JPS6226439B2 - - Google Patents
Info
- Publication number
- JPS6226439B2 JPS6226439B2 JP54126429A JP12642979A JPS6226439B2 JP S6226439 B2 JPS6226439 B2 JP S6226439B2 JP 54126429 A JP54126429 A JP 54126429A JP 12642979 A JP12642979 A JP 12642979A JP S6226439 B2 JPS6226439 B2 JP S6226439B2
- Authority
- JP
- Japan
- Prior art keywords
- corrosion
- specific conductivity
- water
- carbon steel
- cooling system
- 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
Links
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 30
- 229910052760 oxygen Inorganic materials 0.000 claims description 30
- 239000001301 oxygen Substances 0.000 claims description 30
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 23
- 238000001816 cooling Methods 0.000 claims description 22
- 229910000975 Carbon steel Inorganic materials 0.000 claims description 19
- 239000010962 carbon steel Substances 0.000 claims description 19
- 239000011347 resin Substances 0.000 claims description 14
- 229920005989 resin Polymers 0.000 claims description 14
- 238000002347 injection Methods 0.000 claims description 10
- 239000007924 injection Substances 0.000 claims description 10
- 238000000034 method Methods 0.000 claims description 5
- 238000005536 corrosion prevention Methods 0.000 claims description 4
- 238000011033 desalting Methods 0.000 claims description 3
- 230000007797 corrosion Effects 0.000 description 35
- 238000005260 corrosion Methods 0.000 description 35
- 239000000498 cooling water Substances 0.000 description 15
- LPXPTNMVRIOKMN-UHFFFAOYSA-M sodium nitrite Chemical compound [Na+].[O-]N=O LPXPTNMVRIOKMN-UHFFFAOYSA-M 0.000 description 10
- 238000010612 desalination reaction Methods 0.000 description 9
- 239000000126 substance Substances 0.000 description 8
- 239000000463 material Substances 0.000 description 6
- 235000010288 sodium nitrite Nutrition 0.000 description 5
- 229910000881 Cu alloy Inorganic materials 0.000 description 4
- 239000000470 constituent Substances 0.000 description 4
- 239000000203 mixture Substances 0.000 description 4
- 238000002474 experimental method Methods 0.000 description 3
- 239000003112 inhibitor Substances 0.000 description 3
- 239000007788 liquid Substances 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 239000003957 anion exchange resin Substances 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000002328 demineralizing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
- 230000004580 weight loss Effects 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Description
本発明は原子炉補機冷却系の防食方法に関す
る。
原子炉発電装置においては、タービンを駆動す
るためのメインラインの外、各種の補機が設けら
れており、各種の補機すなわち冷却対象系に対し
ては、メインラインの冷却系とは別個の冷却系統
が設けられる。このような補機冷却対象系に対す
る冷却系統は一般に第１図に示す手段により構成
される。第１図において、１は熱交換器、２はポ
ンプ、３は薬注ライン、４はサージタンク、５は
冷却対象系である。この補機冷却系の構成材料は
ステンレス鋼、炭素鋼、銅合金等より成り、たえ
ず循環冷却水にさらされた状態にある。そしてこ
の構成材料の腐食を抑制するために薬注ライン３
により腐食抑制剤として亜硝酸ソーダを添加して
水を循環させ保管していた。しかし、亜硝酸ソー
ダは金属材料の不働態化剤であるので、もしその
量が消耗等による損失のため充分でないと、かえ
つて腐食を促進する結果となる。そのために冷却
系の構成材料を不働態化するのに充分な量、すな
わち臨界濃度を維持するために厳密な水質管理が
必要となる。又冷却系統内の配管、機器等の検査
の場合には系統内の亜硝酸ソーダを含有する水を
一旦廃液処理系へ排水して処理するために亜硝酸
ソーダの存在に基いて廃液処理系の負担が大きく
なるという欠点がある。
本発明は前記欠点を解決するためになされたも
ので、その目的は薬注ラインを有しない新規な原
子炉補機冷却系の防食方法を提供することであ
る。
本発明について概説すると、本発明は構成材料
が炭素鋼又はアルブラツクより成る原子炉補機冷
