケル濃度が低くなつた場合
の最適な制御に関しては十分な考慮がなされていなかつ
た。
A conventional method for controlling the concentration of corrosion products in feed water is disclosed in
Fe / Ni in feed water as described in JP 61-79194
58 Co · 60 Co of'll go-between furnace water to keep the concentration ratio of 2 to 10
It was intended to control so as to lower the ion concentration. However, sufficient consideration has not been given to the optimal control when the nickel concentration decreases.

〔発明が解決しようとする課題〕[Problems to be solved by the invention]

上記従来技術は給水中のFe/Ni濃度比のみに着目して
最適な制御を行なうようにしているが、この条件を満た
して炉水中の58Coイオン濃度が低いレベルを達成したと
きでも炉水中の60Coイオン濃度が予想されるレベルより
も高くなることがあり、制御の指標として問題が残つて
いる。
Although the above-mentioned conventional technology focuses on only the Fe / Ni concentration ratio in the feed water to perform the optimal control, even when the 58 Co ion concentration in the reactor water achieves a low level by satisfying this condition, may be higher than the level 60 Co ion concentration is expected, a problem as an index of control is Zantsu.

本発明の目的は、給水中のニッケル濃度が低くなつた
場合にも、炉水中の60Coイオン濃度を低く維持できる水
冷却直接サイクル型原子力プラント及びその運転方法を
提供することにある。
An object of the present invention is to provide a water-cooled direct cycle nuclear power plant capable of maintaining a low 60 Co ion concentration in reactor water even when the nickel concentration in feedwater is low, and an operation method thereof.

〔課題を解決するための手段〕[Means for solving the problem]

上記目的は、原子炉,タービン,復水器,浄化装置及
び給水ヒータを主たる構成要素として順次含む水冷却直
接サイクル型原子力プラントにおいて、冷却水中の鉄濃
度を測定し、燃料棒表面への鉄の蓄積率が0.5mg/m2/hr
以上となる鉄分量を冷却水中に供給するため、前記鉄濃
度の測定データから鉄濃度の過不足量を算出し、冷却水
中の鉄分を最適量に制御することにより達成できる。
The above-mentioned object is to measure the iron concentration in the cooling water and measure the iron concentration on the fuel rod surface in a water-cooled direct cycle nuclear power plant that includes a nuclear reactor, a turbine, a condenser, a purification device, and a feedwater heater as main components sequentially. 0.5mg / m 2 / hr accumulation rate
In order to supply the above iron content to the cooling water, it can be achieved by calculating the excess or deficiency of the iron concentration from the iron concentration measurement data and controlling the iron content in the cooling water to an optimal amount.

〔作用〕[Action]

本発明は、冷却水中の鉄濃度を測定し、測定されたデ
ータから燃料棒表面への鉄の蓄積率を算出し、算出され
た蓄積率が0.5mg/m2/hr以上となるように冷却水中の鉄
濃度を鉄注入装置から注入する鉄の量を制御するもので
ある。給水中のFe/Ni比を2〜10に保つことは燃料棒表
面に付着するニツケルやコバルトの化学形態を安定で溶
出しにくいフエライト酸化物(NiFe2O4,CoFe2O4)と
し、放射化されて生成した58Coや60Coが炉水中に溶出す
る量をニツケルやコバルトがモノオキサイドの形態で付
着した時に比べて少なくすることができる。しかし、第
2図のa)に示したように燃料棒表面に付着した腐食生
成物のすべての部分から60Coが炉水中に溶出するのでは
なく、ある溶出に寄与できる厚さ内の60Coが炉水中に溶
出すると考えられる。したがつて、b)に示したように
腐食生成物の化学形態がフエライト酸化物であつても鉄
の蓄積が少ない場合では燃料棒表面に蓄積された60Coの
大部分が炉水中への溶出に寄与することになる。これに
対して、c)のように鉄の蓄積量が多い場合には、燃料
棒表面に蓄積された60Coの一部分のみが炉水中への溶出
に寄与することになる。
The present invention measures the iron concentration in the cooling water, calculates the accumulation rate of iron on the fuel rod surface from the measured data, and cools the calculated accumulation rate to be 0.5 mg / m 2 / hr or more. The iron concentration in the water is controlled by the amount of iron injected from the iron injection device. Maintaining the Fe / Ni ratio in the feedwater at 2 to 10 is to reduce the chemical form of nickel and cobalt adhering to the fuel rod surface to ferrite oxide (NiFe 2 O 4 , CoFe 2 O 4 ) The amount of 58 Co and 60 Co produced as a result of the conversion into the reactor water can be reduced as compared with when nickel or cobalt adheres in the form of monooxide. However, instead of 60 Co from all parts of the corrosion products adhering to the fuel rods surface as shown in a) of FIG. 2 is eluted into the reactor water, 60 in the thickness that can contribute to an elution Co Is eluted in the reactor water. Therefore, as shown in b), even when the chemical form of the corrosion product is ferrite oxide, when the accumulation of iron is small, most of the 60 Co accumulated on the fuel rod surface elutes into the reactor water. Will contribute. On the other hand, when the amount of accumulated iron is large as in c), only a part of 60 Co accumulated on the fuel rod surface contributes to elution into the reactor water.

