CN111362388A - Synergistic control method for ethanolamine and ammonia in two-loop thermodynamic system of nuclear power plant - Google Patents
Synergistic control method for ethanolamine and ammonia in two-loop thermodynamic system of nuclear power plant Download PDFInfo
- Publication number
- CN111362388A CN111362388A CN201811591025.8A CN201811591025A CN111362388A CN 111362388 A CN111362388 A CN 111362388A CN 201811591025 A CN201811591025 A CN 201811591025A CN 111362388 A CN111362388 A CN 111362388A
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- China
- Prior art keywords
- ethanolamine
- ammonia
- thermodynamic system
- power plant
- nuclear power
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- HZAXFHJVJLSVMW-UHFFFAOYSA-N 2-Aminoethan-1-ol Chemical compound NCCO HZAXFHJVJLSVMW-UHFFFAOYSA-N 0.000 title claims abstract description 87
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 title claims abstract description 46
- 229910021529 ammonia Inorganic materials 0.000 title claims abstract description 23
- 238000000034 method Methods 0.000 title claims abstract description 16
- 230000002195 synergetic effect Effects 0.000 title claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 27
- VHUUQVKOLVNVRT-UHFFFAOYSA-N Ammonium hydroxide Chemical compound [NH4+].[OH-] VHUUQVKOLVNVRT-UHFFFAOYSA-N 0.000 claims abstract description 18
- 235000011114 ammonium hydroxide Nutrition 0.000 claims abstract description 18
- NLXLAEXVIDQMFP-UHFFFAOYSA-N Ammonium chloride Substances [NH4+].[Cl-] NLXLAEXVIDQMFP-UHFFFAOYSA-N 0.000 claims abstract description 12
- HQBYUMGOEJNFJB-UHFFFAOYSA-N 2-aminoethanol;azane Chemical compound N.NCCO HQBYUMGOEJNFJB-UHFFFAOYSA-N 0.000 claims abstract description 10
- 239000003153 chemical reaction reagent Substances 0.000 claims description 4
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 abstract description 16
- 229910052742 iron Inorganic materials 0.000 abstract description 8
- 239000010802 sludge Substances 0.000 abstract description 5
- 230000000694 effects Effects 0.000 abstract description 3
- 230000002209 hydrophobic effect Effects 0.000 abstract description 2
- 230000007797 corrosion Effects 0.000 description 13
- 238000005260 corrosion Methods 0.000 description 13
- 239000007791 liquid phase Substances 0.000 description 3
- YNAVUWVOSKDBBP-UHFFFAOYSA-N Morpholine Chemical compound C1COCCN1 YNAVUWVOSKDBBP-UHFFFAOYSA-N 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 2
- 230000008021 deposition Effects 0.000 description 2
- 238000011033 desalting Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000012071 phase Substances 0.000 description 2
- 239000010865 sewage Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- 150000001412 amines Chemical class 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 150000001450 anions Chemical class 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000004255 ion exchange chromatography Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 150000007524 organic acids Chemical class 0.000 description 1
- -1 pipeline shapes Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 238000002798 spectrophotometry method Methods 0.000 description 1
- 238000005979 thermal decomposition reaction Methods 0.000 description 1
- 239000012808 vapor phase Substances 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/66—Treatment of water, waste water, or sewage by neutralisation; pH adjustment
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/025—Devices and methods for diminishing corrosion, e.g. by preventing cooling beneath the dew point
Landscapes
- Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Hydrology & Water Resources (AREA)
- Environmental & Geological Engineering (AREA)
- Water Supply & Treatment (AREA)
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
The invention belongs to the technical field of nuclear power plant chemistry, and particularly relates to a ethanolamine ammonia cooperative control method for a two-loop thermodynamic system of a nuclear power plant. And adding ethanolamine solution and ammonia solution into the two-loop thermodynamic system to coordinate and control the concentration of ethanolamine and ammonia in the main water of the two-loop thermodynamic system so as to meet the requirement that the pH of the two-loop thermodynamic system is controlled to be 9.60-9.80. The concentration of the ethanolamine in the main water supply is 1-2.5 mg/kg. The ammonia concentration in the main water is 5-1.5 mg/kg. After the method is implemented, the pH value of the whole two-loop thermodynamic system is controlled to be 9.60-9.80, the iron content of the two loops is obviously reduced, the iron content of main feed water is reduced by about 30%, the hydrophobic iron content of a steam-water separator reheater is reduced by about 87%, the sludge amount flushed from the secondary side of a steam generator is reduced by about 35%, and the effect is obvious.