却系に脱塩樹脂塔及び脱塩樹脂塔の流量を調節す
るバイパス並に酸素注入装置を設けて、酸素注入
により循環水の溶存酸素濃度を30ppbないし
10000ppbに維持し、かつ循環水の比電導度を0.3
μＳ／cm以下に維持することを特徴とする原子炉
補機冷却系の防食方法に関する。
本発明者等は前述した原子炉補機冷却系の構成
材料中、特に腐食損傷が大きいと推定される材料
である炭素鋼（JIS Ｓ S41、化学組成は第１表
参照）及び銅合金であるアルブラツク（JIS
BSTF2、化学組成は第２表参照）について凝似
補機冷却系冷却水（以下単に冷却水という）中の
腐食速度を多角的に検討したところ次の実験結果
が得られた。
炭素鋼の腐食速度と比電導度との関係
（なお比電導度はS.I単位μＳ／cmで示した
が、μＵ／cmと同義である。）
炭素鋼の化学組成
The present invention relates to a corrosion prevention method for a nuclear reactor auxiliary cooling system. In a nuclear reactor power generation system, various auxiliary machines are installed in addition to the main line for driving the turbine, and the various auxiliary machines, that is, the systems to be cooled, are operated separately from the main line cooling system. A cooling system is provided. A cooling system for such an auxiliary equipment cooling target system is generally constructed by the means shown in FIG. In FIG. 1, 1 is a heat exchanger, 2 is a pump, 3 is a chemical injection line, 4 is a surge tank, and 5 is a system to be cooled. The components of this auxiliary cooling system are made of stainless steel, carbon steel, copper alloy, etc., and are constantly exposed to circulating cooling water. In order to suppress corrosion of this constituent material, chemical injection line 3
Therefore, sodium nitrite was added as a corrosion inhibitor and water was circulated during storage. However, since sodium nitrite is a passivating agent for metal materials, if the amount is not sufficient due to loss due to wear and the like, it will result in accelerated corrosion. Therefore, strict water quality control is required to maintain a sufficient amount, or critical concentration, to passivate the constituent materials of the cooling system. In addition, when inspecting piping, equipment, etc. in the cooling system, water containing sodium nitrite in the system is first drained to the waste liquid treatment system for treatment. The disadvantage is that it increases the burden. The present invention has been made to solve the above-mentioned drawbacks, and its purpose is to provide a novel corrosion prevention method for a nuclear reactor auxiliary cooling system that does not have a chemical injection line. To give an overview of the present invention, the present invention provides a demineralizing resin tower, a bypass for adjusting the flow rate of the desalting resin tower, and an oxygen injection device in a nuclear reactor auxiliary cooling system made of carbon steel or Albrak to provide oxygen. By injection, the dissolved oxygen concentration of circulating water can be reduced to 30 ppb or more.
Maintain the specific conductivity of circulating water at 10,000ppb and 0.3
The present invention relates to a method for preventing corrosion of a nuclear reactor auxiliary equipment cooling system, which is characterized by maintaining the temperature below μS/cm. Among the constituent materials of the reactor auxiliary cooling system mentioned above, the present inventors selected carbon steel (JIS S S41, chemical composition: see Table 1) and copper alloy, which are materials estimated to be particularly susceptible to corrosion damage. Albratsk (JIS
