CN112216411A - Primary circuit exhaust method of pressurized water reactor nuclear power station - Google Patents
Primary circuit exhaust method of pressurized water reactor nuclear power station Download PDFInfo
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- CN112216411A CN112216411A CN202010981297.XA CN202010981297A CN112216411A CN 112216411 A CN112216411 A CN 112216411A CN 202010981297 A CN202010981297 A CN 202010981297A CN 112216411 A CN112216411 A CN 112216411A
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- Prior art keywords
- exhaust
- temperature measuring
- bypasses
- pressure container
- nuclear power
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 62
- 238000000034 method Methods 0.000 title claims abstract description 38
- 230000008569 process Effects 0.000 claims abstract description 18
- 239000007788 liquid Substances 0.000 claims description 12
- 238000007872 degassing Methods 0.000 claims 1
- 238000013022 venting Methods 0.000 claims 1
- 238000009529 body temperature measurement Methods 0.000 abstract description 30
- 230000005855 radiation Effects 0.000 abstract description 8
- 238000010248 power generation Methods 0.000 abstract description 5
- 239000003381 stabilizer Substances 0.000 description 9
- 238000012360 testing method Methods 0.000 description 6
- 230000003068 static effect Effects 0.000 description 5
- 239000011521 glass Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000002209 hydrophobic effect Effects 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 230000008439 repair process Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
Abstract
The invention relates to the technical field of a primary circuit auxiliary system of a nuclear power station, and provides a primary circuit exhaust method of a pressurized water reactor nuclear power station, which comprises the following steps: s1: filling water into a loop, opening an exhaust valve of the pressure container, observing the reading of a pressure container water level meter, and closing the exhaust valve of the pressure container after the pressure container water level meter is in full range; s2: continuing to fill the water in the primary loop, opening exhaust valves of the temperature measuring bypasses of the primary loop one by one to exhaust the corresponding temperature measuring bypasses, and closing the exhaust valves of the temperature measuring bypasses after the temperature measuring bypasses finish exhausting; in the exhaust process of any temperature measuring bypass, the exhaust valves of the rest temperature measuring bypasses keep a closed state. In the exhaust method, the pressure container is independently exhausted, whether the pressure container completes exhaust or not can be accurately judged by using the pressure container water level meter, and then the temperature measurement bypasses are exhausted one by one, so that the radiation dose of field personnel is reduced, the water leakage risk is reduced, the exhaust operation time can be shortened, and the power generation loss is reduced.
Description
Technical Field
The invention belongs to the technical field of a primary circuit auxiliary system of a nuclear power station, and particularly relates to a primary circuit exhaust method of a pressurized water reactor nuclear power station.
Background
The primary loop of the pressurized water reactor nuclear power station comprises a reactor pressure vessel, a pressure stabilizer, a steam generator and a main pump which are sequentially communicated through a main pipeline, and a temperature measuring bypass is connected in parallel on the main pipeline. After the nuclear power station is overhauled or tested, a primary circuit needs to be filled with water and exhausted, and at present, the primary circuit is usually exhausted by adopting a mode of combining static exhaust and dynamic exhaust. In the static exhaust process, the reactor pressure vessel, the pressure stabilizer and the primary loop temperature measurement bypass synchronously exhaust, exhaust valves of the reactor pressure vessel, the pressure stabilizer and the primary loop temperature measurement bypass are simultaneously connected with the same downstream drainage pipeline, the drainage quantity is limited, exhaust at each position can be interfered with one another, field personnel need to observe and manually judge according to the drainage condition of the downstream pipeline and glass windows of various field equipment to frequently adjust the opening degree of each exhaust point, more field personnel need to frequently operate, the radiation dose received by the field personnel is higher, the exhaust progress of each equipment is often difficult to accurately know through the glass windows of the equipment due to inconsistent air-water content in each pipeline and the equipment, and when the observation result is wrong, the corresponding error operation can occur in the adjustment of the valve, therefore, a water leakage event easily occurs, large-area pollution to a factory building is caused, in order to reduce water leakage risks, field personnel tend to be conservative in adjusting the opening degree of a valve, the static exhaust operation consumes a long time, the static exhaust operation is usually completed within about 6 hours at present, and great power generation loss is caused.
Disclosure of Invention
The invention aims to solve at least one technical problem in the prior art and provides a primary circuit exhaust method of a pressurized water reactor nuclear power station, which can shorten the exhaust operation time, reduce the water leakage risk and reduce the radiation dose received by workers.