Description
Technical Field
The invention belongs to the technical field of nuclear power plant chemistry, and particularly relates to a ethanolamine ammonia cooperative control method for a two-loop thermodynamic system of a nuclear power plant.
Background
Steam Generators (SGs) are one of the important core devices of a nuclear power plant and are also primary pressure boundaries, and the integrity of the heat transfer tubes of the steam generators is directly related to the safety of the operation of the nuclear power plant. Statistics have shown that failure of a nuclear power plant steam generator is mostly related to breakage cracking of its heat transfer tubes, which is caused by corrosion by more than 80%. Corrosion tends to occur in stagnant areas of the steam generator where sludge deposits are formed, which primarily result from corrosion of the nuclear power plant two-circuit thermal system equipment. In nuclear power plants at home and abroad, a case of shutdown and shutdown caused by the breakage of a two-circuit steam pipeline caused by corrosion occurs for many times, for example, the serious accidents of casualties caused by the thinning and breakage of pipelines caused by accelerated corrosion of the flowing of condensed water pipelines of a 2# unit of a American Sari nuclear power plant and a 3# unit of a Japan American shore nuclear power plant.
Factors influencing the corrosion of the two-loop thermodynamic system equipment of the nuclear power plant are many, including pipeline materials, pipeline shapes, fluid flow rates, temperatures, water quality and the like. For a nuclear power plant that has been put into operation, corrosion of the equipment of the two-circuit thermodynamic system is suppressed, and in the case where other conditions are difficult to change, the most effective method is to improve the management of water chemistry control of the two-circuit thermodynamic system.
Currently, most of domestic nuclear power plants adopt ammonia as a two-loop pH control agent. The gas-liquid distribution coefficient of ammonia is large, so that the ammonia content of a liquid phase system is seriously insufficient during the separation of water and vapor phases, the pH value is low, and carbon steel equipment and pipelines (such as a drainage system) in a liquid phase are seriously corroded. The concrete expression is that the iron content of the two-loop thermodynamic system is high, the sludge washed out from the secondary side of the steam generator is much during overhaul, and the two-loop pipeline is forced to be frequently replaced.
Foreign nuclear power plants also use organic amines (e.g., ethanolamine, morpholine) alone as a two-loop pH control agent. Because the vapor-liquid distribution coefficient of the ethanolamine is small, the ethanolamine is more prone to being distributed in a liquid phase during use, the pH of a two-loop thermodynamic system cannot be controlled to be balanced by singly using the ethanolamine, and meanwhile, the concentration of the ethanolamine in SG sewage is greatly increased, so that the operation burden of a desalting bed is greatly increased for a power plant which is designed to continuously operate in a desalting bed of a steam generator sewage system; in addition, because the ethanolamine can generate a small amount of organic acid due to thermal decomposition, the overall positive conductivity of the ethanolamine secondary loop is increased, the positive conductivity control of a secondary loop thermodynamic system is influenced, and the judgment on the seawater leakage of the condenser and the judgment on the entering of other anion impurities into the secondary loop and the steam generator are greatly disturbed.