60Coの半減期は約5年と通常の運転サイクル1年に比
べて長く、燃料棒に付着したCoの比放射能は時間と共に
単調に増加するとみなせるが、実際のプラントの運転に
伴う炉水中の60Co濃度の上昇率は、比放射能の上昇に比
べて小さいが普通である。これは前に述べたように全て
の燃料棒表面に蓄積した60Coが溶出に寄与していないこ
とに対応する。即ち、新しく燃料棒に付着する鉄の層が
比放射能の高くなつてくる古い付着物からの60Coの炉水
中への溶出を遮蔽する効果があると考えると説明でき
る。このような観点より運転プラントにおける燃料棒へ
の鉄の蓄積率と炉水中の60Co濃度の上昇率を計算してみ
ると、第3図に示したように燃料棒への鉄の蓄積率が大
きくなるほど炉水中の60Co濃度の上昇率が小さくなる傾
向が見出された。この図より燃料棒への鉄の蓄積率が0.
5mg/m2/hr以上の範囲では、炉水中の60Co濃度の上昇率
が小さくなることがわかる。したがつて、燃料棒への鉄
の蓄積率を指標として冷却水中の鉄濃度を最適化するこ
とができる。
The half-life of 60 Co is about 5 years, which is longer than the normal operation cycle of 1 year, and the specific activity of Co attached to the fuel rods can be considered to increase monotonically with time. The rate of increase of the 60 Co concentration is small but normal compared to the increase in specific activity. This corresponds to the fact that 60 Co accumulated on all fuel rod surfaces did not contribute to elution as described above. That is, it can be explained that the iron layer newly adhering to the fuel rod has an effect of shielding the elution of 60 Co into the reactor water from the old adhering matter whose specific activity becomes higher. From this point of view, when the accumulation rate of iron on fuel rods and the rate of increase of 60 Co concentration in reactor water in the operating plant are calculated, the accumulation rate of iron on fuel rods as shown in FIG. It was found that the rate of increase of the 60 Co concentration in the reactor water became smaller as it became larger. From this figure, the accumulation rate of iron on the fuel rod is 0.
It can be seen that in the range of 5 mg / m 2 / hr or more, the increase rate of the 60 Co concentration in the reactor water becomes small. Therefore, the iron concentration in the cooling water can be optimized using the accumulation rate of iron in the fuel rod as an index.

しかしながら、燃料棒表面に蓄積する鉄の量を必要以
上に大きくすると、燃料棒から炉水への熱伝達を阻害
し、燃料被覆管の破損を引き起こしたり、鉄の放射化に
より生成する54Mn,56Feが増加するため、トータルの放
射能濃度が上昇するという弊害があるので不必要な鉄を
持ち込まないようにする必要がある。
However, if the amount of iron accumulated on the fuel rod surface is increased more than necessary, heat transfer from the fuel rods to the reactor water is hindered, which may cause damage to the fuel cladding tube or 54 Mn, Since there is an adverse effect of increasing the total radioactivity concentration due to an increase in 56 Fe, it is necessary to avoid bringing in unnecessary iron.

この中でいう原子炉とは、沸騰水型原子炉または新型
転換炉のように水を冷却材とし燃料棒表面において沸騰
が起るタイプの原子炉である。冷却水中の鉄濃度とは冷
却水中に含まれるイオン化された状態のFe,イオン化さ
れていない水酸化鉄,酸化鉄等といつた化学形態によら
ない全ての鉄の濃度である。鉄濃度を測定する装置とは
原子吸光やイオンクロマトグラフ等のサンプリングされ
た試料に含まれる鉄を全て溶解してイオンにした状態で
その量を定量できる状態である。冷却水中の鉄分を最適
量に制御する装置とは鉄濃度の測定データを入力とし燃
料棒表面への鉄の蓄積率を換算するために必要となるメ
モリと演算装置,演算結果に基づいて注入量を変化させ
るための流量調節弁又は流量を調節できるポンプから構
成された制御装置である。鉄注入装置とは鉄を陽極電解
によりイオン化させ又はさらにクラツド化させる鉄イオ
ン,クラツド発生装置または鉄成分を含む水を貯蔵する
タンクと鉄成分を含む水を冷却水中に注入するためのポ
ンプを有する装置である。
The term "reactor" as used herein refers to a type of reactor in which water is used as a coolant and boiling occurs on the surface of a fuel rod, such as a boiling water reactor or a new type of converter. The iron concentration in the cooling water refers to the concentration of all iron contained in the cooling water, regardless of chemical form, such as ionized Fe, non-ionized iron hydroxide, iron oxide, and the like. An apparatus for measuring iron concentration is a state in which all iron contained in a sampled sample such as atomic absorption or ion chromatography can be dissolved and ionized and the amount thereof can be quantified. The device that controls the iron content in the cooling water to the optimum amount is a memory and a calculation device required to convert the iron accumulation rate on the fuel rod surface with the measured data of the iron concentration as input, and the injection amount based on the calculation result. Is a control device composed of a flow control valve for changing the pressure or a pump capable of controlling the flow. The iron injection device has iron ions for ionizing or further forming iron by anodic electrolysis, a clad generator or a tank for storing water containing iron components, and a pump for injecting water containing iron components into cooling water. Device.

〔実施例〕〔Example〕

以下、本発明の一実施例を第1図により説明する。第
1図は沸騰水型原子力プラントの系統を示した図であ
り、タービン1を作動させた後、復水器2を出た腐食生
成物を含む復水は復水ポンプ3により復水プレフイルタ
4及び復水脱塩器5を通過する際その腐食生成物の大部
分が除去される。浄化させた水は給水ポンプ6、低圧給
水加熱器7、昇圧ポンプ8、高圧給水加熱器9を通って
原子炉圧力容器10に導かれる。原子炉圧力容器10に持ち
込まれる腐食生成物は、復水脱塩器5で除去しされなか
つたものに、主として高圧給水加熱器9の腐食によつて
発生するNi等が加わつたものとなる。その持ち込み量は
サンプリングライン11を通して採取された試料を濃度測
定装置12により測定することから知ることができる。
Hereinafter, an embodiment of the present invention will be described with reference to FIG. FIG. 1 is a diagram showing a system of a boiling water nuclear power plant. After the turbine 1 is operated, the condensate containing the corrosion product that has exited the condenser 2 is condensed by a condensate pre-filter 4 by a condensate pump 3. Most of the corrosion products are removed when passing through the condensate desalter 5. The purified water is led to a reactor pressure vessel 10 through a feedwater pump 6, a low-pressure feedwater heater 7, a booster pump 8, and a high-pressure feedwater heater 9. Corrosion products brought into the reactor pressure vessel 10 are not removed by the condensate demineralizer 5, but also include Ni and the like generated mainly by corrosion of the high-pressure feed water heater 9. The carry-in amount can be known by measuring the sample taken through the sampling line 11 by the concentration measuring device 12.

