CN211875989U - Purification system for high-temperature gas cooled reactor nuclear power unit during starting period of thermal equipment - Google Patents
Purification system for high-temperature gas cooled reactor nuclear power unit during starting period of thermal equipment Download PDFInfo
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- CN211875989U CN211875989U CN202020449890.5U CN202020449890U CN211875989U CN 211875989 U CN211875989 U CN 211875989U CN 202020449890 U CN202020449890 U CN 202020449890U CN 211875989 U CN211875989 U CN 211875989U
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Abstract
The utility model relates to a high temperature gas cooled reactor nuclear power plant water chemistry operating mode specifically is high temperature gas cooled reactor nuclear power unit thermodynamic equipment clean-up system during start-up. The present purification system includes a purification loop during startup; the thermal equipment comprises a steam generator and a condenser; the steam outlet of the steam generator is connected with the input end of a condenser through a steam turbine set, and the output end of the condenser is connected with the main water supply end of the steam generator through a water supply loop; a deaerator is arranged on the water supply loop; the purification loop comprises a primary door connected to the main water supply end of the steam generator during starting and three pipelines arranged behind the primary door; the three pipelines comprise a discharge pipeline, a first water return pipeline and a second water return pipeline; the tail end of the discharge pipeline is connected to a unit flash tank or a heat exchanger, the first water return pipeline is connected to the output end of the condenser, and the second water return pipeline is connected to the inlet of the deaerator. The utility model discloses ensure that the unit gets into steam generator's the quality of water of main feedwater at cold starting, hot starting in-process, its corrosion scale deposit risk of greatly reduced.
Description
Technical Field
The utility model relates to a high temperature gas cooled reactor nuclear power plant water chemistry operating mode specifically is high temperature gas cooled reactor nuclear power unit thermodynamic equipment clean-up system during start-up.
Background
The steam generator of the high-temperature gas cooled reactor nuclear power unit has the characteristics that: (1) the main water supply pipe side (secondary side) is walked, and the helium is walked shell side (is once inclines), for pressurized water reactor nuclear power unit (pressurized water reactor coolant pipe side, main water supply pipe side is walked), deposit corrosion product and other impurity more easily in the high temperature gas cooled reactor nuclear power unit steam generator heat transfer pipe, also take place dirty stifled phenomenon more easily, all can influence the unit safe operation, influence heat exchange efficiency. (2) The same point as most pressurized water reactor nuclear power units is that the steam generator material contains nickel-based alloy which is sensitive to oxygen corrosion, when the unit is started to enter a hot state for flushing, the content of dissolved oxygen entering the steam generator is required to be not more than 100 mu g/L, and after the unit is loaded and connected to the grid, the dissolved oxygen of main feed water entering the steam generator is required to be not more than 3 mu g/L. (3) The high temperature gas cooled reactor nuclear power generator has the characteristic of a once-through boiler, and feed water is directly fed into a steam turbine to do work from water to saturated steam in an evaporator until the feed water becomes superheated steam. No pollution discharge and no superheater. (4) The inner diameter of the steam generator pipe is small, corrosion or deposition of corrosion products on the pipe wall occurs, unit efficiency is seriously influenced, and power consumption of a water supply pump is increased. (5) The steam generator has a special structure, and when the leakage problem of the heat exchange tube occurs, the tube cannot be replaced and repaired, and the machine can only be stopped to plug the tube. (6) The unit parameters are high, and the steam parameters at the outlet of the steam generator are 13.90MPa and 571 ℃; the starting process time of the high-temperature gas cooled reactor nuclear power generating unit is short, 585min is required for cold starting, and 511min is required for warm starting.
Therefore, the strict control of the content of impurities such as dissolved oxygen and corrosion products in the main feed water entering the steam generator is one of the important tasks for ensuring the safe and economic operation of the high-temperature gas-cooled reactor nuclear power unit.