Disclosure of Invention
The invention aims to provide an ethanolamine-ammonia cooperative control method for a two-loop thermodynamic system of a nuclear power plant, which fully utilizes respective volatility characteristics of ethanolamine and ammonia, improves the pH value of a water phase (such as a drainage system) in a steam-water two-phase region of the two-loop thermodynamic system of the nuclear power plant, realizes the balanced control of the pH value of the two-loop thermodynamic system, reduces the Flow Accelerated Corrosion (FAC) rate of the two-loop thermodynamic system, reduces the amount of corrosion products entering a steam generator, reduces sludge deposition on the secondary side of the steam generator, reduces the risk of corrosion damage of a heat transfer pipe of the steam generator, and improves the operation safety of the nuclear power plant.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
an ethanolamine-ammonia cooperative control method for a two-loop thermodynamic system of a nuclear power plant comprises the steps of adding an ethanolamine solution and an ammonia solution into the two-loop thermodynamic system, and coordinately controlling the ethanolamine concentration and the ammonia concentration in main water of the two-loop thermodynamic system so as to meet the requirement that the pH value of the two-loop thermodynamic system is controlled within 9.60-9.80.
The concentration of the ethanolamine in the main water supply is 1-2.5 mg/kg.
The ammonia concentration in the main water is 5-1.5 mg/kg.
The ethanolamine in the ethanolamine solution meets the type I standard of HG/T2915-1997 monoethanolamine for industrial use.
The ammonia water in the ammonia solution meets the analytical purity standard of GB/T631-2007 chemical reagent ammonia water.
The mass percentage of the ethanolamine solution is 0.3-0.5%.
The mass percentage of the ammonia solution is 1-2%.
The beneficial effects obtained by the invention are as follows:
after the method is implemented, the pH value of the whole two-loop thermodynamic system is controlled to be 9.60-9.80, the iron content of the two loops is obviously reduced, the iron content of main feed water is reduced by about 30%, the content of hydrophobic iron of a steam-water separator reheater (MSR) is reduced by about 87%, the amount of sludge washed out from the secondary side of a steam generator is reduced by about 35%, and the effect is obvious.
The pH value of the two-loop thermodynamic system is effectively improved, the balance control is realized, the iron content of the two-loop thermodynamic system is obviously reduced, the corrosion condition of the two-loop thermodynamic system is improved, the corrosion of equipment of the two-loop thermodynamic system is reduced, the migration and deposition of corrosion products to a steam generator are reduced, the integrity of a heat transfer pipe of the steam generator is protected, and the running reliability of the equipment of the two-loop thermodynamic system is improved.
Detailed Description
The present invention will be described in detail with reference to specific examples.
The chemical used in the practice of the invention is ethanolamine (NH)2CH2CH2OH) and ammonia (NH)3·H2O). The optimal pH control anticorrosion effect of the two-loop thermodynamic system is 9.60-9.80, ethanolamine solution and ammonia solution are added into the two-loop thermodynamic system through a dosing device, and according to the actual distribution condition of ethanolamine and ammonia in each steam-water loop of the two-loop thermodynamic system of the nuclear power plant, the concentration of ethanolamine in the main water of the two-loop thermodynamic system is coordinated and controlled to be 1-2.5 mg/kg, and the concentration of ammonia is 5-1.5 mg/kg.
The first step is as follows: preparing a dosing device, wherein the dosing device is provided with an ethanolamine solution tank and an ammonia solution tank, and each solution tank is provided with a dosing pump with adjustable flow, corresponding pipelines, valves and other accessory facilities.
The second step is that: the chemicals used were: ethanolamine (NH)2CH2CH2OH) and ammonia (NH)3·H2O). The ethanolamine needs to meet the type I standard of "HG/T2915-1997 monoethanolamine for industrial use", and the ammonia water needs to meet the analytical purity standard of "GB/T631-2007 ammonia water as chemical reagent".
The third step: respectively preparing ethanolamine solution and ammonia solution, one solution tank preparing ethanolamine solution in 0.3-0.5 wt% and the other solution tank preparing ammonia solution in 1-2 wt%.
The fourth step: the ethanolamine dosing pump and the ammonia dosing pump are started, and the ethanolamine solution and the ammonia solution are added into the two-loop system at the same time.
The fifth step: sampling the main feed water in the two-loop thermodynamic system according to the determination of ethanolamine concentration in water vapor of DL/T1479-2015 power plant-ion chromatography and the water vapor analysis method of DL/T502.16-2006 thermal power plant part 16: measurement of ammonia (naesli reagent spectrophotometry) ethanolamine concentration and ammonia concentration were analyzed.