試料サンプリングと鉄濃度の測定の具体的な例を以下
に示す。サンプリングライン11に0.45μmのミリポアフ
イルター1枚と陽イオン交換ペーパーを2〜3枚セツト
した試料ホルダーを取り付け約100ml/分の流量で積算流
量100〜150通水する。ミリポアフイルターに捕集され
た鉄クラツドは6Nの塩酸200mlを加えて加熱し溶解させ
たのち蒸留水で定容とする。陽イオン交換ペーパーに捕
集された鉄イオンは2N塩酸15mlに5分以上浸漬し溶離さ
せる操作を2〜3回行い、最後に2N塩酸で定容とする。
このようにして調整した試料水をを原子吸光光度計を用
いて測定し、鉄濃度を算出する。原子吸光法に共通する
一般事項はJIS K 0121(原子吸光分析方法通則)が参考
となる。
Specific examples of sample sampling and iron concentration measurement are shown below. A sampling line 11 is equipped with a sample holder in which one 0.45 μm Millipore filter and two or three cation exchange papers are set, and an integrated flow rate of 100 to 150 is passed at a flow rate of about 100 ml / min. The iron clad collected in the Millipore filter is heated to dissolve by adding 200 ml of 6N hydrochloric acid, and then made up to a constant volume with distilled water. The iron ions collected on the cation exchange paper are immersed in 15 ml of 2N hydrochloric acid for 5 minutes or more to elute, and the volume is adjusted to 2 to 3 times with 2N hydrochloric acid.
The sample water thus adjusted is measured using an atomic absorption spectrophotometer, and the iron concentration is calculated. JIS K 0121 (general rules of atomic absorption analysis method) is referred to for general matters common to the atomic absorption method.

本発明では、この測定値を演算装置13に入力し、演算
装置において知識ベース14に格納されているプラントパ
ラメータを用いながら次の式に従つて燃料棒への鉄の蓄
積率への換算を行なう。
In the present invention, this measured value is input to the arithmetic unit 13, and the arithmetic unit converts the iron accumulation rate into the fuel rods using the plant parameters stored in the knowledge base 14 according to the following equation. .

ここで、 α:燃料棒への鉄の蓄積率(mg/m2/hr) C :給水中の鉄濃度(ppb) F :定格給水流量(t/hr) S :燃料棒表面積(m2) P :測定時の出力(MW) Pmax:定格出力(MW) (1)式により求められた燃料棒への鉄の蓄積率αが0.
5より小さい時は(0.5−α)に相当する分以上の冷却水
中の鉄濃度を増加させるように制御する。即ち、(1)
式を変形して得られる次式を用いて増加させる給水中の
鉄濃度を求める。
Where: α: accumulation rate of iron in fuel rod (mg / m 2 / hr) C: iron concentration in feed water (ppb) F: rated feed water flow rate (t / hr) S: fuel rod surface area (m 2 ) P: Output during measurement (MW) Pmax: Rated output (MW) The accumulation rate α of iron in the fuel rod obtained by equation (1) is 0.
When it is smaller than 5, control is performed so as to increase the iron concentration in the cooling water by an amount equal to or more than (0.5-α). That is, (1)
The increased iron concentration in the feed water is determined using the following equation obtained by modifying the equation.

ここで、 δC:増加させるべき給水中の鉄濃度の下限値(ppb) 増加させるべき給水中の鉄濃度の下限値δCに対応す
る鉄注入装置15からの鉄の注入量は、δC×F(mg/h
r)として求められる。実際に注入する鉄の量はδC×
Fに炉内構造材や再循環配管等に付着する分を補うだけ
過剰にする必要がある。過去の経験から給水系から炉内
に持ち込まれる鉄が燃料棒に付着する割合はほぼ80〜90
%であることより、過剰分としては(C+δC)の10〜
20%を下限とすればよい。このようにして求められた鉄
の注入率となるように、鉄注入装置15から給水中に注入
される鉄の量を流量調節弁16を用いて行なうことができ
る。
Here, δC: the lower limit of the iron concentration in the feed water to be increased (ppb) The iron injection amount from the iron injector 15 corresponding to the lower limit δC of the iron concentration in the feed water to be increased is δC × F ( mg / h
r). The amount of iron actually injected is δC ×
It is necessary to make F excessive enough to compensate for the amount of F that adheres to the structural material inside the furnace, the recirculation pipe, and the like. From the past experience, the ratio of iron brought into the furnace from the water supply system to the fuel rods is almost 80 to 90
%, The excess is (C + δC) 10 to
The lower limit may be 20%. The amount of iron injected into the water supply from the iron injection device 15 can be adjusted using the flow control valve 16 so that the iron injection rate determined in this manner is obtained.

鉄注入装置15の具体例として鉄含有水を発生させる電
解鉄発生装置として実開昭63−135200号に開示されてい
るものがあり、その構成を第8図に示す。電解鉄発生装
置は、CO2圧入原水槽17、電解槽18、CO2放散器19とから
構成される。CO2圧入原水槽ではガス噴射口20を通してC
O2ガス50/hの割合で電解槽に流し、電解槽では更にガ
ス噴射口22を通してN2ガスを100/hの割合で導入し、C
O2ガス放散器ではガス噴射口23を通してN2ガスを200/
hの割合で排出し、鉄製電極21に加える電解電流を100V2
0A、供給する脱気純水の量を60/hとすると約100ppmの
鉄イオンを含む水を得ることができる。このようにして
得られる鉄イオンを含むポンプと流量調節弁を用いて約
20/hから60/hの間で流量を調節することにより、給
水流量6400t/hの1100MWeクラスのプラントでは、給水中
の鉄濃度を0.3〜1.0ppb増加させるこが可能である。
As a specific example of the iron injection device 15, there is one disclosed in Japanese Utility Model Application Laid-Open No. 63-135200 as an electrolytic iron generator for generating iron-containing water, and its configuration is shown in FIG. The electrolytic iron generator includes a CO 2 injection raw water tank 17, an electrolytic tank 18, and a CO 2 diffuser 19. In the CO 2 injection raw water tank, C is injected through the gas injection port 20.
O 2 gas was flowed into the electrolytic cell at a rate of 50 / h, and in the electrolytic cell, N 2 gas was further introduced at a rate of 100 / h through the gas injection port 22, and C
In the O 2 gas dissipator, N 2 gas is supplied at 200 /
h at a rate of 100 V2
Assuming that the deaerated pure water to be supplied is 0 A and the amount of the supplied deaerated water is 60 / h, water containing about 100 ppm of iron ions can be obtained. Using a pump containing iron ions obtained in this way and a flow control valve,
By adjusting the flow rate between 20 / h and 60 / h, it is possible to increase the iron concentration in the feedwater by 0.3 to 1.0 ppb in a 1100 MWe class plant with a feedwater flow rate of 6400 t / h.