In the technical field of water chemical working conditions of nuclear power plants, the risks of corrosion and scaling of a steam generator are reduced from three stages of normal operation, non-use maintenance and unit start-up of a unit. The purification of the thermal equipment in the starting process of the unit is an important step, the main feed water is supervised before entering the steam generator, and the main feed water is recycled or discharged when the main feed water is unqualified. And a water return pipe section or a discharge pipe section is not arranged from the outlet of the high-pressure heater to the inlet pipe section of the steam generator in the conventional thermal equipment, so that the thermal equipment is subjected to technical upgrading and reconstruction.
SUMMERY OF THE UTILITY MODEL
To the problem that exists among the prior art, the utility model provides a guarantee that the unit starts in-process and gets into the interior main water quality of giving water of steam generator heat exchange tube, furthest's reduction steam generator heat exchange tube takes place to corrode, the high temperature gas cooling of scale deposit nuclear power unit thermodynamic equipment clean system during start.
The utility model discloses a realize through following technical scheme:
the purification system comprises a purification loop during starting of thermodynamic equipment of the high-temperature gas cooled reactor nuclear power unit;
the thermal equipment comprises a steam generator and a condenser; the steam outlet of the steam generator is connected with the input end of the condenser through the turbine set, and the output end of the condenser is connected with the main water supply end of the steam generator through the water supply loop; a deaerator is arranged on the water supply loop;
the purification loop comprises a primary door connected to the main water supply end of the steam generator during starting and a three-way pipeline arranged behind the primary door; the three pipelines comprise a discharge pipeline, a first water return pipeline and a second water return pipeline; the tail end of the discharge pipeline is connected to a unit flash tank or a heat exchanger, the first water return pipeline is connected to the output end of the condenser, and the second water return pipeline is connected to the inlet of the deaerator.
Furthermore, the first return water pipeline is connected with the output end of the condenser through a temperature and pressure reducer and a connecting pipeline which are sequentially arranged.
Furthermore, the first return water pipeline is made of alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipeline wall is more than 20mm, and the inner diameter of the pipeline is not less than that of a main pipeline connected with the steam generator.
Furthermore, the connecting pipeline is made of alloy steel or stainless steel containing more than 0.15% of chromium, the wall thickness is 10mm, and the inner diameter of the pipeline is not less than that of the first water return pipeline.
Furthermore, the second water return pipeline is made of alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipe wall is more than 20mm, and the inner diameter of the pipe is not less than that of a main pipe connected with the steam generator.
Furthermore, the discharge pipeline is made of alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipe wall is more than 20mm, and the inner diameter of the pipeline is not less than that of a main pipeline connected with the steam generator.
Furthermore, the three pipelines are connected in a three-way mode or in three independent pipelines, and secondary doors are respectively arranged on the three pipelines.
Compared with the prior art, the utility model discloses following profitable technological effect has:
the utility model can effectively control the water quality when the unit is washed in cold state and hot state by adding the discharge pipeline from the main feed water inlet pipe of the steam generator to the unit flash tank or the heat exchanger, thereby preventing unqualified water from entering the steam generator and reducing the corrosion and scaling risks of the steam generator; by adding the first return water pipeline from the main water supply inlet pipe of the steam generator to the condenser, the unqualified main water supply can be ensured to be circularly purified in the cold and hot washing processes of the unit start, so that the water quality can be ensured, the corrosion and scaling risks of the steam generator can be reduced, and the water resource can be saved; through increasing the second return water pipe from steam generator main feedwater inlet tube to oxygen-eliminating device inlet tube, can guarantee that the unit is under various starting condition, the dissolved oxygen of the main feedwater that gets into steam generator satisfies the demands, reduce steam generator's corruption, the scale deposit risk, thereby can improve the unit cold state, the hot state quality of washing, after guaranteeing that the unit is washed with circulation deoxidization in the hot state, the feedwater oxygen-free or the hypoxemia (dissolved oxygen content is less than 20 mu g/L) that gets into steam generator, the iron content is less than 20 mu g/L in the feedwater, other feedwater indexes accord with the feedwater quality of high temperature gas cooled reactor unit during operation, but furthest's reduction is because of the corrosion of the steam generator that reactor start initial stage feedwater quality of water is less than operation quality of water and brings, the scale deposit risk.
