CN108151967B - Nuclear power plant nuclear island factory building liquid leakage rate measuring device - Google Patents
Nuclear power plant nuclear island factory building liquid leakage rate measuring device Download PDFInfo
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- CN108151967B CN108151967B CN201711154796.6A CN201711154796A CN108151967B CN 108151967 B CN108151967 B CN 108151967B CN 201711154796 A CN201711154796 A CN 201711154796A CN 108151967 B CN108151967 B CN 108151967B
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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- 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 belongs to the technical field of liquid leakage measurement in nuclear island plants of nuclear power plants, and particularly relates to a device for measuring the liquid leakage rate of a nuclear island plant of a nuclear power plant, which comprises a cylindrical barrel vertically arranged in a room floor (3) of the nuclear island plant of the nuclear power plant, wherein the top end of the barrel is connected with a drainage pipeline and a groove (9) for discharging radioactive liquid, the bottom end of the barrel is connected with a liquid discharge pipeline (7) provided with a liquid discharge control valve (6), a liquid level meter probe (10) connected with a liquid level meter and a timer (8) is arranged in the barrel, and the leakage rate of the radioactive liquid flowing into the barrel can be calculated through the liquid level meter and the timer (8). This leakage rate measuring device's setting need not extra space requirement, only need replace original floor drain can, have small, it is convenient to change, easily realizes, simple structure's characteristics can calculate the average leakage rate of liquid of obtaining arbitrary period through liquid level information and the timing information that corresponds.
Description
Technical Field
The invention belongs to the technical field of measurement of liquid leakage in nuclear island plants of nuclear power plants, and particularly relates to a device for measuring the liquid leakage rate of the nuclear island plants of the nuclear power plants.
Background
According to the way that radioactive materials reach or irradiate the human body, the external irradiation way and the internal irradiation way can be distinguished, wherein the internal irradiation way mainly refers to the way that the radioactive materials irradiate the human body after entering the human body, and the ways that the radioactive materials enter the human body mainly include ways of inhalation, ingestion, skin ingestion and the like.
In a nuclear island factory building of a pressurized water reactor nuclear power station, due to the phenomena of leakage and leakage of equipment pipelines and various storage tank containers and the evaporation of open pits such as a built-in refueling water tank, a refueling water pool, a spent fuel water pool and the like, airborne radioactive substances are dispersed in the nuclear island factory building, and part of the radioactive substances are used as airborne radioactive effluents and are discharged into the environment from a nuclear island to cause environmental public radiation dose; the other part of the radioactive substance is retained in the nuclear island plant, workers can suck the airborne radioactive substances to cause suction internal irradiation when working in the nuclear island plant, the suction internal irradiation is one of main sources of irradiation suffered by workers of the pressurized water reactor nuclear power station, and in order to ensure that the irradiated dose of the workers meets the requirements of the regulatory standard and is at the lowest level which can be reasonably reached, the airborne radioactive concentration in the nuclear island plant must be evaluated, and the airborne radioactive concentration level is effectively monitored and controlled.
Under the normal operation condition of the nuclear power station, the airborne radioactive substances in the nuclear island plant mainly come from the following ways: 1) leaks in the system and equipment piping that transport the radioactive fluid within the nuclear island plant; 2) evaporation of open pits such as a built-in refueling water tank (IRWST), a reactor refueling water pool and a spent fuel water pool; 3) distribution of radioactive liquids or vapors leaking into the nuclear island plant in the plant vapor phase.
Under normal operating mode, in the factory building airborne radioactive substance on the one hand because radioactive liquid constantly leaks or evaporates and gets into the factory building free space, on the other hand because self decay is got rid of and constantly reduces with the ventilation, consequently, airborne radioactive concentration is in among the dynamic change in the factory building.