When we examined the corrosion rate in the cooling water of the condensed auxiliary cooling system (hereinafter simply referred to as cooling water) for BSTF2 (chemical composition, see Table 2) from various angles, we obtained the following experimental results. Relationship between corrosion rate and specific electrical conductivity of carbon steel (The specific electrical conductivity is expressed in the SI unit μS/cm, but it is synonymous with μU/cm.) Chemical composition of carbon steel
【表】
炭素鋼を温度30℃、流速0.2cm／ｓ、溶存酸素
濃度8ppmの冷却水に浸漬し、冷却水の比電導度
を変化させて、炭素鋼の腐食速度（腐食による減
量により測定）と比電導度との関係を測定した。
その結果を第２図に示す。
第２図から明らかなように、比電導度が0.3μ
Ｓ／cmを越える場合には腐食速度が急激に大にな
り、又0.3μＳ／cmを越える場合には前記関係は
他の因子の影響により、不安定であり、0.3μ
Ｓ／cm以下において安定することが判る。
炭素鋼の腐食速度と溶存酸素濃度との関係比電
導度を0.06μＳ／cm、及び0.3μＳ／cmとした冷
却水について、その溶存酸素濃度を変化させて温
度35℃、流速１cm／ｓで腐食速度を測定した。そ
の結果を第３図に示す。第３図から溶存酸素濃度
30ppb以上で腐食速度は比電導度0.06μＳ／cmで
は10mg／dm2・ｍ、同0.3μＳ／cmでは20mg／
dm2・ｍ（ｍは月）以下に保たれることが明らか
である。
以上の実験から炭素鋼の防食には他の因子の影
響を考慮して、少なくとも比電導度を0.3μＳ／
cm以下に維持し、又溶存酸素濃度を30ppbないし
10000ppbに維持すると有効である。
アルブラツクの腐食速度と比電導度との関係
アルブラツクの化学組成[Table] Carbon steel was immersed in cooling water at a temperature of 30°C, a flow rate of 0.2 cm/s, and a dissolved oxygen concentration of 8 ppm, and the specific conductivity of the cooling water was varied to determine the corrosion rate of carbon steel (measured by weight loss due to corrosion). The relationship between this and specific conductivity was measured.
The results are shown in FIG. As is clear from Figure 2, the specific conductivity is 0.3 μ
When the corrosion rate exceeds 0.3μS/cm, the corrosion rate increases rapidly, and when the corrosion rate exceeds 0.3μS/cm, the above relationship becomes unstable due to the influence of other factors.
It can be seen that it is stable at S/cm or less. Relationship between corrosion rate and dissolved oxygen concentration of carbon steel For cooling water with specific conductivity of 0.06 μS/cm and 0.3 μS/cm, corrosion was conducted at a temperature of 35°C and a flow rate of 1 cm/s by changing the dissolved oxygen concentration. The speed was measured. The results are shown in FIG. From Figure 3, dissolved oxygen concentration
At 30 ppb or more, the corrosion rate is 10 mg/dm 2 m at specific conductivity of 0.06 μS/cm, and 20 mg/dm at specific conductivity of 0.3 μS/cm.
It is clear that it is kept below dm 2 ·m (m is the month). From the above experiments, the corrosion protection of carbon steel requires a specific conductivity of at least 0.3μS/
Maintain dissolved oxygen concentration below 30ppb or less.
It is effective if maintained at 10000ppb. Relationship between corrosion rate and specific conductivity of Alblack Chemical composition of Alblack
【表】
アルブラツクを温度30℃、流速0.2cm／ｓ、溶
存酸素濃度8ppmの冷却水に浸漬し、冷却水の比
電導度を変化させて、炭素鋼の場合と同様の実験
を行い、腐食速度と比電導度との関係を測定し
た。その結果を第４図に示す。第４図から明らか
なように、第２図に示す炭素鋼の場合と同様にア
ルブラツクにおいても比電導度が0.3μＳ／cm以
下では腐食が抑制される。
アルブラツクの腐食速度と溶存酸素濃度との関係
比電導度を0.06μＳ／cm及び0.3μＳ／cmとし
た冷却水について炭素鋼の場合と同様な条件で溶
存酸素濃度を変化させて腐食速度を測定した。そ
の結果を第５図に示す。第５図から明らかなよう
に第３図に示す炭素鋼の場合と同様に溶存酸素濃
度30ppb以上でアルブラツクは防食される。
アルブラツクを溶存酸素濃度30〜60ppb、温度
35℃で、比電導度の異なる水中に3960時間浸漬
し、その腐食速度を測定した。
比電導度0.06μＳ／cmの水中では腐食減量は
22.3mg／ｄm2であり、0.3μＳ／cmを超え0.5μ
Ｓ／cmの間に保つた水中では34.5mg／ｄm2であつ
た。
したがつて銅合金は炭素鋼と同様に比電導度の