In order to achieve the purpose, the invention adopts the technical scheme that: the method for exhausting the primary circuit of the pressurized water reactor nuclear power station comprises the following steps:
s1: filling water into a loop, opening an exhaust valve of the pressure container, observing the reading of a pressure container water level meter, and closing the exhaust valve of the pressure container after the pressure container water level meter is in full range;
s2: continuing to fill the water in the primary loop, opening exhaust valves of the temperature measuring bypasses of the primary loop one by one to exhaust the corresponding temperature measuring bypasses, and closing the exhaust valves of the temperature measuring bypasses after the temperature measuring bypasses finish exhausting; in the exhaust process of any temperature measuring bypass, the exhaust valves of the rest temperature measuring bypasses keep a closed state.
Preferably, in step S2, in the exhaust process of each temperature measuring bypass, the opening degree and the exhaust time of the exhaust valve are preset values.
Preferably, in the step S2, in the exhaust process of each temperature measuring bypass, the opening degree of the exhaust valve is fully opened, and the exhaust time is 10 minutes.
Preferably, the step S2 further includes: and in the exhaust process of each temperature measuring bypass, the exhaust progress of each temperature measuring bypass is judged by observing the liquid level of the downstream drain tank of the primary loop.
Preferably, the downstream hydrophobic tank is RPE003 BA.
Preferably, in step S1, the reading of the pressure vessel water level meter is observed in a main control room.
Preferably, in step S1, the pressure container level is RCP090 MN.
Preferably, in the steps S1 and S2, the exhaust valve of the pressure stabilizer is kept open.
The primary circuit exhaust method of the pressurized water reactor nuclear power station has the beneficial effects that: in the exhaust method, the pressure container is exhausted independently, the liquid level in the pressure container can be accurately measured by using the pressure container water level gauge, then whether the pressure container finishes exhausting or not can be accurately judged, the situation of the liquid level and the air-water ratio in the pressure container does not need to be frequently observed through a glass window on site, the radiation dose received by workers can be effectively reduced, misjudgment is not easy to occur, after the full range of the pressure container water level gauge, the pressure container can be judged to finish exhausting, the water level in a loop also reaches the inlet water level of a voltage stabilizer at the moment and is far higher than the pipeline elevation of each temperature measurement bypass, then the temperature measurement bypasses are exhausted one by one, the exhaust operations of each temperature measurement bypass and the pressure container cannot interfere with each other, and after the interference of other lines is eliminated, the exhaust time of each temperature measurement bypass is only related to the opening degree of the exhaust valve, the proper opening size and the exhaust time can be obtained through calculation or test, the corresponding temperature measurement bypass exhaust valve is opened and closed according to the calculation or test result or observation of the drainage condition of the downstream pipeline in the operation process, the field personnel are not required to frequently observe the exhaust condition and adjust the opening size of each temperature measurement bypass exhaust valve, the frequency and the time of the field personnel entering the operation field are effectively reduced, so the radiation dose received by the field personnel can be effectively reduced, meanwhile, because the pressure container and each temperature measurement bypass exhaust one by one, the drainage quantity of the downstream drainage pipeline in each exhaust step is not easy to exceed the standard, the drainage smoothness can be ensured, the water leakage risk is reduced, the exhaust valve can exhaust with larger opening in the exhaust process of each temperature measurement bypass, the exhaust speed can be accelerated, and the exhaust operation time can be effectively shortened, and the power generation loss is reduced.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
FIG. 1 is a schematic structural diagram of a primary circuit of a conventional pressurized water reactor nuclear power plant;
fig. 2 is a schematic layout of RCP090 MN.
Wherein, in the figures, the respective reference numerals:
10-a main pipeline; 20-a pressure vessel; 30-a voltage stabilizer; 40-a steam generator; 50-main pump; 60-bypass temperature measurement.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects to be solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
Fig. 1 is a schematic structural diagram of a primary circuit of a pressurized water reactor nuclear power station, the primary circuit includes a pressure vessel 20, a voltage stabilizer 30, a steam generator 40 and a main pump 50 which are sequentially communicated by a main pipeline 10, a temperature measuring bypass 60 is further connected in parallel on the main pipeline 10 to measure the temperature of each part of the main pipeline 10, exhaust valves are connected on the pressure vessel 20, the voltage stabilizer 30 and each temperature measuring bypass 60, and in the water filling and exhaust operation of the primary circuit, the exhaust valves are communicated with a downstream drain tank through a downstream drain pipeline.
Fig. 2 is a schematic diagram of the arrangement of RCP090MN, in parallel with pressure vessel 20, to enable direct and accurate measurement of the liquid level within pressure vessel 20.