When the removal rate of a certain nuclide in a plant due to self decay and ventilation is equal to the generation rate caused by leakage or evaporation, the airborne radioactive concentration of the nuclide does not change with time any more, namely the equilibrium concentration of the nuclide is reached, and the equilibrium concentration Ci of the ith nuclide can be calculated by the following formula:
in the formula:
Ci(t) -airborne radioactive concentration (Bq/m) of the ith nuclear species at time t3)；
LRi-the leakage rate or evaporation rate (g/s) of radioactive liquid in the system or device inside the plant;
Ai-specific activity of radioactivity of the ith nuclide in the liquid, Bq/g;
PFi-the partition factor of the ith species in the vapor phase;
v-free space volume of plant, m3；
λTi-total removal constant, s, of i-th nuclide in the plant-1；
According to the above formula, if the airborne concentration of a certain nuclide at a certain time is accurately estimated, the leakage rate of the radioactive liquid in the system or equipment must be measured. At present, liquid discharged from system pipelines and equipment in a nuclear island room by 'running, overflowing and leaking' is generally discharged through a floor drain in the room and is collected in a water collection pit of a fixed room in a factory building. However, in the design of a nuclear power plant, the specific leakage amount of a certain room or area cannot be given by the system arrangement and the process design, and a corresponding leakage rate cannot be obtained.
Disclosure of Invention
Aiming at the problem that the specific leakage amount of a certain room or region cannot be specifically measured in the nuclear island plant of the conventional nuclear power plant, the invention provides the device which can accurately measure the leakage rate of the radioactive liquid in a certain free space in the nuclear island plant.
In order to achieve the above purposes, the technical scheme adopted by the invention is a nuclear power plant nuclear island plant liquid leakage rate measuring device, which comprises a cylindrical barrel vertically arranged in a room floor of a nuclear island plant of a nuclear power plant, wherein the top end of the barrel is connected with a drainage pipeline and a groove for discharging radioactive liquid, the bottom end of the barrel is connected with a liquid discharge pipeline provided with a liquid discharge control valve, a liquid level meter probe connected with a liquid level meter and a timer is arranged in the barrel, and the leakage rate of the radioactive liquid flowing into the barrel can be calculated through the liquid level meter and the timer.
Further, the liquid discharge pipeline is connected with a nuclear island waste liquid treatment system, and the radioactive liquid enters the nuclear island waste liquid treatment system through the liquid discharge pipeline.
Further, a high liquid level setting value is arranged near the top end of the cylinder body, and a low liquid level setting value is arranged near the bottom end of the cylinder body; the liquid level meter and the timer comprise a liquid level meter and a timer;
when the liquid level of the radioactive liquid in the cylinder is lower than the low liquid level setting value, the liquid level meter automatically triggers the liquid discharge control valve to be closed;
after the liquid discharge control valve is closed, the liquid level meter and the timer start to record the liquid level of the radioactive liquid in the barrel and the time corresponding to the liquid level in real time for calculating the leakage rate;
after the liquid level meter and the timer start real-time recording, when the liquid level of the radioactive liquid rises from bottom to top and contacts the high liquid level setting value, the liquid level meter and the timer stop real-time recording, automatically calculate the leakage rate of the current cycle, and simultaneously control the liquid discharge control valve to be opened to discharge the radioactive liquid; the cycle refers to the time period from the beginning of real-time recording to the end of real-time recording of the liquid level meter and the timer.
When the liquid level of the radioactive liquid in the cylinder is lower than the low liquid level setting value, the liquid level meter automatically triggers the liquid discharge control valve to be closed, and the liquid level meter and the timer start a new real-time recording of the circulation, so that the automatic circulation recording is realized without manual intervention.
Further, an anti-overflow drainage bypass is further arranged on the barrel, and when the liquid level of the radioactive liquid in the barrel exceeds the high liquid level setting value and continues to rise, the radioactive liquid can enter the nuclear island waste liquid treatment system through the anti-overflow drainage bypass.
Further, the liquid level gauge and the timer are located outside the barrel.
Furthermore, the bottom of the cylinder body is of a cone-shaped structure protruding downwards, and the liquid discharge pipeline is connected to the middle of the cone-shaped structure, so that the radioactive liquid can flow out of the cylinder body conveniently.