Preferably, a temperature-reducing pressure reducer with a temperature-reducing and pressure-reducing function is arranged on the first return water pipeline, so that the return water pressure and the temperature can be adjusted to required parameters, and the pressure and the temperature value at the outlet of the pipeline can be effectively kept within a certain range.
Preferably, alloy steel or stainless steel containing more than 0.15% of chromium is adopted, the thickness of the pipe wall is more than 20mm, the inner diameters of the discharge pipeline, the first water return pipeline and the second water return pipeline are not less than the inner diameter of a main pipeline connected with the steam generator, the pressure of the water return pipeline is reduced, and the corrosion of the water return pipeline is reduced so as to reduce corrosion products entering a thermodynamic system to the maximum extent.
Preferably, alloy steel or stainless steel containing more than 0.15% of chromium is adopted, the thickness of the pipe wall is 10mm, the inner diameter of the connecting pipeline is not smaller than that of the first water return pipeline, the pressure of the water return pipeline is reduced, the corrosion of the water return pipeline is reduced, and the corrosion products entering a thermodynamic system are reduced to the maximum extent.
Drawings
FIG. 1 is a schematic view of the purification system of the present invention.
In the figure: the system comprises a condenser 1, a condensate pump 2, a condensate fine treatment device 3, a third low-pressure heater 4, a second low-pressure heater 5, a first low-pressure heater 6, a deaerator 7, a water feed pump 8, a high-pressure heater 9, a steam generator 10, a high-pressure cylinder 11, a low-pressure cylinder 12, a condensate fine treatment outlet hydrazine adding point 13, a condensate fine treatment outlet ammonia adding point 14, a deaerator sewer pipe hydrazine adding point 15, a deaerator sewer pipe ammonia adding point 16, a high-pressure heater outlet hydrazine adding point 17, a steam generator inlet sampling point 18, a helium fan 19, a nuclear reactor 20, a unit flash tank or heat exchanger 21, a temperature and pressure reducing device 22, a first water return pipeline 23, a second water return pipeline 24, a steam-water separator 25, a radioactivity monitoring water pool 26, a discharge pipeline 27 and a connecting pipeline 28.
Detailed Description
The present invention will now be described in further detail with reference to specific examples, which are intended to be illustrative, but not limiting, of the invention.
As shown in fig. 1, the secondary loop system of the high temperature gas cooled reactor nuclear power plant comprises a condenser 1, a condensate pump 2, a condensate fine treatment device 3, a third low-pressure heater 4, a second low-pressure heater 5, a first low-pressure heater 6, a deaerator 7, a water feed pump 8, a high-pressure heater 9, a steam generator 10, a high-pressure cylinder 11 and a low-pressure cylinder 12 which are connected in sequence, and the primary loop comprises a nuclear reactor 20, a helium fan 19 and a steam generator 10 which are connected in sequence. As shown in fig. 1, the purification system during the start-up of the thermal equipment of the high temperature gas cooled reactor nuclear power plant comprises a water discharge pipeline 27 arranged at an inlet pipe of the steam generator 10 to the plant flash tank or the heat exchanger 21, a second water return pipeline 24 to the deaerator 7, and a first water return pipeline 23 to the condenser 1.
As the preferred embodiment of the present invention, the water discharge pipeline 27 from the inlet pipeline of the steam generator 10 to the unit expander or the heat exchanger 21 should be alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipeline wall should be more than 20mm, and the inner diameter of the pipeline is not less than the inner diameter of the main pipeline connected with the steam generator 10.
As the preferred embodiment of the present invention, the second water return pipe 24 from the inlet pipe of the steam generator 10 to the inlet of the deaerator 7 should be alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipe wall should be more than 20mm, and the inner diameter of the pipe is not less than the inner diameter of the main pipe connecting the steam generator 10.
