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JPH0664185B2 - Reactor water quality control system - Google Patents
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JPH0664185B2 - Reactor water quality control system - Google Patents

Reactor water quality control system

Info

Publication number
JPH0664185B2
JPH0664185B2 JP60264904A JP26490485A JPH0664185B2 JP H0664185 B2 JPH0664185 B2 JP H0664185B2 JP 60264904 A JP60264904 A JP 60264904A JP 26490485 A JP26490485 A JP 26490485A JP H0664185 B2 JPH0664185 B2 JP H0664185B2
Authority
JP
Japan
Prior art keywords
hydrogen
hydrogen peroxide
reactor
reactor water
concentration
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
JP60264904A
Other languages
Japanese (ja)
Other versions
JPS62126398A (en
Inventor
英史 伊部
隆芳 安田
英年 唐沢
誠 長瀬
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 JP60264904A priority Critical patent/JPH0664185B2/en
Publication of JPS62126398A publication Critical patent/JPS62126398A/en
Publication of JPH0664185B2 publication Critical patent/JPH0664185B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Treatment Of Water By Oxidation Or Reduction (AREA)

Description

【発明の詳細な説明】 〔発明の利用分野〕 本発明は軽水炉の水質制御に係り、特に軽水炉炉心の液
相中の溶存酸素濃度制御に好適な水質制御システムに関
する。
Description: TECHNICAL FIELD The present invention relates to water quality control of a light water reactor, and particularly to a water quality control system suitable for controlling dissolved oxygen concentration in the liquid phase of a light water reactor core.

〔発明の背景〕[Background of the Invention]

従来のシステムは特開昭57-3086号公報に記載のよう
に、再循環系配管より分岐した配管に溶存酸素,水素濃
度測定装置,SUS304鋼の腐食電位測定系を設け、その測
定値により水素注入量を制御して溶存酸素濃度、腐食電
位を一定の幅におさめる構成となつていた。しかし、こ
の手法は一定の酸素,水素の濃度分布を持つ軽水炉の一
次冷却系全体に対し、計測点のみでの水質を保証するの
にすぎなかつた。
As described in Japanese Patent Application Laid-Open No. 57-3086, the conventional system is provided with a dissolved oxygen / hydrogen concentration measuring device and a corrosion potential measuring system of SUS304 steel in a pipe branched from the recirculation system, and hydrogen is measured according to the measured values. The injection amount was controlled to keep the dissolved oxygen concentration and the corrosion potential within a certain range. However, this method only guarantees the water quality at the measurement points only for the entire primary cooling system of the light water reactor with a constant oxygen and hydrogen concentration distribution.

特に、建設してから数年を経た海外の先行炉では、特に
厳しい条件におかれる炉心材料に対する水質環境を制御
することが望まれている。従来の手法ではこのような必
要性まで満たすことはできない。
In particular, it has been desired to control the water quality environment for the core material under particularly severe conditions in overseas advanced reactors that have been built for several years. Conventional methods cannot meet such needs.

〔発明の目的〕[Object of the Invention]

本発明は、原子炉炉心の水質をモニタする手段を提供
し、そのモニタ値に基づいて水素注入率を精度良く定
め、炉心の水質を最適に制御することを目的とする。
An object of the present invention is to provide means for monitoring the water quality of a nuclear reactor core, accurately determine the hydrogen injection rate based on the monitor value, and optimally control the water quality of the core.

〔発明の概要〕[Outline of Invention]

原子炉炉水中の溶存酸素、溶存水素は、炉心の放射線に
より水分子が分解した結果生じる。発明者らは、原子炉
炉水中の水の放射線分解生物13成分についての40の高速
化学反応を数値的に解析し、系統内の各成分の定常濃度
分布を求める技術を開発してきた。本発明はその技術開
発の過程で見出された水素注入下の過酸化水素と酸素濃
度の関連に関する新しい知見に基づく、すなわち、過酸
化水素濃度の減少は、酸素濃度が極めて低くなつてから
生ずる、との知見に基づきなされたものである。
Dissolved oxygen and dissolved hydrogen in the reactor water are the result of water molecules being decomposed by radiation from the core. The inventors have developed a technique for numerically analyzing 40 rapid chemical reactions of 13 components of radiolytic organisms in water in reactor water and obtaining a steady-state concentration distribution of each component in the system. The present invention is based on a new finding found in the process of technological development regarding the relationship between hydrogen peroxide and oxygen concentration under hydrogen injection, that is, the decrease in hydrogen peroxide concentration occurs after the oxygen concentration becomes extremely low. It was made based on the knowledge of.