低い水中で腐食が抑制される。
ところで、銅合金の腐食を考えると、中性付近
では表面に形成される酸化物被膜の形成で防食性
が増加するが、余り高い酸素濃度の水中では被膜
の溶解の恐れがあり、最適の溶存酸素濃度として
は30〜100ppbの範囲である。
以上の実験から原子炉補機冷却系においては構
成材料である炭素鋼又はアルブラツクの防食のた
めに、循環水の比電導度を0.3μＳ／cm以下に維
持することにより亜硝酸ソーダの添加に代る効果
が達成されることが認められ、本発明は比電導度
を低下させるために陽、陰イオン交換樹脂を使用
する脱塩樹脂塔を冷却系統内に設けたものであ
る。そして循環水の全液量を脱塩樹脂塔に通すこ
とは、常に脱塩樹脂塔に負荷をかけることになる
ので脱塩樹脂塔の流量を調節するバイパスを設
け、比電導度が0.3μＳ／cmを越えた場合には脱
塩樹脂塔を通過する水量を多くするようにバイパ
スの通過量を調整することが必要である。
又循環水の溶存酸素濃度は30ppb以上の維持す
るのが望ましいので、この濃度を維持する手段と
して冷却系統内に酸素注入装置を設けた。
次に本発明の原子炉補機冷却系の防食方法を、
その冷却系の一具体例である第６図について説明
する。図中１は熱交換器、２はポンプ、４はサー
ジタンク、５は冷却対象系、６は脱塩樹脂塔、７
は電導度計、８はバイパス、９は流量調節弁、１
０は酸素ボンベである。
系統内の冷却水はポンプ２により冷却対象系５
から熱交換器１を通して例えば流速0.2cm／ｓで
循環、冷却され、その間にサージタンク４により
水圧調整が行なわれる。この系統内に脱塩樹脂塔
６を設けて水を循環すると同時にその比電導度を
低下させる。そして電導度計７により比電導度が
0.3μＳ／cm以下になるように管理され、比電導
度が0.3μＳ／cmを越えた場合には脱塩樹脂塔６
を通過する流量を多くするようにバイパス８の流
量調節弁９が作動する。又酸素ボンベ１０より系
統内の水の溶存酸素濃度を30ppbを越えるように
酸素を供給する。
本発明によれば、腐食抑制剤として亜硝酸ソー
ダを添加することなく、循環水の純度と溶存酸素
濃度の管理を行なう脱塩樹脂塔、そのバイパス及
び酸素注入装置を付加することにより、容易に系
統内の構成材料を防食でき、又排水による廃液処
理系への負担が減少されるという利点がある。[Table] Albrak was immersed in cooling water at a temperature of 30°C, a flow rate of 0.2 cm/s, and a dissolved oxygen concentration of 8 ppm, and the specific conductivity of the cooling water was varied, and an experiment similar to that for carbon steel was conducted. The relationship between this and specific conductivity was measured. The results are shown in FIG. As is clear from FIG. 4, similar to the case of carbon steel shown in FIG. 2, corrosion is suppressed in Alblack when the specific conductivity is 0.3 μS/cm or less. Relationship between corrosion rate and dissolved oxygen concentration of Albrak Corrosion rate was measured using cooling water with specific conductivity of 0.06μS/cm and 0.3μS/cm by changing dissolved oxygen concentration under the same conditions as for carbon steel. . The results are shown in FIG. As is clear from FIG. 5, Alblack is protected from corrosion when the dissolved oxygen concentration is 30 ppb or more, similar to the case of carbon steel shown in FIG. Dissolved oxygen concentration 30-60ppb, temperature
They were immersed in water with different specific conductivities at 35°C for 3960 hours, and their corrosion rates were measured. In water with a specific conductivity of 0.06μS/cm, the corrosion loss is
22.3mg/ dm2 , exceeding 0.3μS/cm and 0.5μ
In water maintained between S/cm2, the concentration was 34.5 mg/ dm2 . Therefore, like carbon steel, copper alloys are inhibited from corrosion in water with low specific conductivity. By the way, considering the corrosion of copper alloys, corrosion resistance increases due to the formation of an oxide film on the surface near neutrality, but in water with too high an oxygen concentration, there is a risk that the film will dissolve, so it is difficult to find the optimal solution. The oxygen concentration is in the range of 30 to 100 ppb. From the above experiments, in order to prevent corrosion of the carbon steel or Albrak, which is the component material, in the reactor auxiliary cooling system, the specific conductivity of the circulating water is maintained at 0.3μS/cm or less, which can replace the addition of sodium nitrite. It has been recognized that this effect