As a preferred embodiment of the present invention, a temperature and pressure reducer 22 should be disposed from the inlet pipeline of the steam generator 10 to the first return water pipeline 23 of the condenser 1; the first return water pipeline 23 which is positioned in front of the inlet of the temperature and pressure reducing device 22 is alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipeline wall is more than 20mm, and the inner diameter of the pipeline is not less than the inner diameter of a main pipeline connected with the steam generator 10; the connecting pipeline 28 positioned behind the outlet of the temperature and pressure reducing device 22 should be alloy steel or stainless steel containing more than 0.15% of chromium, the wall thickness should be about 10mm, and the inner diameter of the pipeline is not less than the inner diameter of the first return water pipeline 23.
As the preferred embodiment of the present invention, the inlet of the steam generator 10 is connected to the water discharge pipe 27 of the unit flash tank or the heat exchanger 21, the second water return pipe 24 is connected to the inlet of the deaerator 7, and the first water return pipe 23 is connected to the condenser 1 by a three-way connection or independent pipe connection.
The specific working process is as follows:
1) during the cold-state starting period of the unit, the cold-state flushing process comprises the following steps:
(1) supplementing the desalted water into a condenser 1, starting a condensed water ammonia adding pump, and increasing the pH value of system flushing water to 9.5-10.0; the condensate pump 2 is started and recirculation is established. When the iron content of the outlet of the condensate pump 2 is more than 400 mug/L, the condensate pump is discharged from the outlet of the first low-pressure heater 6, and water is supplemented to the condenser 1 to maintain the water level and circulation.
(2) When the iron content of the water discharged from the condensate pump 2 is less than 400 mug/L, water can be fed into the deaerator 7. After the deaerator 7 is normal in water level, starting a recirculating pump for circulating flushing; it is desirable to have an auxiliary steam heating system at this point. Connecting a temporary discharge pipeline from the deaerator 7 to a water discharge pipeline of the condenser 1, discharging sewage with the iron content of more than 200 mug/L to a waste water storage pool, recovering the sewage to the condenser 1 after the sewage is qualified, and putting the sewage into the condensate fine treatment device 3 for water quality purification.
(3) When the iron content at the outlet of the deaerator 7 is less than 200 mug/L, the water feeding pump 8 can be started to feed water to the high-pressure heater 9. When the iron content of the feed water sample at the inlet sampling point 18 of the steam generator 10 is more than 200 mug/L, the feed water sample is discharged through the discharge pipeline 27; when the iron content of a feed water sample at an inlet sampling point 18 of the steam generator 10 is between 100 and 200 mu g/L, the feed water sample is recycled to the condenser 1 through a first return water pipeline 23 to continue purification treatment; when the iron content of the feed water sample at the inlet sampling point 18 of the steam generator 10 is less than 100 mug/L, the feed water sample can enter the steam generator 10 for cold flushing.
(4) Hydrazine is added into the feed water at a hydrazine adding point 15 at the outlet of the deaerator 7 before the steam generator 10 feeds water, and the concentration of the hydrazine added into the feed water is 200-500 mug/L. Water discharged from the steam generator 10 enters a steam-water separator 25 of the start-stop reactor system, and unqualified washing water is discharged to a discharge pipeline of a radioactivity monitoring water pool 26 through a drain pipe of the steam-water separator 25; when the content of the iron in the drainage water of the steam-water separator 25 is less than 50 mug/L, the drainage water is recycled to the condenser 1 through the drainage pipeline of the steam-water separator 25, and the circular washing is realized.
(5) And when the content of iron in the hydrophobic drainage water of the steam-water separator 25 is less than 30 mu g/L, the content of silicon dioxide is less than 30 mu g/L, and the hydrogen conductivity is less than 0.5 mu S/cm, finishing cold state flushing.
2) During the cold-state starting period of the unit, the hot-state flushing process comprises the following steps:
(1) after the cold state washing is qualified, a first water circulation washing flow of the condenser 1 → the condensate pump 2 → the low-pressure heater 4 → the low-pressure heater 5 → the low-pressure heater 6 → the deaerator 7 → the condenser 1 is established, and the drainage water of the deaerator 7 is recycled to the condenser 1 through the existing pipeline. And starting the auxiliary boiler, heating the deaerator 7 to about 170 ℃ by using steam of the auxiliary boiler to carry out hot state washing, and carrying out thermal deoxidization. When the iron content of the water discharged from the deaerator 7 is more than 100 mug/L, the water is recovered from the condenser 1 and discharged through a discharge pipeline.