The invention has the beneficial effects that:
(1) the device has no extra space requirement, only needs to change the original floor drain into the device for measuring the liquid leakage rate of the nuclear island plant of the nuclear power plant, has small volume, is convenient to replace and is easy to realize;
(2) the liquid level meter has a simple structure, the key components are the liquid level meter and the timer, the switch of the timer is triggered through the liquid level, and the average liquid leakage rate in any time period can be calculated through the liquid level information and the corresponding timing information;
(3) the device has a bypass protection design, a high liquid level setting value and an anti-overflow drainage bypass are set, the radioactive liquid is ensured to be discharged according to a designed pipeline, and the waste liquid is prevented from overflowing a monitoring device or overflowing to the floor of a room;
(4) the measurement can be circulated, when the liquid level reaches a high liquid level setting value, the liquid discharge control valve 6 is triggered to be opened, and the liquid is discharged through the liquid discharge pipeline 7. At this time, the total liquid discharge duration corresponding to the high liquid level setting value (at A2 in the figure) is recorded and stored by a timer. When the liquid level decreases to a low liquid level setting (at a1 in the figure), the liquid discharge control valve 6 is triggered to close, and the liquid level meter and the timer are simultaneously triggered to start working, and a new round of measurement and timing is started until the cycle is finished.
Drawings
FIG. 1 is a schematic diagram of a nuclear power plant nuclear island plant fluid leakage rate measurement device according to an embodiment of the invention;
in the figure: 1-overflow-preventing drainage bypass, 2-high liquid level setting value, 3-room floor, 4-liquid level, 5-low liquid level setting value, 6-liquid discharge control valve, 7-liquid discharge pipeline, 8-liquid level meter and timer, 9-drainage pipeline and groove, and 10-liquid level meter probe.
Detailed Description
The invention is further described below with reference to the figures and examples.
As shown in fig. 1, the device for measuring the liquid leakage rate of the nuclear island plant provided by the invention is used for monitoring the leakage rate of the radioactive liquid in the room of the nuclear island plant of the nuclear power plant (the radioactive liquid refers to the sparse drainage water in the room of the nuclear island plant), so as to obtain the leakage rate of the radioactive liquid in the corresponding room, and the device for measuring the liquid leakage rate of the nuclear island plant comprises an anti-overflow drainage bypass 1, a liquid discharge control valve 6, a liquid discharge pipeline 7, a liquid level meter, a timer 8 (including two devices of the liquid level meter and the timer), a liquid level meter probe 10 and the like.
Wherein the barrel is cylindrical, set up perpendicularly in room floor 3 of the nuclear island factory building of nuclear power plant (can replace the floor drain in former floor 3), the room of the nuclear island factory building is used for discharging the drainage pipeline and the slot 9 of radioactive liquid and is connected to the barrel top, liquid discharge pipeline 7 is connected in the barrel bottom, be equipped with liquid discharge control valve 6 on the liquid discharge pipeline 7, level gauge probe 10 sets up in the barrel, level gauge and time-recorder 8 set up outside the barrel, level gauge probe 10 links to each other with level gauge and time-recorder 8, can calculate the leakage rate of the radioactive liquid that flows into in the barrel through level gauge and time-recorder 8.
The liquid discharge pipeline 7 is connected with the nuclear island waste liquid treatment system, and radioactive liquid enters the nuclear island waste liquid treatment system through the liquid discharge pipeline 7.
A high liquid level setting value 2 (shown as A2 in the figure) is arranged near the top end of the barrel, and a low liquid level setting value 5 (shown as A1 in the figure) is arranged near the bottom end of the barrel;
when the liquid level 4 of the radioactive liquid in the cylinder is lower than the low liquid level setting value 5, the liquid discharge control valve 6 is closed in a linkage manner;
after the liquid discharge control valve 6 is closed, the liquid level meter and the timer 8 start to record the numerical value of the liquid level 4 of the radioactive liquid in the cylinder and the time corresponding to the liquid level 4 in real time for calculating the leakage rate;
after the liquid level meter and the timer 8 start real-time recording, when the liquid level of the radioactive liquid rises from bottom to top and contacts the high liquid level setting value 2, the liquid level meter and the timer 8 stop real-time recording, the liquid level meter and the timer 8 automatically calculate the leakage rate of the circulation, and simultaneously the radioactive liquid discharge control valve 6 is controlled to be opened to discharge the radioactive liquid. The cycle refers to the time period from the beginning of real-time recording to the end of real-time recording of the liquid level meter and the timer.
