JPS59115998A - Condenser in atomic power plant - Google Patents

Condenser in atomic power plant

Info

Publication number
JPS59115998A
JPS59115998A JP22444082A JP22444082A JPS59115998A JP S59115998 A JPS59115998 A JP S59115998A JP 22444082 A JP22444082 A JP 22444082A JP 22444082 A JP22444082 A JP 22444082A JP S59115998 A JPS59115998 A JP S59115998A
Authority
JP
Japan
Prior art keywords
condenser
iron oxide
steam
oxide film
hot well
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.)
Pending
Application number
JP22444082A
Other languages
Japanese (ja)
Inventor
Yukio Henmi
逸見 幸雄
Minoru Akimoto
実 秋元
Shinji Kashibe
樫部 信司
Katsutoshi Azuma
東 克俊
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.)
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co 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 Nippon Genshiryoku Jigyo KK, Nippon Atomic Industry Group Co Ltd filed Critical Nippon Genshiryoku Jigyo KK
Priority to JP22444082A priority Critical patent/JPS59115998A/en
Publication of JPS59115998A publication Critical patent/JPS59115998A/en
Pending legal-status Critical Current

Links

Classifications

    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28FDETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F19/00Preventing the formation of deposits or corrosion, e.g. by using filters or scrapers
    • F28F19/02Preventing the formation of deposits or corrosion, e.g. by using filters or scrapers by using coatings, e.g. vitreous or enamel coatings
    • F28F19/06Preventing the formation of deposits or corrosion, e.g. by using filters or scrapers by using coatings, e.g. vitreous or enamel coatings of metal

Abstract

PURPOSE:To obtain a condenser having improved corrosion resistance for lessening the amount of Fe to be released in the hot well portion for atomic power plants by forming black iron oxide film having excellent corrosion resistance on the surface to be brought in contact with liquid of the main condenser. CONSTITUTION:A black iron oxide film 3 is provided on the inner surface of the hot well 2 of a condenser 1 by contacting the inner surface of the hot well 2 of the main condenser 1 made of a carbon steel or low-alloy steel with oxygen- containing steam (5-10kg/cm<2>) of 100 deg.C or higher, e.g., of 140-170 deg.C, for 100- 500hr, usually for 200-400hr. Since the portion other than the hot well 2 of the main condenser 1, e.g., the cooling tube 4, outer surface of a support plate 5, and inner surface of the body cylinder 6, is touched by usual high-temperature steam during the operation of unclear reactor, no pretreatment with steam is needed for the portion.

Description

【発明の詳細な説明】 [発明の技術分野] 本発明8は、原子力発電所における復水装置に関する。[Detailed description of the invention] [Technical field of invention] The present invention 8 relates to a condensing device in a nuclear power plant.

[発明の技術的背景コ 冷却材として軽水を使用する原子力発電所、例えば沸騰
水形原子力発電所においては、原子炉圧力容器において
軽水を直接加熱して蒸気を発生させ、この蒸気で蒸気タ
ービンを駆動させた後、排出された蒸気は主復水器にお
いて復水とし、給水加熱器を経て吸水ポンプにより再び
原子炉圧力容器に送られるようにされている。
[Technical Background of the Invention] In nuclear power plants that use light water as a coolant, such as boiling water nuclear power plants, light water is directly heated in the reactor pressure vessel to generate steam, and this steam is used to drive a steam turbine. After operation, the discharged steam is converted into condensate in the main condenser, and is sent to the reactor pressure vessel again by a water suction pump via a feed water heater.

しかしてこのサイクルにおいて、機器・配管等を構成す
る鉄系含金は、軽水中の含有酸素により徐々に酸化され
、その一部は微細な酸化鉄やイオンの状態で冷却材中に
放出されるようになる。
However, during the lever cycle, the iron-based metals that make up the equipment, piping, etc. are gradually oxidized by the oxygen contained in the light water, and some of them are released into the coolant in the form of fine iron oxides and ions. It becomes like this.

このような微細な酸化鉄やイオンが冷却材中に放出され
ると炉心において放射化されるため、従来から特に鉄分
の放出量の多い主復水器の後段に復水浄化系を配置して
放出された鉄分を除去することが行なわれている。
If such fine iron oxides and ions are released into the coolant, they become radioactive in the reactor core, so conventionally a condensate purification system has been placed after the main condenser where a particularly large amount of iron is released. Efforts are being made to remove the released iron.