(2) When the iron content of the water discharged from the deaerator 7 is less than 100 mug/L, the water discharged from the deaerator 7 is recycled to the condenser 1 through the existing pipeline, and the water is fed into the high-pressure water supply system for washing. And simultaneously starting a hydrazine dosing pump, adding hydrazine to a hydrazine dosing point 15 of a downcomer of the deaerator 7 until the content of the hydrazine in the water supply is 200-500 mu g/L, and carrying out chemical deoxidization.
(3) The maintaining condenser 1 → the condensate pump 2 → the third low-pressure heater 4 → the second low-pressure heater 5 → the first low-pressure heater 6 → the deaerator 7 → the feed pump 8 → the high-pressure heater 9 → the second water circulation flushing flow of the condenser 1 and the start boiler heating steam, and the outlet of the high-pressure heater 9 is connected to the condenser 1 through the first return water pipe 23, the temperature and pressure reducing device 22 and the connecting pipe 28. When the iron content of the feed water sample at the inlet sampling point 18 of the steam generator 10 is more than 200 mug/L, the feed water sample is temporarily discharged through the discharge pipeline 27; when the iron content of a feed water sample at an inlet sampling point 18 of the steam generator 10 is between 50 and 200 mu g/L, the feed water sample is recycled to the condenser 1 through a first return water pipeline 23 to continue purification treatment; when the main feed water iron content is less than 50 mug/L and the dissolved oxygen content exceeds 100 mug/L, the main feed water iron content is recovered to the deaerator 7 through the second water return pipe 24, the circular deaerating treatment of chemical deaerating and thermal deaerating is carried out, and the main feed water iron content entering the steam generator 10 is ensured to be less than 50 mug/L and the dissolved oxygen content is ensured to be less than 100 mug/L. When the iron content of the feed water sample at the inlet sampling point 18 of the steam generator 10 is less than 50 mug/L and the dissolved oxygen content is less than 100 mug/L, hot water flushing can be carried out on the feed water to the steam generator 10 and the system of starting and stopping the reactor (the steam-water separator 25). The flushing flow is adjusted and changed by the recirculation of the water feeding pump 8, and the flushing effect is improved.
(4) The water discharged from the steam generator 10 enters a steam-water separator 25 of the start-stop reactor system, and unqualified washing water is discharged to a discharge pipeline of a radioactive monitoring water pool 26 through a drain pipe of the steam-water separator 25; when the content of the iron in the drainage of the steam-water separator 25 is less than 30 mug/L, the drainage water is recycled to the condenser 1 through a drainage pipeline of the steam-water separator 25, so that the circular washing is realized.
(5) Establishing a condenser 1 → a condensate pump 2 → a third low-pressure heater 4 → a second low-pressure heater 5 → a first low-pressure heater 6 → a deaerator 7 → a water feeding pump 8 → a high-pressure heater 9 → a steam generator 10 → a starting steam-water separator 25 → a large circulation of the condenser 1, carrying out thermal state circulation washing, and purifying the water quality of equipment by using a condensate fine treatment device 3 to enable the water quality to meet the starting requirement of the unit so as to finish the thermal state washing of the unit.
(6) And in the washing process, ammonia is added through an ammonia adding point 14 at a condensate fine treatment outlet and an ammonia adding point 16 at a deaerator sewer pipe to adjust the pH value of the feed water, and the pH value of the washing water is maintained between 9.5 and 10.0. Hydrazine is added into the flushing water through a hydrazine dosing point 15 of a downcomer of the deaerator 7, and 200 mu g/L-500 mu g/L of hydrazine in the flushing water is maintained, so that the dissolved oxygen content of the main feed water entering the steam generator 10 is ensured to be less than 100 mu g/L.