反対に(1)式で求められた燃料棒への鉄の蓄積率α
が3.0好ましくは2.0(mg/m2/hr)より大きい時は(α−
2.0)に相当する分の冷却水中の鉄濃度を減少させるよ
うに制御する。即ち、(1)式を変形して得られる次式
を用いて減少させる給水中の鉄濃度を求める。
Conversely, the accumulation rate α of iron in the fuel rod calculated by equation (1)
Is greater than 3.0, preferably 2.0 (mg / m 2 / hr), (α-
Control to reduce the iron concentration in the cooling water equivalent to 2.0). That is, the iron concentration in the supply water to be reduced is obtained using the following equation obtained by modifying the equation (1).

ここで、 δC′:減少させるべき給水中の鉄濃度(ppb) (3)式で求められた減少させるべき給水中の鉄濃度
δC′に対応する注入量(δC′×F)だけ流量調節弁
16を用いて減らすことあるいは注入を停止することによ
り燃料棒への鉄の蓄積率αを2.0(mg/m2/hr)以下に制
御することができる。
Here, δC ′: iron concentration in the feed water to be reduced (ppb) The flow control valve by the injection amount (δC ′ × F) corresponding to the iron concentration δC ′ in the feed water to be reduced obtained by the equation (3).
By reducing the amount by using 16 or by stopping the injection, the accumulation rate α of iron in the fuel rod can be controlled to 2.0 (mg / m 2 / hr) or less.

先に述べた1100MWeクラスのプラントで100ppmの鉄イ
オンを含む水を注入している場合はδC′×Fに相当す
る注入流量の変更量は となる。これによりα値は好ましい2.0以下となるが、
鉄濃度が高すぎると鉄に起因する放射能の増加を引き起
こす併害もあるので運転時間5000h以降ではα値を0.5〜
1.0にするように注入量を抑制することが好ましい。
When water containing 100 ppm of iron ions is injected into a 1100 MWe class plant as described above, the amount of change in the injection flow rate corresponding to δC ′ × F is Becomes As a result, the α value is preferably 2.0 or less,
If the iron concentration is too high, there may be complications that cause an increase in radioactivity caused by iron.
It is preferable to suppress the injection amount to 1.0.

もつとも、注入量を0としてもα値が0.5を越える給
水濃度が得られる時は鉄注入を行う必要はないが、鉄濃
度の制御は不能となるため、復水浄化系の性能改善をす
ることが好ましい。
In any case, it is not necessary to inject iron when the water supply concentration exceeds 0.5, even if the injection amount is 0, but iron concentration cannot be controlled, so the performance of the condensate purification system should be improved. Is preferred.

上記のように給水中の鉄濃度を制御することにより、
燃料棒への鉄の蓄積率αを0.5から2.0(mg/m2/hr)の範
囲に保つことができるので炉水中の60Co濃度の上昇率を
低くすることができる。
By controlling the iron concentration in the feedwater as described above,
Since the accumulation rate α of iron in the fuel rod can be kept in the range of 0.5 to 2.0 (mg / m 2 / hr), the rate of increase of the 60 Co concentration in the reactor water can be reduced.

上記実施例の(1)から(3)式では鉄濃度を測定し
た時の出力Pの入力も燃料棒への蓄積率αの算出に用い
ているが、この代わりに測定時の給水流量を用いてもよ
い。このとき、(1)から(3)式は以下のように書き
換えられる。
In Equations (1) to (3) of the above embodiment, the input of the output P when the iron concentration is measured is also used to calculate the accumulation rate α in the fuel rod, but the feedwater flow rate at the time of measurement is used instead. You may. At this time, the expressions (1) to (3) are rewritten as follows.

ここで、 F′:測定時の給水流量(t/hr) 変形例 上記実施例では燃料棒への鉄の蓄積率にのみ着目して
鉄の濃度を制御しようとするものであつたが、新しいプ
ラントの第1サイクルの初期の運転においては燃料棒表
面の腐食生成物が少ないため鉄とニツケル又はコバルト
が燃料棒表面で接触する確率が小さくなると推定され
る。このため、第1サイクルの初期の運転においては燃
料棒全体に腐食生成物が付着するまでは燃料棒への鉄の
蓄積率が下限値を0.5以上に設定しておく方が好まし
い。このように燃料棒表面に早期に鉄の付着層を形成
し、配管等の構造材への放射性腐食生成物の取り込み速
度の大きい時期の炉水中の放射性腐食生成物の濃度を低
くすることは、一次系の線量率を低く維持する上で効果
がある。
Here, F ': water supply flow rate at the time of measurement (t / hr) Modification In the above embodiment, the iron concentration is controlled by focusing only on the accumulation rate of iron in the fuel rod. It is estimated that in the early operation of the first cycle of the plant, the probability of iron and nickel or cobalt coming into contact on the fuel rod surface is reduced due to less corrosion products on the fuel rod surface. For this reason, in the initial operation of the first cycle, it is preferable that the lower limit of the accumulation rate of iron in the fuel rod be set to 0.5 or more until the corrosion product adheres to the entire fuel rod. In this way, it is possible to form an adhesion layer of iron early on the fuel rod surface and reduce the concentration of radioactive corrosion products in the reactor water at a time when the rate of incorporation of radioactive corrosion products into structural materials such as pipes is high. It is effective in keeping the primary system dose rate low.