本発明は、原子炉、前記原子炉炉心の過酸化水素濃度を
測定する過酸化水素センサー、前記過酸化水素センサー
の出力に基づいて水素注入率を決定する制御装置及び前
記制御装置で決められた水素注入率で前記原子炉に水素
を注入する水素注入装置を有することを特徴とする。
The present invention is determined by a reactor, a hydrogen peroxide sensor that measures the hydrogen peroxide concentration in the reactor core, a controller that determines the hydrogen injection rate based on the output of the hydrogen peroxide sensor, and the controller. It has a hydrogen injection device for injecting hydrogen into the reactor at a hydrogen injection rate.

〔発明の実施例〕Example of Invention

水は炉心の放射線により分解し、水素,酸素,過酸化水
素が生成する。発明者らは、原子炉炉心における水の放
射線分解生成物の濃度を炉心入口から距離をパラメータ
として数値的に解析した。その結果を第2図に示す。水
素,酸素は沸騰が始まると蒸気相に抜け液相の濃度が減
少するが、過酸化水素濃度は沸騰に左右されないことが
わかる。
Water is decomposed by radiation from the core, producing hydrogen, oxygen, and hydrogen peroxide. The inventors numerically analyzed the concentration of radiolysis products of water in the reactor core with the distance from the core inlet as a parameter. The results are shown in FIG. It can be seen that hydrogen and oxygen escape to the vapor phase when boiling starts and the concentration of the liquid phase decreases, but the concentration of hydrogen peroxide does not depend on boiling.

水の放射線分解による酸素の生成は、水素の存在下で抑
えられる。水素注入下における原子炉炉心での液相にお
ける酸素濃度と過酸化水素濃度の数値的解析結果を第3
図に示す。
The production of oxygen by radiolysis of water is suppressed in the presence of hydrogen. Numerical analysis result of oxygen concentration and hydrogen peroxide concentration in liquid phase in reactor core under hydrogen injection
Shown in the figure.

水素注入下においては、酸素濃度は水素注入率を高める
と共になめらかに減少する。一方、過酸化水素濃度はあ
る範囲でほとんど変化しないが、水素注入率増加ととも
に一旦増加し、それから急激に減少する傾向をもつ。も
う少し詳しく見ると、過酸化水素の急激な減少は酸素濃
度が極めて低くなつてからであることがわかる。これは
次の様に理解することができる。すなわち、注入した水
素は、注入率が低いうちは、 H+OH→HO+H (1) H+O→HO (2) HO+HO→H+O (3) 2×((1)+(2))+(3)より 2H+O+2OH→2HO+H (4) のように炉心で生成した酸素が水素と再結合する過程で
過酸化水素を生成する。過酸化水素自身も H+H→HO+OH (5) (1)+(5)により H+H→2HO (6) の反応により減衰するが、反応(5)の速度定数が、反応
(2)の速度に比べて遅いため結局正味の反応としては(4)
の反応が(6)の反応に比べ支配的になるため、水素注入
率の低い側で過酸化水素濃度は変わらないか、増加す
る。一方、水素注入率が高くなり、酸素濃度が低くなる
と(2)に代わつて(5)が支配的となり、正味の反応として
は専ら(6)が進行する。酸素が消滅してから過酸化水素
が急激に減少する現象は以上のように理解できる。
Under the hydrogen injection, the oxygen concentration increases smoothly with the increase of the hydrogen injection rate. On the other hand, the hydrogen peroxide concentration hardly changes within a certain range, but it tends to increase once with the increase of the hydrogen injection rate, and then to decrease sharply. Taking a closer look, it can be seen that the sharp decrease in hydrogen peroxide occurs after the oxygen concentration becomes extremely low. This can be understood as follows. That is, the injected hydrogen is H 2 + OH → H 2 O + H (1) H + O 2 → HO 2 (2) HO 2 + HO 2 → H 2 O 2 + O 2 (3) 2 × (( From 1) + (2)) + (3), hydrogen peroxide is generated in the process of recombining oxygen generated in the core with hydrogen like 2H 2 + O 2 + 2OH → 2H 2 O + H 2 O 2 (4). Hydrogen peroxide itself is also attenuated by the reaction of H 2 + H 2 O 2 → 2H 2 O (6) due to H + H 2 O 2 → H 2 O + OH (5) (1) + (5), but the rate of reaction (5) Constant but reaction
As a result, the net reaction is (4)
Since the reaction of becomes more dominant than the reaction of (6), the hydrogen peroxide concentration does not change or increases on the side where the hydrogen injection rate is low. On the other hand, when the hydrogen injection rate becomes high and the oxygen concentration becomes low, (5) becomes dominant instead of (2), and (6) proceeds exclusively as a net reaction. The phenomenon in which hydrogen peroxide sharply decreases after the disappearance of oxygen can be understood as described above.