The utility model discloses clean system during high temperature gas cooled reactor nuclear power unit thermodynamic equipment starts, through increasing steam generator 10 entry to unit flash vessel or heat exchanger 21's drainage pipe 27, to the second return water pipeline 24 of 7 entrys of oxygen-eliminating device, 23 three routes pipelines of first return water pipeline to condenser 1, first return water pipeline 23 includes temperature and pressure reduction ware 22, ensure that the unit starts at the cold state, the main water quality of water that gets into steam generator 10 among the hot start-up process, greatly reduced steam generator 10's corruption, the scale deposit risk.
Claims (7)
1. The purification system for the thermal equipment of the high-temperature gas cooled reactor nuclear power unit during starting is characterized by comprising a purification loop during starting;
the thermal power equipment comprises a steam generator (10) and a condenser (1); a steam outlet of the steam generator (10) is connected with an input end of the condenser (1) through a turbine set, and an output end of the condenser (1) is connected with a main water supply end of the steam generator (10) through a water supply loop; a deaerator (7) is arranged on the water supply loop;
the purification loop comprises a primary door connected to the main water supply end of the steam generator (10) during starting and a three-way pipeline arranged behind the primary door; the three pipelines comprise a discharge pipeline (27), a first water return pipeline (23) and a second water return pipeline (24); the tail end of the discharge pipeline (27) is connected to a unit flash tank or a heat exchanger (21), the first water return pipeline (23) is connected to the output end of the condenser (1), and the second water return pipeline (24) is connected to the inlet of the deaerator (7).
2. The purification system during startup of a thermal plant of a high temperature gas cooled reactor nuclear power plant according to claim 1, wherein the first return water pipe (23) is connected to the output end of the condenser (1) through a temperature and pressure reducing device (22) and a connecting pipe (28) which are arranged in sequence.
3. The purification system during the startup period of the thermal equipment of the nuclear power unit of the high temperature gas cooled reactor as claimed in claim 1 or 2, wherein the first water return pipeline (23) is made of alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipeline wall is more than 20mm, and the inner diameter of the pipeline is not less than the inner diameter of a main pipeline connected with the steam generator (10).
4. The purification system during the startup of the thermal equipment of the high-temperature gas-cooled reactor nuclear power generating unit according to claim 2, characterized in that the connecting pipeline (28) is made of alloy steel or stainless steel containing more than 0.15% of chromium, the wall thickness is 10mm, and the inner diameter of the pipeline is not less than that of the first return water pipeline (23).
5. The system for cleaning the nuclear power plant of the high temperature gas cooled reactor nuclear power plant during startup according to claim 1, wherein the second water return pipe (24) is made of alloy steel or stainless steel containing more than 0.15% of chromium, the pipe wall thickness is more than 20mm, and the inner diameter of the pipe is not less than the inner diameter of the main pipe connected with the steam generator (10).
6. The system for cleaning the nuclear power plant of the high temperature gas cooled reactor nuclear power plant during startup according to claim 1, wherein the discharge pipe (27) is made of alloy steel or stainless steel containing more than 0.15% of chromium, the thickness of the pipe wall is more than 20mm, and the inner diameter of the pipe is not less than the inner diameter of the main pipe connected with the steam generator (10).
7. The system of claim 1, wherein the three-way pipeline is connected by a tee or divided into three separate pipelines, and the three-way pipeline is provided with a secondary door.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112420232A (en) * | 2020-11-18 | 2021-02-26 | 华能山东石岛湾核电有限公司 | Two return circuits water supply system of high temperature gas cooled reactor nuclear power plant |
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2020
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112420232A (en) * | 2020-11-18 | 2021-02-26 | 华能山东石岛湾核电有限公司 | Two return circuits water supply system of high temperature gas cooled reactor nuclear power plant |
| CN112420232B (en) * | 2020-11-18 | 2022-07-15 | 华能山东石岛湾核电有限公司 | Two-loop water supply system of high-temperature gas cooled reactor nuclear power plant |
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