実施例2 本発明の第2の実施例は燃料棒への鉄の蓄積率を制御
しようとしているプラントにおいて、そのプラント固有
のパラメータにしたがつて予め給水中の鉄濃度と燃料棒
への鉄の蓄積率の関係を求めて第4図に示したような運
転時間に対する給水中の鉄濃度の制御目標値を設定して
おき、これに基づいて運転中の給水中の鉄濃度を制御す
ることにより燃料棒への鉄の蓄積率を0.5(mg/m2/hr)
以上にすることができる。
Embodiment 2 In a second embodiment of the present invention, in a plant in which the accumulation rate of iron in the fuel rod is to be controlled, the iron concentration in the feed water and the iron concentration in the fuel rod are determined in advance in accordance with a plant-specific parameter. By calculating the relationship between the accumulation rates and setting a control target value of the iron concentration in the feed water with respect to the operation time as shown in FIG. 4, the iron concentration in the feed water during operation is controlled based on this. 0.5 (mg / m 2 / hr) iron accumulation rate on fuel rod
Or more.

具体例を1100MWeのプラントで以下に示す。プラント
パラメータの概略値は、定格熱出力Pmax3300MWt、給水
流量6400t/h、燃料棒表面積7000m2である。従つて、定
格出力運転を行うことを仮定し、5000時間までαを0.
7、それ以後は0.5という下限値に制御目標を設定する
と、給水中の鉄濃度は5000時間までは(1)式より0.7
7、その以後は0.55ppbとなる。多少の余裕を見て、小数
点以下2桁目を切り上げると、第4図に示した給水中の
鉄濃度制御目標パターンが得られる。
A specific example is shown below for a 1100 MWe plant. The approximate values of the plant parameters are a rated heat output Pmax of 3300 MWt, a feedwater flow rate of 6400 t / h, and a fuel rod surface area of 7000 m 2 . Therefore, assuming that the rated output operation is performed, α is set to 0.
7, After that, if the control target is set to the lower limit of 0.5, the iron concentration in the water supply will be 0.7 from equation (1) until 5000 hours.
7, it becomes 0.55ppb after that. After rounding up the second decimal place with some allowance, the iron concentration control target pattern in the water supply shown in FIG. 4 is obtained.

上記鉄濃度制御パターンに従つた運転を行つた場合の
炉水中の60Coイオン濃度のシミュレーション解析の結果
を第9図に示す。比較のために全ての運転時間給水中の
鉄濃度で0.3ppb、αで0.27を保つた場合の解析結果を第
10図に示す。2000から6000時間の間では20%から40%も
低い値となることが解析的に示されている。この結果、
10000時間後の配管表面の線量率は最適条件では約25mR/
hであるが、鉄が不足する第10図の解析条件では約35mR/
hと40%高くなることが予想される。鉄の量が更に少な
い場合ではこの差が一層大きくなる。
FIG. 9 shows the results of a simulation analysis of the 60 Co ion concentration in the reactor water when the operation was performed according to the iron concentration control pattern. For comparison, the analysis results for the case where the iron concentration in the feedwater was kept at 0.3 ppb and α at 0.27 for all operating hours were compared.
Figure 10 shows. Analytical results show that between 2000 and 6000 hours, values are as low as 20% to 40%. As a result,
The dose rate on the piping surface after 10,000 hours is about 25 mR /
h, but about 35 mR /
h and is expected to be 40% higher. This difference is even greater when the amount of iron is smaller.

給水中の鉄濃度制御パターンを予め設定しておく場合
では、給水中の鉄濃度を測定した後の燃料棒への鉄の蓄
積率の算出プロセスを必要としなくなるため制御が簡略
化されるが、出力変動に対しての考慮は省略されてしま
う。
If the iron concentration control pattern in the feedwater is set in advance, the control is simplified because the process of calculating the accumulation rate of iron in the fuel rods after measuring the iron concentration in the feedwater is not required, The consideration for the output fluctuation is omitted.

第4図で給水中の鉄濃度を運転サイクルの前半で高め
に、後半で低めにしてあるのは、先にも述べたように前
半では燃料棒表面を早期に鉄で覆いニツケルらコバルト
を安定な化学形態で燃料棒上に付着させるためである。
In Fig. 4, the iron concentration in the feedwater is set high in the first half of the operation cycle and low in the second half of the operation cycle. As mentioned earlier, the fuel rod surface is covered with iron early in the first half and nickel and other cobalt are stabilized. This is because it is deposited on the fuel rod in a simple chemical form.

実施例3 先の実施例では炉水中の60Co濃度の上昇率の範囲を広
めに定義し、これに基づいて給水中の鉄濃度を最適に制
御しようとするものであるが、第3図に示した燃料棒へ
の鉄の蓄積率と炉水中の60Co濃度の上昇率の関係は実際
にはかなりのばらつきを持つているので、各プラントご
との最適化を図る方法として第5図に示した制御方法を
用いることができる。即ち、給水中の鉄濃度の他に炉水
中の60Co濃度,給水流量,日付等を入力とし、これらの
値をデータベースに格納すると共に燃料棒への鉄の蓄積
率と炉水中の60Co濃度の上昇率を算出する。炉水中の60
Co濃度の上昇率が設定されている上昇率以下の場合は求
められた最新の燃料棒への鉄の蓄積率を最適な鉄の蓄積
率の下限値として登録する。反対に炉水中の60Co濃度の
上昇率が設定されている上昇率以上の場合は、前回の制
御に用いられた燃料棒への鉄の蓄積率の下限値としては
小さすぎたことを示すので、前回の制御に用いられた燃
料棒への鉄の蓄積率を10〜20%増加させた値を最適な鉄
の蓄積率の下限値として登録する。このようにして燃料
棒への鉄の蓄積率の最適値を変化させることにより、各
プラント、各運転時間ごとに最適な給水中の鉄濃度の制
御が可能となる。燃料棒への最適な鉄の蓄積率の下限値
が求められた後の給水中の鉄濃度の制御方法は第1の実
施例と同様にすればよい。
Example 3 In the previous example, the range of the increase rate of the 60 Co concentration in the reactor water was broadly defined, and the iron concentration in the feed water was to be optimally controlled based on this. The relationship between the rate of accumulation of iron in the fuel rods and the rate of increase of the 60 Co concentration in the reactor water actually varies considerably, so a method for optimizing each plant is shown in Fig. 5. Other control methods can be used. That is, in addition to the iron concentration in the feed water, the 60 Co concentration in the reactor water, the feed water flow rate, the date, etc. are input, and these values are stored in a database, and the iron accumulation rate in the fuel rods and the 60 Co concentration in the reactor water Is calculated. 60 in the reactor water
If the increase rate of the Co concentration is equal to or less than the set increase rate, the latest iron accumulation rate in the fuel rod obtained is registered as the lower limit value of the optimal iron accumulation rate. Conversely, if the increase rate of the 60 Co concentration in the reactor water is higher than the set increase rate, it indicates that the lower limit of the accumulation rate of iron on the fuel rod used in the previous control was too small. Then, a value obtained by increasing the accumulation rate of iron in the fuel rod used in the previous control by 10 to 20% is registered as the lower limit value of the optimal accumulation rate of iron. By changing the optimum value of the accumulation rate of iron in the fuel rods in this manner, it becomes possible to control the iron concentration in the feedwater optimally for each plant and each operation time. The method of controlling the iron concentration in the water supply after the optimum lower limit value of the iron accumulation rate on the fuel rods is determined may be the same as in the first embodiment.