炉水中の酸素濃度を直接モニタすることは以下の理由で
困難である。
Direct monitoring of oxygen concentration in reactor water is difficult for the following reasons.

1 第2図で示したように、酸素は沸騰下で蒸気相と液
相とに分布するため、両相を分離して測定することは難
しい。
1. As shown in FIG. 2, oxygen is distributed in the vapor phase and the liquid phase under boiling, so it is difficult to measure both phases separately.

2 数十ppb以下の溶存酸素濃度を正確に測定すること
は難しい。
2 It is difficult to accurately measure the dissolved oxygen concentration below several tens of ppb.

本発明は、過酸化水素の以上の性質を利用して酸度濃度
を直接モニタするのではなく、過酸化水素濃度をモニタ
して酸素濃度を制御するもので、具体的には、第3図か
ら分かるように、過酸化水素濃度が、水素注入をしない
通常運転時より低くなる程度の水素を注入するもので、
このように水素注入率を定めることにより、SCC(応力
腐食割れ)が発生しないとされている溶存酸素濃度5〜
10ppbが自動的に保証される。
The present invention does not directly monitor the acidity concentration by utilizing the above properties of hydrogen peroxide, but monitors the hydrogen peroxide concentration to control the oxygen concentration. Specifically, from FIG. As you can see, hydrogen peroxide is injected so that the hydrogen peroxide concentration is lower than that during normal operation without hydrogen injection.
By determining the hydrogen injection rate in this way, the dissolved oxygen concentration of 5 to which SCC (stress corrosion cracking) does not occur
10ppb is automatically guaranteed.

以下、本発明の一実施例を第1図により説明する。第1
図では過酸化水素センサ5を例えば中性子計装管等を介
して炉心に設け、信号処理装置6に接続した制御装置7
により水素注入装置8からの水素注入率を制御する。
An embodiment of the present invention will be described below with reference to FIG. First
In the figure, a hydrogen peroxide sensor 5 is provided in the reactor core via, for example, a neutron instrumentation tube, and a controller 7 connected to a signal processor 6 is provided.
The hydrogen injection rate from the hydrogen injection device 8 is controlled by.

過酸化水素センサとしては、紫外吸光度モニタによるも
のが次の点で有効である。
As the hydrogen peroxide sensor, an ultraviolet absorbance monitor is effective in the following points.

1 波長を190〜250nm程度にすれば、同時に存在する水
素,酸素の妨害をうけない。
1 If the wavelength is set to 190-250 nm, it will not be interfered by hydrogen and oxygen existing at the same time.