is achieved, and the present invention provides a desalination resin tower using positive and anion exchange resins in the cooling system in order to reduce the specific conductivity. Passing the entire amount of circulating water through the desalination resin tower always puts a load on the desalination resin tower, so a bypass was installed to adjust the flow rate of the desalination resin tower, and the specific conductivity was reduced to 0.3μS/ cm, it is necessary to adjust the amount of water passing through the bypass so as to increase the amount of water passing through the desalination resin tower. Furthermore, since it is desirable to maintain the dissolved oxygen concentration in the circulating water at 30 ppb or more, an oxygen injection device was installed in the cooling system as a means to maintain this concentration. Next, the corrosion prevention method of the nuclear reactor auxiliary cooling system of the present invention is as follows:
FIG. 6, which is a specific example of the cooling system, will be explained. In the figure, 1 is a heat exchanger, 2 is a pump, 4 is a surge tank, 5 is a cooling target system, 6 is a desalination resin tower, 7
is a conductivity meter, 8 is a bypass, 9 is a flow rate control valve, 1
0 is an oxygen cylinder. Cooling water in the system is pumped to the target system 5 by pump 2.
The water is circulated and cooled through the heat exchanger 1 at a flow rate of, for example, 0.2 cm/s, during which the water pressure is adjusted by the surge tank 4. A desalination resin tower 6 is provided in this system to circulate water and reduce its specific conductivity. Then, the specific conductivity is determined by the conductivity meter 7.
The specific conductivity is controlled to be 0.3μS/cm or less, and if the specific conductivity exceeds 0.3μS/cm, the desalination resin tower 6
The flow rate control valve 9 of the bypass 8 operates to increase the flow rate passing through. Further, oxygen is supplied from the oxygen cylinder 10 so that the dissolved oxygen concentration in the water in the system exceeds 30 ppb. According to the present invention, by adding a desalination resin column, its bypass, and an oxygen injection device to manage the purity and dissolved oxygen concentration of circulating water without adding sodium nitrite as a corrosion inhibitor, it is possible to easily control the purity and dissolved oxygen concentration of circulating water. There are advantages in that the constituent materials within the system can be protected from corrosion and the burden on the waste liquid treatment system due to wastewater is reduced.
第１図は従来の防食抑制剤注入機構を有する原
子炉補機冷却系の概略図、第２図は炭素鋼の腐食
速度と冷却水の比電導度との関係を示すグラフ、
第３図は炭素鋼の腐食速度と冷却水の溶存酸素濃
度との関係を示すグラフ、第４図はアルブラツク
の腐食速度と冷却水の比電導度との関係を示すグ
ラフ、第５図はアルブラツクの腐食速度と冷却水
の溶存酸素濃度との関係を示すグラフ、第６図は
本発明を実施する原子炉補機冷却系の一具体例の
概略図である。
１…熱交換器、２…ポンプ、３…薬注ライン、
４…サージタンク、５…冷却対象系、６…脱塩樹
脂塔、７…電導度計、８…バイパス、９…流量調
整弁、１０…酸素ボンベ。
Figure 1 is a schematic diagram of a nuclear reactor auxiliary cooling system with a conventional corrosion inhibitor injection mechanism, Figure 2 is a graph showing the relationship between the corrosion rate of carbon steel and the specific conductivity of cooling water.