変形例 給水中の鉄濃度を制御する方法として炉水中の60Co濃
度と54Mn濃度を指標として行なうこともできる。即ち、
第6図に示したように炉水中の60Co濃度が高くなつてき
た場合には給水中の鉄濃度を高くし、炉水中の54Mn濃度
が高くなつてきた場合には給水中の鉄濃度を低く制御す
る方法である。この場合、低減しようとしている放射性
腐食生成物を直接指標としているためわかりやすく、現
象が不明でも制御することが可能である。しかしなが
ら、放射化のプロセスと制御効果が現れるには時間遅れ
が生じるため最適化という観点では不十分である。
Modification As a method for controlling the iron concentration in the feed water, the concentration of 60 Co and the concentration of 54 Mn in the reactor water can be used as indices. That is,
As shown in Fig. 6, when the 60 Co concentration in the reactor water increases, the iron concentration in the feedwater increases, and when the concentration of 54 Mn in the reactor water increases, the iron concentration in the feedwater increases. Is a method of controlling the temperature to be low. In this case, since the radioactive corrosion product to be reduced is directly used as an index, it is easy to understand, and it is possible to control even if the phenomenon is unknown. However, the activation process and the control effect have a time delay to appear, which is insufficient from the viewpoint of optimization.

実施例4 燃料棒表面への鉄の蓄積率が0.5(mg/m2/hr)以上を
保つている場合でも、燃料棒表面でのFe/Ni比が2以下
となるほどニツケルが多いプラントにおいては、給水中
のニツケル濃度が測定値も最適な給水中の鉄濃度を算出
するプロセスに取り込む必要がある。即ち、燃料棒表面
への鉄の蓄積率を算出した第1式で鉄をNiに置き換えた
式よりニツケルの蓄積率を算出し、燃料棒表面への鉄の
蓄積率とニツケルの蓄積率の比が2以下とならないよう
に給水中の鉄濃度を制御するものである。このようにす
ることでニツケルやコバルトは安定な化学形態(NiFe2O
4,COFe2O4等)で燃料棒に付着し、放射性コバルトの溶
出が抑制される。ただし、燃料棒へのニツケルの蓄積率
の算出に当つては、鉄の場合と異なつて炉内構造材から
のニツケルの発生量が無視できないことと燃料棒に付着
する割合が鉄に比べて小さくおよそ60〜70%であること
に注意する必要があるが、簡易的には炉内の発生を無視
するかわに燃料棒に付着する割合を大きく見積ることに
よつても大きな誤差にはならない。また、起動試験中の
ように出力変動が大きい時は上記の条件を必ずしも満た
す必要はない。なぜなら、出力変動時は燃料棒からの腐
食生成物の剥離が起りやすく制御の効果が期待できない
からである。本発明において、特に好ましいFe/Ni比は
2〜5である。
Example 4 Even in the case where the accumulation rate of iron on the fuel rod surface is maintained at 0.5 (mg / m 2 / hr) or more, in a plant where the nickel is so large that the Fe / Ni ratio on the fuel rod surface becomes 2 or less. The nickel concentration in the water supply must also be taken into the process of calculating the optimum iron concentration in the water supply, with the measured values also being optimal. That is, the nickel accumulation rate is calculated from the equation (1) in which iron is replaced with Ni in the first equation that calculates the accumulation rate of iron on the fuel rod surface, and the ratio of the iron accumulation rate to the nickel accumulation rate on the fuel rod surface is calculated. The iron concentration in the feed water is controlled so that the value does not become 2 or less. In this way, nickel and cobalt have stable chemical forms (NiFe 2 O
4 , COFe 2 O 4 etc.) adheres to the fuel rods and suppresses elution of radioactive cobalt. However, when calculating the accumulation rate of nickel on fuel rods, unlike the case of iron, the amount of nickel generated from structural materials in the furnace cannot be ignored, and the rate of adhesion to fuel rods is smaller than that of iron. It should be noted that it is about 60 to 70%, but it is not a big error to estimate the rate of sticking to the fuel rods rather than simply ignoring the generation in the furnace. When the output fluctuation is large, such as during a start-up test, it is not always necessary to satisfy the above conditions. This is because, when the output fluctuates, the corrosion products are easily separated from the fuel rods, and the control effect cannot be expected. In the present invention, a particularly preferred Fe / Ni ratio is 2 to 5.