2 水の放射線分解生成物は、第4図に示すように波長
を190〜300nmの紫外領域に吸収を持つことはよく知られ
ているが、第2図に示すように実炉環境では過酸化水素
の吸光度測定に妨害となりうる成分は極めて低濃度であ
り、問題にならない。
2 It is well known that the radiolysis products of water have absorption in the ultraviolet region of 190 to 300 nm as shown in Fig. 4, but as shown in Fig. 2, they are peroxidized in the actual reactor environment. The components that may interfere with the measurement of the absorbance of hydrogen are extremely low in concentration, which is not a problem.

3 過酸化水素は、液相のみに存在するので、気液二相
流の中で液相のみの情報をとり出せばよい。
3 Since hydrogen peroxide exists only in the liquid phase, it is only necessary to extract information on the liquid phase in the gas-liquid two-phase flow.

センサー構造を第5図に示す。吸光部18は炉水中に浸漬
し、入射紫外パルスを石英窓21を介し吸光部18に入射す
る。光パルスはミラー19により反射され、ハーフミラー
12を介して他方の窓より、減衰光パルス量を計測し、吸
光度を求める。石英窓20,15、13のように3段以上の構
造とし、窓20,15の間にガス(190〜250nmの波長範囲に
吸収をもたないもの、例えばN)を詰め、ベローズ17
にり炉水の微少な圧力変動を吸収する。石英窓15と13の
間隙は、炉水圧力と同じになるようにガスを詰める。最
終段の窓13は、冷却フイン14により十分低温に保つ。こ
のようにすることにより、窓20のシール材として、高温
には強いもの(例えば、メタライズ加工など機械的な応
力が加わつた時シール性が悪くてもよい)、窓13のシー
ル材として機械的変形には強いもの(例えば四フツ化エ
チレンなど、耐熱性が悪くてもよい)を用いることがで
き信頼性が向上する。この過酸化水素センサー5によっ
て、過酸化水素濃度は次のように測定される。炉水は、
吸光部18に入る。石英窓21から入射された光パルス石英
窓13、15間を減衰なく透過し、吸光部18に入射される。
吸光部18では、光パルスは過酸化水素水濃度に応じて吸
収される。従って、ミラー19に反射して、ハーフミラー
12を介して得られる光パルスの減衰量は、過酸化水素水
の濃度を表すことになる。なお、22は原子炉圧力容器壁
を示す。
The sensor structure is shown in FIG. The light absorbing part 18 is immersed in reactor water, and an incident ultraviolet pulse is made incident on the light absorbing part 18 through a quartz window 21. The light pulse is reflected by the mirror 19 and the half mirror
The attenuation light pulse amount is measured from the other window via 12 to obtain the absorbance. It has a structure of three or more stages such as quartz windows 20, 15 and 13, and a gas (a material which does not have absorption in the wavelength range of 190 to 250 nm, for example, N 2 ) is packed between the windows 20 and 15 and bellows 17
Absorbs minute pressure fluctuations in the water of the seaweed. The gap between the quartz windows 15 and 13 is filled with gas so as to be the same as the reactor water pressure. The window 13 at the final stage is kept at a sufficiently low temperature by the cooling fins 14. By doing so, a sealing material for the window 20 that is resistant to high temperatures (for example, the sealing property may be poor when mechanical stress such as metallization is applied), or a sealing material for the window 13 is mechanical. A material that is strong in deformation (for example, ethylene tetrafluoride or the like, which may have poor heat resistance) can be used, and reliability is improved. The hydrogen peroxide concentration is measured by the hydrogen peroxide sensor 5 as follows. The reactor water is
Enters the light absorption section 18. The optical pulse incident from the quartz window 21 is transmitted between the quartz windows 13 and 15 without attenuation and is incident on the light absorption section 18.
In the light absorption unit 18, the light pulse is absorbed according to the hydrogen peroxide solution concentration. Therefore, it reflects on the mirror 19 and becomes a half mirror.
The attenuation of the light pulse obtained via 12 will represent the concentration of hydrogen peroxide solution. Reference numeral 22 indicates a wall of the reactor pressure vessel.