Figure 3 is a graph showing the relationship between the corrosion rate of carbon steel and the dissolved oxygen concentration in cooling water, Figure 4 is a graph showing the relationship between the corrosion rate of Alblack and the specific conductivity of cooling water, and Figure 5 is a graph showing the relationship between the corrosion rate of carbon steel and the specific conductivity of cooling water. FIG. 6 is a graph showing the relationship between the corrosion rate and the dissolved oxygen concentration of the cooling water. 1... Heat exchanger, 2... Pump, 3... Chemical injection line,
4... Surge tank, 5... System to be cooled, 6... Desalting resin tower, 7... Conductivity meter, 8... Bypass, 9... Flow rate adjustment valve, 10... Oxygen cylinder.
Claims (1)
原子炉補機冷却系に脱塩樹脂塔及び脱塩樹脂塔の
流量を調節するバイパス並に酸素注入装置を設け
て、酸素注入により循環水の溶存酸素濃度を
30ppbないし10000ppbに維持し、かつ循環水の
比電導度を0.3μＳ／cm以下に維持することを特
徴とする原子炉補機冷却系の防食方法。1. A reactor auxiliary cooling system made of carbon steel or Albrak is equipped with a desalinating resin tower, a bypass that adjusts the flow rate of the desalting resin tower, and an oxygen injection device to improve the dissolved oxygen concentration of circulating water by injecting oxygen. of
A corrosion prevention method for a nuclear reactor auxiliary equipment cooling system characterized by maintaining the specific conductivity of circulating water at 30 ppb to 10,000 ppb and below 0.3 μS/cm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12642979A JPS5651694A (en) | 1979-10-02 | 1979-10-02 | Corrosion protection system for auxiliary equipment of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12642979A JPS5651694A (en) | 1979-10-02 | 1979-10-02 | Corrosion protection system for auxiliary equipment of nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5651694A JPS5651694A (en) | 1981-05-09 |
| JPS6226439B2 true JPS6226439B2 (en) | 1987-06-09 |
Family
ID=14934963
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP12642979A Granted JPS5651694A (en) | 1979-10-02 | 1979-10-02 | Corrosion protection system for auxiliary equipment of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5651694A (en) |
-
1979
- 1979-10-02 JP JP12642979A patent/JPS5651694A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5651694A (en) | 1981-05-09 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CA3004311C (en) | Corrosion control for water systems using tin corrosion inhibitor with a hydroxycarboxylic acid | |
| JPH0658437B2 (en) | Radioactivity reduction methods for nuclear power plants | |
| EP1405671B1 (en) | Method of preventing corrosion in a water system | |
| CN113322466B (en) | Corrosion inhibitor applied to SCAL indirect air cooling system and dosing method thereof | |
| SE460628B (en) | METHOD OF OPERATION OF NUCLEAR POWER PLANT WITH COOKER REACTOR | |
| JPS6226439B2 (en) | ||
| JP2013194274A (en) | Corrosion prevention system and corrosion prevention method for nuclear power plant | |
| RU2543573C1 (en) | Intracircuit passivation method of steel surfaces of fast neutron nuclear reactor | |
| JPS6230269B2 (en) | ||
| US5714118A (en) | Method and composition for inhibiting corrosion | |
| JPH1128461A (en) | Water-based metal corrosion suppression method | |
| JPH02227193A (en) | Method for preventing generation of rust and/or scale in water channel | |
| JP2917813B2 (en) | Water-based metal corrosion suppression method | |
| JPH0335385B2 (en) | ||
| Herrigel | Corrosion Experience with Aluminum Desalting Plants | |
| JPH0438836B2 (en) | ||
| CA2092421C (en) | Method for corrosion-proofing of a water system | |
| US3718499A (en) | Process for protecting ferrous base metals against corrosion,and articles produced thereby | |
| JPH0631815B2 (en) | Nuclear power plant water supply system | |
| Drane | Some Aspects of-Water Treatment for Central Heating Systems | |
| US3809572A (en) | Protecting ferrous base metal articles against corrosion by treatment with niobium oxide | |
| JP2003090895A (en) | Method and device for demineralizing condensate | |
| JPS55147946A (en) | Preventive method for corrosion of winding | |
| KR19990024319A (en) | Water treatment agent composition and method for inhibiting corrosion and scale of water pipe | |
| Tyzack et al. | Some material compatibility aspects of SGHWRs |