実施例5 実施例の1では、原子炉に持込まれる鉄の濃度を測定
する位置は、第1図に示したように高圧給水加熱器と原
子炉圧力容器の間だけであつたが、第7図に示すよう
に、鉄の注入点の下流側でかつ給水ポンプの上流側にも
測定点を追加して2ケ所とすることもできる。この場
合、上流側と下流側の2つの測定値を比較することによ
り、給水加熱器や途中の配管に鉄が付着することによる
注入鉄の損失を知ることができる。この損失が極端に変
動する時は、注入鉄の化学形態が変つたことが考えら
れ、鉄注入装置の異常を検知することが可能となる。
Embodiment 5 In Embodiment 1, the position for measuring the concentration of iron carried into the reactor was only between the high pressure feed water heater and the reactor pressure vessel as shown in FIG. As shown in the figure, two measurement points can be added downstream of the iron injection point and also upstream of the feedwater pump. In this case, by comparing the two measured values on the upstream side and the downstream side, it is possible to know the loss of the injected iron due to the adhesion of the iron to the feed water heater and the piping on the way. When this loss fluctuates extremely, it is considered that the chemical form of the injected iron has changed, and it is possible to detect an abnormality of the iron injection device.

〔発明の効果〕〔The invention's effect〕

本発明によれば、炉水中の沈降性の放射性腐食生成物
の濃度をあまり増加させることなく、炉水中の60Co濃度
の上昇率を低く保つことができ、運転サイクルを通じて
低い炉水中の60Co濃度を維持することができる。炉水中
60Co濃度が低ければ一次冷却系配管に付着する60Coの
量も少なくなるので、定期点検時の一次系の線量率を低
くすることができるので被曝線量を少なくする効果があ
る。
According to the present invention, without significantly increasing the concentration of the precipitation of radioactive corrosion products in the reactor water, it is possible to keep the increase rate of 60 Co concentration in the reactor water low, 60 Co low reactor water through operating cycles The concentration can be maintained. If the concentration of 60 Co in the reactor water is low, the amount of 60 Co adhering to the primary cooling system piping is also reduced, so that the dose rate of the primary system at the time of the periodic inspection can be reduced, which has the effect of reducing the exposure dose.

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

第1図は本発明の一実施例を示すための沸騰水型原子炉
の給水系統図、第2図は燃料棒表面からの60Co溶出と鉄
蓄積量の関係を模式的に表現した図、第3図は燃料棒表
面への鉄の蓄積率と炉水中の60Co濃度の上昇率の関係を
示した図、第4図は運転時間と給水中の鉄濃度の制御目
標値の関係を示した図、第5図は燃料棒への鉄の蓄積率
を可変とした時の給水中の鉄濃度の制御プロセスフロー
図、第6図は炉水中の60Co濃度と54Mn濃度を指標とした
時の給水中の鉄濃度の制御プロセスフロー図、第7図は
給水ヒータの上流側及び下流側の2つの位置に鉄濃度を
測定する装置を設けた例を示す系統図であり、第8図は
電解鉄発生装置の概略断面図であり、第9図及び第10図
はそれぞれ本発明方法での原子力プラントの運転時間と
60Co炉水中の濃度変化と、鉄濃度を変化させない場合の
運転時間と60Coの炉水中の濃度変化を示すグラフであ
る。 1……タービン、2……復水器、3……復水ポンプ、4
……復水プレフイルタ、5……復水脱塩器、6……給水
ポンプ、7……低圧給水加熱器、8……昇圧ポンプ、9
……高圧給水加熱器、10……原子炉圧力容器、11……サ
ンプリングライン、12……濃度測定装置、13……診断装
置、14……知識ベース、15……鉄注入装置、16……鉄注
入量制御弁、17……CO2圧入原水槽、18……電解槽、19
……CO2放散器、20……CO2ガス噴射口、21……鉄製電
極、22,23……N2ガス噴射口。
FIG. 1 is a diagram showing a water supply system of a boiling water reactor for illustrating one embodiment of the present invention, and FIG. 2 is a diagram schematically showing the relationship between 60 Co elution from the fuel rod surface and iron accumulation, Figure 3 is a diagram showing the relationship between the increase rate of 60 Co concentration of accumulation rate and reactor water of iron into the fuel rod surface, Figure 4 shows the relationship between the control target value of iron concentration in the feedwater and operation time and Fig, Fig. 5 control process flow diagram of the iron concentration in the feedwater when the accumulation rate of iron into the fuel rod is variable, Figure 6 is a 60 Co concentration and 54 Mn concentration in the reactor water as an index FIG. 7 is a system diagram showing an example in which a device for measuring the iron concentration is provided at two positions on the upstream side and the downstream side of the feed water heater, and FIG. 9 is a schematic cross-sectional view of an electrolytic iron generator, and FIG. 9 and FIG.
60 Co furnace and the concentration change of water is a graph showing the operation time and 60 Co concentration changes in the reactor water in the case of not changing the iron concentration. 1 ... turbine, 2 ... condenser, 3 ... condenser pump, 4
………………………………………………………………………………………………………………………………… …………………………………………… ·····
High pressure feed water heater, 10 Reactor pressure vessel, 11 Sampling line, 12 Concentration measuring device, 13 Diagnostic device, 14 Knowledge base, 15 Iron injection device, 16 Iron injection quantity control valve, 17… CO 2 press-in raw water tank, 18 …… Electrolysis tank, 19
…… CO 2 diffuser, 20 …… CO 2 gas injection port, 21 …… Iron electrode, 22,23 …… N 2 gas injection port.

フロントページの続き (72)発明者 内田 俊介 茨城県日立市森山町1168番地 株式会社 日立製作所エネルギー研究所内 (56)参考文献 特開 昭61−213693(JP,A) 特開 昭62−233796(JP,A) 特開 昭63−11898(JP,A) (58)調査した分野(Int.Cl.6,DB名) G21D 3/00 - 3/18Continuing from the front page (72) Inventor Shunsuke Uchida 1168 Moriyama-cho, Hitachi City, Ibaraki Pref. Energy Laboratory, Hitachi, Ltd. (56) References JP-A-61-213693 (JP, A) JP-A-62-233796 (JP) , A) JP-A-63-11898 (JP, A) (58) Fields investigated (Int. Cl. 6 , DB name) G21D 3/00-3/18