本実施例によれば、過酸化水素濃度を監視し水素注入し
ない通常運転時より低く保つよう水素注入率を選定する
ことにより、炉水中の溶存酸素濃度は5〜10ppbのレベ
ルに抑えることができSCC抑制に有効な炉水環境を実現
できる。
According to the present embodiment, the concentration of dissolved oxygen in the reactor water can be suppressed to a level of 5 to 10 ppb by monitoring the hydrogen peroxide concentration and selecting the hydrogen injection rate so as to keep it lower than that during normal operation in which hydrogen is not injected. A reactor water environment effective for SCC control can be realized.

第6図は、本実施例の別な実施例を示す。第6図では、
再循環系配管2の溶存酸素濃度をさらに効率よく下げる
ために、過酸化水素注入装置11が設けてある。再循環系
配管2に溶存酸素計9を設け、過酸化水素注入装置11か
らの注入量を不必要に大きくしないよう制御装置10によ
り制御することができる。
FIG. 6 shows another embodiment of this embodiment. In Figure 6,
A hydrogen peroxide injection device 11 is provided in order to more efficiently reduce the dissolved oxygen concentration in the recirculation system pipe 2. A dissolved oxygen meter 9 is provided in the recirculation system pipe 2 and can be controlled by the controller 10 so as not to unnecessarily increase the injection amount from the hydrogen peroxide injection device 11.

過酸化水素注入により溶存酸素濃度が減少するのは、過
酸化水素の熱分解によりOH基が生成しこのOH基が次の反
応を促進する。すなわち、 H→2OH (7) H+OH→HO+H (1) H+O→HO (2) HO+HO→H+O (3) となり、(7)+2((1)+(2))+(3)より 2H+O→2HO (8) のように過酸化水素が触媒的な役割を果して注入した水
素と炉水中の溶存酸素の再結合を促進し、その結果、溶
存酸素濃度を低下させる。
Dissolved oxygen concentration decreases due to hydrogen peroxide injection because OH group is generated by thermal decomposition of hydrogen peroxide, and this OH group promotes the next reaction. That is, H 2 O 2 → 2OH (7) H 2 + OH → H 2 O + H (1) H + O 2 → HO 2 (2) HO 2 + HO 2 → H 2 O 2 + O 2 (3) and (7) +2 ( From (1) + (2)) + (3), hydrogen peroxide plays a catalytic role like 2H 2 + O 2 → 2H 2 O (8) and recombines the injected hydrogen and dissolved oxygen in the reactor water. Promotes, resulting in a decrease in dissolved oxygen concentration.

本実施例によれば、炉心のみならず再循環系配管の溶存
酸素濃度もSCC抑制に有効な十分に低い値に維持するこ
とが可能となる。
According to this example, it is possible to maintain not only the core but also the dissolved oxygen concentration in the recirculation system pipe at a sufficiently low value effective for SCC suppression.

〔発明の効果〕〔The invention's effect〕

以上のように本発明によれば、原子炉炉心の溶存酸素濃
度5〜10ppbの制御が可能となり、原子炉の安全性、稼
働率向上の大きな効果がある。
As described above, according to the present invention, it becomes possible to control the dissolved oxygen concentration of the reactor core of 5 to 10 ppb, and there is a great effect of improving the safety and operating rate of the reactor.