The preferred embodiment of the invention provides a primary circuit exhaust method of a pressurized water reactor nuclear power station, which comprises the following steps: s1: filling water into a loop, opening an exhaust valve of the pressure container 20, observing the reading of a pressure container water level meter, and closing the exhaust valve of the pressure container 20 after the pressure container water level meter is in full range; s2: continuing to fill water in the loop, opening exhaust valves of the temperature measuring bypasses 60 of the loop one by one to exhaust the corresponding temperature measuring bypasses 60, and closing the exhaust valves of the temperature measuring bypasses 60 after the temperature measuring bypasses 60 finish exhausting; in the process of exhausting any temperature measuring bypass 60, the exhaust valves of the rest temperature measuring bypasses 60 are kept in a closed state. In the exhaust method, the pressure container 20 is independently exhausted, the liquid level in the pressure container 20 can be accurately measured by using the pressure container water level gauge, then whether the pressure container 20 finishes the exhaust can be accurately judged, the conditions of the liquid level and the air-water ratio in the pressure container 20 do not need to be frequently observed on site through a glass window, the dosage size borne by workers can be effectively reduced, the error judgment is not easy to occur, after the pressure container water level gauge is in a full range, the pressure container 20 can be judged to finish the exhaust, the water level in a primary circuit reaches the water level of an inlet of a voltage stabilizer 30 and is far higher than the pipeline elevation of each temperature measurement bypass line, then the temperature measurement bypasses 60 are subjected to the exhaust operation one by one, the exhaust operations of the temperature measurement bypasses 60 and the pressure container 20 cannot interfere with each other, and after the interference of other lines is eliminated, the exhaust time of each temperature measurement bypass 60 is only related to the opening size of the, the proper opening size and the proper exhaust time can be obtained through calculation or test, the corresponding temperature measurement bypass 60 exhaust valve opening and closing operation can be carried out only according to the calculation or test result or observation of the drainage condition of the downstream pipeline in the operation process, the field personnel do not need to observe the exhaust condition and adjust the opening size of each temperature measurement bypass 60 exhaust valve frequently, the frequency and the time of the field personnel entering the operation field are effectively reduced, so that the radiation dose received by the field personnel can be effectively reduced, meanwhile, because the pressure container 20 and each temperature measurement bypass 60 exhaust one by one, the drainage quantity of the downstream drainage pipeline in each exhaust step is not easy to exceed the standard, the drainage smoothness can be ensured, the water leakage risk is reduced, the exhaust valve can exhaust with larger opening in the exhaust process of each temperature measurement bypass 60, and the exhaust speed can be accelerated, therefore, the time of the exhaust operation can be effectively shortened, and the power generation loss can be reduced. The exhaust method can enable the static exhaust flow to exit the major repair critical path, the major repair critical path can be saved for about 6 hours through testing, and the annual power generation loss is reduced by more than ten million yuan.
In the conventional pressurized water reactor nuclear power plant, the number of the steam generators 40 and the main pumps 50 is generally three, and the number of the temperature measuring bypasses 60 is also generally six.
As a preferred embodiment of the present invention, it may also have the following additional technical features.
In this embodiment, in the exhaust process of each temperature measurement bypass 60 in step S2, the opening degree and the exhaust time of the exhaust valve are preset values, because the exhaust of each temperature measurement bypass 60 is performed independently in the exhaust method, the interference of other lines is eliminated, the preset value can be obtained according to calculation or experiments, the field personnel do not need to observe and judge independently, the radiation dose received by the field personnel can be further reduced, the deviation of the exhaust operation and the result caused by the subjective judgment of the field personnel is also reduced, the operation is more standardized, the popularization and the application are facilitated, the number of times of operating the valve is less, the valve wear can be reduced, and the reliability of the valve is ensured. The opening of the exhaust valve influences the exhaust speed of the exhaust valve, and the maximum opening of the exhaust valve is limited by the hydrophobic amount of the downstream hydrophobic pipeline. In the existing pressurized water reactor nuclear power station, the drainage quantity of the downstream drainage pipeline can meet the drainage requirement of the exhaust valve of the single temperature measurement bypass 60 in a fully-opened state, so that in the embodiment, the exhaust valve of the temperature measurement bypass 60 is kept fully opened in the exhaust process to shorten the exhaust time of the temperature measurement bypass 60 as much as possible, the exhaust time is preset to 10 minutes, and the gas in the temperature measurement bypass 60 can be fully exhausted through tests, of course, in other embodiments, the opening degree and the exhaust time of the exhaust valve of the temperature measurement bypass 60 can be flexibly adjusted according to the conditions of corresponding equipment and operation requirements.