Claims (6)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】原子炉,タービン,復水器,浄化装置及び
給水ヒータを主たる構成要素として順次含む水冷却直接
サイクル型原子力プラントにおいて、 冷却水中の鉄濃度を測定する装置、燃料棒表面への鉄の
蓄積率が0.5mg/m2/hr以上となる鉄分量を冷却水中に供
給するため、前記鉄濃度の測定データから鉄濃度の不足
量を算出し、冷却水中の鉄分を最適量に制御する装置を
備えた鉄注入装置を有することを特徴とする水冷却直接
サイクル型原子力プラント。
In a water-cooled direct cycle nuclear power plant which includes a nuclear reactor, a turbine, a condenser, a purification device, and a feedwater heater as main components in sequence, a device for measuring iron concentration in cooling water, In order to supply the amount of iron at which the accumulation rate of iron becomes 0.5 mg / m 2 / hr or more to the cooling water, an insufficient amount of the iron concentration is calculated from the iron concentration measurement data, and the iron content in the cooling water is controlled to an optimal amount. A water-cooled direct cycle nuclear power plant, comprising an iron injection device provided with a device for performing the above.
【請求項2】燃料棒表面への鉄の蓄積率が1〜2mg/m2/h
rとなるように冷却水中の鉄分を最適量に制御すること
を特徴とする第1項記載の水冷却直接サイクル型原子力
プラント。
2. The accumulation rate of iron on the fuel rod surface is 1 to 2 mg / m 2 / h.
2. The water-cooled direct cycle nuclear power plant according to claim 1, wherein the iron content in the cooling water is controlled to an optimum amount so as to be r.
【請求項3】鉄成分を冷却水中に注入する位置を復水浄
化装置の下流側とすることを特徴とする第2項記載の水
冷却直接サイクル型原子力プラント。
3. The water-cooled direct cycle nuclear power plant according to claim 2, wherein the position where the iron component is injected into the cooling water is located downstream of the condensate purification device.
【請求項4】冷却水中の鉄濃度を測定する位置を復水浄
化装置の下流側であって、かつ給水ヒータの上流側、又
は原子炉圧力容器と給水ヒータ間もしくはその両方とす
ることを特徴とする第1項記載の水冷却直接サイクル型
原子力プラント。
4. The method according to claim 1, wherein the iron concentration in the cooling water is measured on the downstream side of the condensate purifier and upstream of the feed water heater, or between the reactor pressure vessel and the feed water heater, or both. 2. A water-cooled direct cycle nuclear power plant according to claim 1.
【請求項5】原子炉,タービン,復水器,浄化装置及び
給水ヒータを主たる構成要素として順次含む水冷却直接
サイクル型原子力プラントの運転方法において、 冷却水中の鉄濃度を測定し、更に、燃料棒表面への鉄の
蓄積率が0.5mg/m2/hr以上となる鉄分量を冷却水中に供
給するため、前記鉄濃度の測定データから鉄濃度の過不
足量を算出し、冷却水中に最適量の鉄分を注入しながら
運転することを特徴とする水冷却直接サイクル型原子力
プラントの運転方法。
5. A method for operating a water-cooled direct cycle nuclear power plant, which includes a reactor, a turbine, a condenser, a purifier, and a feedwater heater as main components sequentially, comprising: measuring an iron concentration in cooling water; In order to supply the amount of iron at which the accumulation rate of iron on the rod surface is 0.5 mg / m 2 / hr or more to the cooling water, the excess or deficiency of the iron concentration is calculated from the measured data of the iron concentration, and is optimal for the cooling water. A method for operating a water-cooled direct-cycle nuclear power plant, which operates while injecting an amount of iron.
【請求項6】原子炉,タービン,復水器,浄化装置及び
給水ヒータを主たる構成要素として順次含む水冷却直接
サイクル型原子力プラントの運転方法において、 冷却水中の鉄濃度を測定し、燃料棒表面への鉄の蓄積率
を算出することに加え、冷却水中のニッケル濃度を測定
し、測定されたニッケル濃度と鉄濃度とから冷却水中の
鉄とニッケルの濃度比を演算し、燃料棒表面への鉄の蓄
積率が0.5mg/m2/hr以上であっても冷却水中の鉄とニッ
ケルの濃度比が2以下の場合は、前記濃度比が2以上と
なるように冷却水中に最適量の鉄分を注入しながら運転
することを特徴とする水冷却直接サイクル型原子力プラ
ントの運転方法。
6. A method of operating a water-cooled direct cycle nuclear power plant, which includes a reactor, a turbine, a condenser, a purifier, and a feedwater heater as main constituents in a sequential manner. In addition to calculating the rate of accumulation of iron in the cooling water, the nickel concentration in the cooling water is measured, and the iron / nickel concentration ratio in the cooling water is calculated from the measured nickel concentration and the iron concentration. Even if the iron accumulation rate is 0.5 mg / m 2 / hr or more, if the concentration ratio of iron and nickel in the cooling water is 2 or less, the optimal amount of iron in the cooling water is adjusted so that the concentration ratio becomes 2 or more. A method for operating a water-cooled direct cycle nuclear power plant, characterized by operating while pouring water.
JP1075152A 1988-03-30 1989-03-29 Water-cooled direct cycle nuclear power plant Expired - Fee Related JP2821167B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1075152A JP2821167B2 (en) 1988-03-30 1989-03-29 Water-cooled direct cycle nuclear power plant

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Application Number Priority Date Filing Date Title
JP7437588 1988-03-30
JP63-74375 1988-03-30
JP1075152A JP2821167B2 (en) 1988-03-30 1989-03-29 Water-cooled direct cycle nuclear power plant

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JPH01316692A JPH01316692A (en) 1989-12-21
JP2821167B2 true JP2821167B2 (en) 1998-11-05

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US5245642A (en) * 1991-10-31 1993-09-14 General Electric Company Method of controlling co-60 radiation contamination of structure surfaces of cooling water circuits of nuclear reactors
JP2808970B2 (en) * 1992-03-19 1998-10-08 株式会社日立製作所 Nuclear power plant, its water quality control method and its operation method
US6937686B2 (en) * 2002-09-30 2005-08-30 General Electric Company Iron control in BWR's with sacrificial electrodes
USD1077102S1 (en) 2023-07-10 2025-05-27 Karsten Manufacturing Corporation Golf club head

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JPS61213693A (en) * 1985-03-19 1986-09-22 株式会社東芝 Condensate and feedwater system for nuclear power plant
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