[背領技術の問題点コ しかしながら、このような冷却材中に放出された酸化鉄
を復水浄化系を用いて除去したとしても、偶良を抑制り
ることにはならないから、本質的な解決手段とはならな
い。
[Problems with backlash technology]However, even if iron oxide released into the coolant is removed using a condensate purification system, it will not suppress backlash, so It is not a solution.

さらに放出される鉄分が多いときは、復水浄化系の負担
が大きくなり、また処理すべき固形廃棄物の吊が多くな
るという難点がある。
Furthermore, when a large amount of iron is released, the burden on the condensate purification system increases, and there are also disadvantages in that a large amount of solid waste must be suspended.

[発明の目的] 本発明者等は、かかる従来の難点を解消すべく鋭意研究
をすずめたところ、鉄分の放出量の多い主復水器にd3
い−Cも、高温蒸気の接する部分には、耐食性の優れた
黒色酸化鉄被膜(Fe3o4)が形成され鉄分の放出量
が少なくなっており、一方ボットウエル表面のにうに比
較的温度の低い、復水と接する表面には耐食性の劣った
黒色酸化鉄(Fe304)や赤色酸化鉄(α−Fe 2
03 )が形成されて全鉄分放出量のうちがなりの部分
がここで放出されていることを見出した。
[Purpose of the Invention] The inventors of the present invention conducted intensive research in order to resolve these conventional difficulties, and found that d3
In the case of I-C, a black iron oxide film (Fe3O4) with excellent corrosion resistance is formed on the parts that come in contact with high-temperature steam, reducing the amount of iron released. The surface that comes into contact with water contains black iron oxide (Fe304) and red iron oxide (α-Fe2), which have poor corrosion resistance.
03) was formed, and it was found that a small portion of the total amount of iron released was released here.

本発明は、かかる知見に基いてなされたもので、特にホ
ットウェルの部分の耐食性が改良された鉄族出量の少な
い原子力発電所における復水装置く本明細書では主復水
器と復水配管の両者を総称して復水装置という)を提供
しようとするものである。
The present invention has been made based on this knowledge, and is a condensing device for a nuclear power plant with a low amount of iron, in which the corrosion resistance of the hot well portion is particularly improved. Both pipes are collectively referred to as a condensate device).

[発明の概要] 本発明は、上記目的を達成するため、原子炉圧力容器で
発生され蒸気タービンを通過した蒸気を復水にする接液
表面が鉄系合金からなる主復水器を備えた復水装置にお
いて、前記主復水器の接液表面に耐食性の優れた黒色酸
化鉄被膜を形成させて成ることを特徴としている。
[Summary of the Invention] In order to achieve the above object, the present invention includes a main condenser whose wetted surface is made of an iron-based alloy, which condenses steam generated in a reactor pressure vessel and passed through a steam turbine. The condenser device is characterized in that a black iron oxide coating with excellent corrosion resistance is formed on the liquid contact surface of the main condenser.

[発明の実施例] 以下本発明の一実施例を図面を参照して説明する。[Embodiments of the invention] An embodiment of the present invention will be described below with reference to the drawings.

第1図は、本発明の復水装置を概略的に示す側断面図で
ある。この復水装置1のホットウェル2の内表面には黒
色酸化鉄被膜3が設けられている。
FIG. 1 is a side sectional view schematically showing a condensing device of the present invention. A black iron oxide coating 3 is provided on the inner surface of the hot well 2 of this condensing device 1.

この黒色酸化鉄被膜3は、炭素鋼あるいは低合金鋼等か
らなる主復水器1ゐホットウェル2の内表面をioo’
c以上、例えば140〜17o℃の温度の酸素を含む蒸
気(5〜10hg/c+/)と1゜0〜500時間、通
常は200〜400時間接触させることにより形成させ
ることができる。主復水器1のホラ[ヘラ1ル2以外の
部分、例えば冷却管4、さざえ板5の外表面、本体胴6
の内表面等は、原子炉の運転時常時高温の蒸気が接触す
るので必ずしも事前に蒸気の処理を行なう必要はないが
、必要に応じて事前に処理を施すことも勿論差支えない
。なお、図にあいC符号7.8は水室、9は冷却水入口
、10は冷却水出口、11は蒸気入口、12は復水用1
コである。
This black iron oxide coating 3 coats the inner surface of the main condenser 1 and hot well 2 made of carbon steel or low alloy steel.
It can be formed by contacting with oxygen-containing steam (5 to 10 hg/c+/) at a temperature of 1°C or higher, for example 140 to 17°C, for 1° to 500 hours, usually 200 to 400 hours. Hole of the main condenser 1 [portions other than the spatula 1, e.g.
Since the inner surface of the reactor is always in contact with high-temperature steam during operation of the nuclear reactor, it is not necessarily necessary to pre-treat the steam, but it is of course possible to pre-treat the inner surface if necessary. In the figure, C code 7.8 is the water chamber, 9 is the cooling water inlet, 10 is the cooling water outlet, 11 is the steam inlet, and 12 is the condensate water 1.
It is Ko.