In this embodiment, step S2 further includes: in the exhaust process of each temperature measurement bypass 60, the exhaust progress of each temperature measurement bypass 60 is judged by observing the liquid level of the downstream drain tank of the primary loop, so that the temperature measurement bypass 60 is further ensured to exhaust fully, and the water leakage risk can be further reduced. In other embodiments, the opening degree and the exhaust time of the exhaust valve of the temperature measuring bypass 60 may not be preset, and the exhaust progress of the temperature measuring bypass 60 may be determined only by observing the liquid level change of the drain tank downstream of the primary circuit or other positions of the downstream drain pipeline. In the conventional pressurized water reactor nuclear power plant, the number of the downstream drain tank is RPE003BA, and the liquid discharged from each temperature measuring bypass 60 first enters RPE003BA, so that the exhaust state of each temperature measuring bypass 60 can be directly reflected by the liquid level change of RPE003BA, and the judgment result is more accurate. In practical application, the exhaust condition of the temperature measuring bypass 60 can be monitored by other downstream drain tanks capable of reflecting the exhaust progress of the temperature measuring bypass 60.
In this embodiment, in step S1, the reading of the pressure vessel level gauge is observed in the main control room, so that the number of times and time that field personnel enter the field can be further reduced, and the radiation dose to the field personnel can be reduced. In the existing pressurized water reactor nuclear power station, the pressure container water level gauge is numbered as RCP090MN, the liquid level of the pressure container 20 is directly detected, and the detection result is more accurate.
In steps S1 and S2, the exhaust valve of the pressurizer 30 is kept open, the exhaust valve of the pressurizer 30 has the highest height, and the pressurizer 30 completes the exhaust correspondingly after the primary circuit is filled with water.
The above additional technical features can be freely combined and used in superposition by those skilled in the art without conflict.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents and improvements made within the spirit and principle of the present invention are intended to be included within the scope of the present invention.
Claims (8)
1. A primary circuit exhaust method of a pressurized water reactor nuclear power station is characterized by comprising the following steps:
s1: filling water into a loop, opening an exhaust valve of the pressure container, observing the reading of a pressure container water level meter, and closing the exhaust valve of the pressure container after the pressure container water level meter is in full range;
s2: continuing to fill the water in the primary loop, opening exhaust valves of the temperature measuring bypasses of the primary loop one by one to exhaust the corresponding temperature measuring bypasses, and closing the exhaust valves of the temperature measuring bypasses after the temperature measuring bypasses finish exhausting; in the exhaust process of any temperature measuring bypass, the exhaust valves of the rest temperature measuring bypasses keep a closed state.
2. The method as claimed in claim 1, wherein in step S2, the opening and the exhaust time of the exhaust valve of each temperature measuring bypass are preset values during the exhaust process.
3. The method as claimed in claim 2, wherein in the step S2, the exhaust process of each temperature measuring bypass has a fully opened exhaust valve for 10 minutes.
4. A primary circuit exhaust method of a pressurized water reactor nuclear power plant as claimed in any one of claims 1 to 3, wherein said step S2 further includes: and in the exhaust process of each temperature measuring bypass, the exhaust progress of each temperature measuring bypass is judged by observing the liquid level of the downstream drain tank of the primary loop.
5. The primary circuit exhaust method of the pressurized water reactor nuclear power plant as claimed in claim 4, wherein the downstream trap is RPE003 BA.
6. The primary circuit venting method of a pressurized water reactor nuclear power plant as claimed in claim 1, wherein in step S1, the reading of the pressure vessel level gauge is observed in a main control room.
7. The primary circuit degassing method for a pressurized water reactor nuclear power plant as claimed in claim 1, wherein in step S1, the pressure vessel water level is RCP090 MN.
8. The primary circuit exhaust method of the pressurized water reactor nuclear power plant as claimed in claim 1, wherein in steps S1 and S2, an exhaust valve of the pressurizer is kept open.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010981297.XA CN112216411A (en) | 2020-09-17 | 2020-09-17 | Primary circuit exhaust method of pressurized water reactor nuclear power station |
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| CN202010981297.XA CN112216411A (en) | 2020-09-17 | 2020-09-17 | Primary circuit exhaust method of pressurized water reactor nuclear power station |
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| CN112216411A true CN112216411A (en) | 2021-01-12 |
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| CN202010981297.XA Pending CN112216411A (en) | 2020-09-17 | 2020-09-17 | Primary circuit exhaust method of pressurized water reactor nuclear power station |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112908500A (en) * | 2021-01-14 | 2021-06-04 | 中广核研究院有限公司 | Volume control method for non-condensable gas at top of pressure container |
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2020
- 2020-09-17 CN CN202010981297.XA patent/CN112216411A/en active Pending
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