And a sixth step: according to the concentration of ethanolamine and ammonia in the main water supply, the medicine-adding flow rate of the corresponding medicine-adding pump is regulated to make the concentration of ethanolamine and ammonia be in the required control range (ethanolamine concentration is 1-2.5 mg/kg, ammonia concentration is 5-1.5 mg/kg) so as to meet the requirement of controlling pH of two-circuit thermodynamic system at 9.60-9.80.
Claims (7)
1. A synergistic control method for ethanolamine and ammonia in a two-loop thermodynamic system of a nuclear power plant is characterized by comprising the following steps: and adding ethanolamine solution and ammonia solution into the two-loop thermodynamic system to coordinate and control the concentration of ethanolamine and ammonia in the main water of the two-loop thermodynamic system so as to meet the requirement that the pH of the two-loop thermodynamic system is controlled to be 9.60-9.80.
2. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the concentration of the ethanolamine in the main water supply is 1-2.5 mg/kg.
3. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the ammonia concentration in the main water is 5-1.5 mg/kg.
4. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the ethanolamine in the ethanolamine solution meets the type I standard of HG/T2915-1997 monoethanolamine for industrial use.
5. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the ammonia water in the ammonia solution meets the analytical purity standard of GB/T631-2007 chemical reagent ammonia water.
6. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the mass percentage of the ethanolamine solution is 0.3-0.5%.
7. The method for cooperatively controlling ethanolamine ammonia in a two-circuit thermodynamic system of a nuclear power plant according to claim 1, wherein: the mass percentage of the ammonia solution is 1-2%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811591025.8A CN111362388A (en) | 2018-12-25 | 2018-12-25 | Synergistic control method for ethanolamine and ammonia in two-loop thermodynamic system of nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811591025.8A CN111362388A (en) | 2018-12-25 | 2018-12-25 | Synergistic control method for ethanolamine and ammonia in two-loop thermodynamic system of nuclear power plant |
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| Publication Number | Publication Date |
|---|---|
| CN111362388A true CN111362388A (en) | 2020-07-03 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811591025.8A Pending CN111362388A (en) | 2018-12-25 | 2018-12-25 | Synergistic control method for ethanolamine and ammonia in two-loop thermodynamic system of nuclear power plant |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114477407A (en) * | 2022-01-06 | 2022-05-13 | 广东核电合营有限公司 | Nuclear power station secondary loop pH adjusting method and system |
| WO2025021307A1 (en) | 2023-07-27 | 2025-01-30 | Framatome Gmbh | Conditioning of water-steam-circuit of light and heavy water reactors |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102557225A (en) * | 2010-12-28 | 2012-07-11 | 秦山核电有限公司 | Method for adjusting pH value of secondary circuit of nuclear power plant |
| CN105417668A (en) * | 2015-12-25 | 2016-03-23 | 中国核动力研究设计院 | Novel composite alkalizer and application thereof |
| CN106854017A (en) * | 2015-12-09 | 2017-06-16 | 中核核电运行管理有限公司 | Nuclear power station secondary loop therrmodynamic system morpholine-ammonia collaboration chemical control method |
-
2018
- 2018-12-25 CN CN201811591025.8A patent/CN111362388A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102557225A (en) * | 2010-12-28 | 2012-07-11 | 秦山核电有限公司 | Method for adjusting pH value of secondary circuit of nuclear power plant |
| CN106854017A (en) * | 2015-12-09 | 2017-06-16 | 中核核电运行管理有限公司 | Nuclear power station secondary loop therrmodynamic system morpholine-ammonia collaboration chemical control method |
| CN105417668A (en) * | 2015-12-25 | 2016-03-23 | 中国核动力研究设计院 | Novel composite alkalizer and application thereof |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114477407A (en) * | 2022-01-06 | 2022-05-13 | 广东核电合营有限公司 | Nuclear power station secondary loop pH adjusting method and system |
| WO2025021307A1 (en) | 2023-07-27 | 2025-01-30 | Framatome Gmbh | Conditioning of water-steam-circuit of light and heavy water reactors |
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Application publication date: 20200703 |
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