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

第1図は本発明の一実施例の構成図、第2図は、炉心の
蒸気相と液相における水の放射線分解生成物の濃度の計
算値を示す線図、第3図は炉心出口における水素、酸
素、過酸化水素の濃度の計算値の線図、第4図は水の放
射線分解生成物の吸光度のグラフ、第5図は本発明のセ
ンサの実施例の構成図、第6図は本発明の他の実施例の
構成図である。 1……原子炉圧力容器、2……再循環配管、3……給水
配管、4……主蒸気系配管、5……過酸化水素センサ、
6……信号処理部、7……制御部、8……水素注入装
置、9……溶存酸素計、12……ハーフミラー、13……石
英窓、14……冷却フイン、15……石英窓、18……吸光
部、19……ミラー、20……石英窓、23……炉水。
FIG. 1 is a configuration diagram of an embodiment of the present invention, FIG. 2 is a diagram showing calculated values of concentrations of radiolysis products of water in a vapor phase and a liquid phase of a core, and FIG. 3 is at a core outlet. Diagrams of calculated values of concentrations of hydrogen, oxygen and hydrogen peroxide, FIG. 4 is a graph of absorbance of radiolysis products of water, FIG. 5 is a configuration diagram of an embodiment of the sensor of the present invention, and FIG. 6 is It is a block diagram of the other Example of this invention. 1 ... Reactor pressure vessel, 2 ... Recirculation pipe, 3 ... Water supply pipe, 4 ... Main steam system pipe, 5 ... Hydrogen peroxide sensor,
6 ... Signal processing part, 7 ... control part, 8 ... hydrogen injection device, 9 ... dissolved oxygen meter, 12 ... half mirror, 13 ... quartz window, 14 ... cooling fin, 15 ... quartz window , 18 ... Absorber, 19 ... Mirror, 20 ... Quartz window, 23 ... Reactor water.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 唐沢 英年 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 (72)発明者 長瀬 誠 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60−220898(JP,A) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Hidetoshi Karasawa 1168 Moriyama-cho, Hitachi City, Ibaraki Prefecture Hiritsu Manufacturing Co., Ltd. Energy Research Institute (72) Makoto Nagase 1168 Moriyama-cho, Hitachi City, Ibaraki Prefecture Hitsuritsu Co., Ltd. (56) Reference Japanese Patent Laid-Open No. 60-220898 (JP, A)

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】原子炉、前記原子炉炉水の過酸化水素濃度
を測定する過酸化水素センサー、前記過酸化水素センサ
ーの出力に基づいて、前記炉水の過酸化水素濃度が水素
注入前の炉水の過酸化水素濃度と概ね等しくなるように
水素注入率を決定する制御装置、及び前記制御装置で決
められた水素注入率で前記原子炉に水素を注入する水素
注入装置を有することを特徴とする原子炉水質制御シス
テム。
1. A reactor, a hydrogen peroxide sensor for measuring the hydrogen peroxide concentration of the reactor water, and the hydrogen peroxide concentration of the reactor water before hydrogen injection based on the output of the hydrogen peroxide sensor. It has a control device that determines the hydrogen injection rate so as to be approximately equal to the hydrogen peroxide concentration of the reactor water, and a hydrogen injection device that injects hydrogen into the reactor at the hydrogen injection rate determined by the control device. Reactor water quality control system.
【請求項2】前記制御装置は、前記炉水の過酸化水素濃
度が水素注入前の炉水の過酸化水素濃度に比べて高いと
きは水素注入率を増加させ、低いときは水素注入率を減
少させることを特徴とする特許請求の範囲第1項に記載
の原子炉水質制御システム。
2. The control device increases the hydrogen injection rate when the hydrogen peroxide concentration of the reactor water is higher than the hydrogen peroxide concentration of the reactor water before hydrogen injection, and increases the hydrogen injection rate when it is low. The reactor water quality control system according to claim 1, wherein the system is reduced.
【請求項3】前記過酸化水素センサーは波長が190〜250
nmの検出光を有する紫外吸光度モニタであることを特徴
とする特許請求の範囲第1項に記載の原子炉水質制御シ
ステム。
3. The hydrogen peroxide sensor has a wavelength of 190 to 250.
The reactor water quality control system according to claim 1, which is an ultraviolet absorbance monitor having detection light of nm.
JP60264904A 1985-11-27 1985-11-27 Reactor water quality control system Expired - Lifetime JPH0664185B2 (en)

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Application Number Priority Date Filing Date Title
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Publications (2)

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JPS62126398A JPS62126398A (en) 1987-06-08
JPH0664185B2 true JPH0664185B2 (en) 1994-08-22

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Publication number Priority date Publication date Assignee Title
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JPS62126398A (en) 1987-06-08

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