ボットウェル2の内面部分のみに酸化処理を施すには、
主復水器1の設置前にそのままあるいは設置後冷却包゛
4の部分を例えば遮蔽板で覆ってホットウェル2内に直
接100℃以上の酸素を含有する蒸気を導入するように
すればよい。この酸化処理に使用する蒸気は主蒸気管に
バイパス管を接続して主蒸気を導入づるようにし−Cも
よく、ハウスボイラーから蒸気管を用いて導入するよう
にし【もよい。
To perform oxidation treatment only on the inner surface of Botwell 2,
Before installing the main condenser 1, the cooling envelope 4 may be directly introduced into the hot well 2 at a temperature of 100° C. or higher by covering the cooling envelope 4 with a shielding plate, for example, or after the installation. The steam used for this oxidation treatment may be introduced by connecting a bypass pipe to the main steam pipe, or may be introduced from the house boiler using a steam pipe.

このようにして黒色酸化鉄被膜の形成された主復水器は
、以下の模擬実験からも明らかなように耐食性に極めて
優れている。
The main condenser with the black iron oxide film formed in this way has extremely excellent corrosion resistance, as is clear from the following simulation experiment.

(耐食性の試験) 34 、5 mm x 46 mm X 2 mmの炭
素m(38−41)をD lN5095−1592 (
120番またはそれより細かいもの〉のエメリペーパで
表面仕上げし、アルコール中で15分間超音波洗浄を行
なった後、これを20mJ2の純水を入れたオー1−ク
レープニ入h150℃で340時間加熱加圧して表面に
黒色の酸化鉄被膜を形成させた。
(Corrosion Resistance Test) Carbon m(38-41) of 34 mm x 46 mm x 2 mm was coated with D lN5095-1592 (
The surface was finished with emery paper of No. 120 or finer, and after ultrasonic cleaning in alcohol for 15 minutes, it was heated and pressurized at 150℃ for 340 hours in an O-1-crepe tube containing 20mJ2 of pure water. A black iron oxide film was formed on the surface.

この黒色の酸化鉄被膜を有する炭素鋼をX線解析装置に
より分析したところFe3O4が形成されていることが
確認された。
When this carbon steel having a black iron oxide coating was analyzed using an X-ray analyzer, it was confirmed that Fe3O4 was formed.

次にこの黒色酸化鉄被膜を生成させた試料と超音波洗浄
までを行ない黒色酸化鉄被膜を形成させなかった比較試
料とを原子炉の復水条件下にさらし、定期的にサンプリ
ングを行ない鉄放出率を求めた。なお、放出量の定量は
、腐食試験槽出口側からループ水を定期的にサンプリン
グしく0.4μmニュークリポアフィルターく1枚)、
イオン交換フィルター(カチオン2枚、アニオン2枚)
使用)原子吸光d1により鉄を定量した。
Next, the sample on which this black iron oxide film was formed and a comparison sample that had not been formed with a black iron oxide film through ultrasonic cleaning were exposed to the condensate conditions of a nuclear reactor, and regular sampling was performed to release iron. The rate was calculated. In addition, to quantify the amount released, periodically sample the loop water from the outlet side of the corrosion test tank (with one 0.4 μm Nuclepore filter).
Ion exchange filter (2 cations, 2 anions)
Use) Iron was determined by atomic absorption d1.

測定結果を第2図のグラフに示す。第2図から明らかな
ように黒色酸化被膜を形成した試料の鉄放出率は徐々に
増加していぎ、550時間経過で40MDM (11,
(/dm2/month )となり、これから徐々に減
少しU300〜900時間経過後は約30 M D M
 T”はは安定した。また放出鉄はほとんどイオン状で
あり、クラッド等は検出限界以下であった。これに対し
°C黒色酸化鉄被膜を有しない試料の鉄放出率は第2図
から明らかなようにほぼ65MDMであった。
The measurement results are shown in the graph of FIG. As is clear from Figure 2, the iron release rate of the sample with a black oxide film gradually increased, and after 550 hours, the iron release rate was 40MDM (11,
(/dm2/month), and it gradually decreases from then on to about 30 M D M after U300 to 900 hours have elapsed.
T" was stable. In addition, most of the released iron was in ionic form, and cladding was below the detection limit. In contrast, the iron release rate of the sample without the °C black iron oxide film is clear from Figure 2. As such, it was approximately 65MDM.

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

第1図は本発明の復水装置を概略的に示J−側断面図、
第2図は本発明の効果を確認するための模擬実験のにd
5 Lプる鉄放出率を示づグラフである。 1・・・・・・・・・・・・主復水器 2・・・・・・・・・・・・ホッ]ヘウエル3・・・・
・・・・・・・・黒色酸化鉄買被膜4・・・・・・・・
・・・・冷却管 5・・・・・・・・・・・・管ささえ板6・・・・・・
・・・・・・本体胴 代理人弁理士   須 山 佐 −
FIG. 1 schematically shows the condensing device of the present invention, a J-side sectional view,
Figure 2 shows a mock experiment to confirm the effects of the present invention.
5 is a graph showing the iron release rate of 5 L. 1... Main condenser 2... Howell] Hewell 3...
・・・・・・・・・Black iron oxide coating 4・・・・・・・・・
...Cooling pipe 5...Pipe support plate 6...
・・・・・・Patent attorney representing the main body: Satoshi Suyama −

Claims (3)

【特許請求の範囲】[Claims] (1)原子炉j圧力容器で発生され蒸気タービンを通過
した蒸気を復水にする接液表面が鉄系合金からなる主復
水器を備えた復水装置において、前記主復水器の接液表
面に黒色酸化鉄被膜を形成させで成ることを特徴とする
原子力発電所における復水装置。
(1) In a condensing device equipped with a main condenser whose wetted surface is made of an iron-based alloy, the steam that is generated in the reactor j pressure vessel and passed through the steam turbine is condensed. A condensing device for a nuclear power plant characterized by forming a black iron oxide film on the liquid surface.
(2)鉄系合金は、炭素鋼または低合金鋼からなる特許
請求の範囲第1項記載の原子力発電所における復水装置
(2) The condensing device in a nuclear power plant according to claim 1, wherein the iron-based alloy is made of carbon steel or low alloy steel.
(3)黒色酸化鉄被膜は、Fe3O4から成る特許請求
の範囲第1項または第2項記載の原子力発電所における
復水装置。
(3) A condensing device in a nuclear power plant according to claim 1 or 2, wherein the black iron oxide film is made of Fe3O4.
JP22444082A 1982-12-21 1982-12-21 Condenser in atomic power plant Pending JPS59115998A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP22444082A JPS59115998A (en) 1982-12-21 1982-12-21 Condenser in atomic power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP22444082A JPS59115998A (en) 1982-12-21 1982-12-21 Condenser in atomic power plant

Publications (1)

Publication Number Publication Date
JPS59115998A true JPS59115998A (en) 1984-07-04

Family

ID=16813799

Family Applications (1)

Application Number Title Priority Date Filing Date
JP22444082A Pending JPS59115998A (en) 1982-12-21 1982-12-21 Condenser in atomic power plant

Country Status (1)

Country Link
JP (1) JPS59115998A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6321590A (en) * 1986-07-16 1988-01-29 株式会社東芝 Fuel aggregate
US7165418B2 (en) * 1995-10-06 2007-01-23 Hitachi, Ltd. Absorption refrigerator and production method thereof

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57139288A (en) * 1981-02-23 1982-08-28 Hitachi Ltd Hot well of main condenser

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57139288A (en) * 1981-02-23 1982-08-28 Hitachi Ltd Hot well of main condenser

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6321590A (en) * 1986-07-16 1988-01-29 株式会社東芝 Fuel aggregate
US7165418B2 (en) * 1995-10-06 2007-01-23 Hitachi, Ltd. Absorption refrigerator and production method thereof

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