When the liquid level 4 of the radioactive liquid in the cylinder is lower than the low liquid level setting value 5, the liquid level meter automatically triggers the liquid discharge control valve 6 to be closed, and the liquid level meter and the timer 8 start the real-time recording of a new cycle, so that the automatic cycle recording is realized without manual intervention.
The anti-overflow drainage bypass 1 is arranged on the outer side of the barrel, the upper end of the anti-overflow drainage bypass 1 is communicated with the top end of the barrel, the lower end of the anti-overflow drainage bypass 1 is communicated with the lower end of the liquid discharge pipeline 7, and when the liquid level 4 of the radioactive liquid in the barrel exceeds the high liquid level setting value 2 and continues to rise, the radioactive liquid can enter the nuclear island waste liquid treatment system through the anti-overflow drainage bypass 1 (the process does not pass through the liquid discharge control valve 6).
The bottom of the cylinder is a cone-shaped structure protruding downwards (the position of the cone-shaped structure is lower than the low liquid level setting value 5), and a liquid discharge pipeline 7 is connected to the middle part of the cone-shaped structure (namely the lowest position of the cone-shaped structure), so that radioactive liquid can flow out of the cylinder conveniently.
The measurement principle of the nuclear power plant nuclear island plant liquid leakage rate measurement device provided by the invention is as follows:
the cross section area of the cylindrical barrel of the nuclear power plant nuclear island plant liquid leakage rate measuring device is fixed, and the volume corresponding to the liquid level height can be obtained through direct calculation according to the liquid level height. The volume corresponding to the low liquid level setting value A1 is assumed to be V1At this time, the recording time corresponding to the timer is T1After a period of waste liquid leakage is collected, the volume corresponding to the liquid level 4 is ViThe corresponding recording time is TiThen the corresponding leakage rate LR in the room during that time periodiCan be calculated by the following formula:
the device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (6)
1. The utility model provides a nuclear power plant's nuclear island factory building liquid leakage rate measuring device which characterized by: including the columniform barrel of perpendicular setting in room floor (3) of the nuclear island factory building of nuclear power plant, the drainage pipeline and slot (9) that are used for discharging radioactive liquid are connected on the barrel top, liquid discharge pipeline (7) that are equipped with liquid discharge control valve (6) are connected to the barrel bottom, be equipped with level gauge probe (10) of connecting level gauge and time-recorder (8) in the barrel, through level gauge and time-recorder (8) can be to the inflow in the barrel the leakage rate of radioactive liquid calculates.
2. The nuclear power plant nuclear island plant liquid leakage rate measuring device of claim 1, characterized by: the liquid discharge pipeline (7) is connected with a nuclear island waste liquid treatment system, and the radioactive liquid enters the nuclear island waste liquid treatment system through the liquid discharge pipeline (7).
3. The nuclear power plant nuclear island plant liquid leakage rate measuring device of claim 2, characterized in that: a high liquid level setting value (2) is arranged near the top end of the barrel, and a low liquid level setting value (5) is arranged near the bottom end of the barrel; the liquid level meter and the timer (8) comprise a liquid level meter and a timer;
when the liquid level (4) of the radioactive liquid in the barrel is lower than the low liquid level setting value (5), the liquid level meter automatically triggers the liquid discharge control valve (6) to be closed;
after the liquid discharge control valve (6) is closed, the liquid level meter and the timer (8) start to record the liquid level of the radioactive liquid in the barrel and the time corresponding to the liquid level in real time for calculating the leakage rate;
after the liquid level meter and the timer (8) start real-time recording, when the liquid level (4) of the radioactive liquid rises from bottom to top and contacts the high liquid level setting value (2), the liquid level meter and the timer (8) stop real-time recording, automatically calculate the leakage rate of the circulation, and simultaneously control the liquid discharge control valve (6) to be opened to discharge the radioactive liquid; the cycle refers to a time period from the start of real-time recording to the termination of real-time recording of the liquid level meter and the timer (8);
when the liquid level (4) of the radioactive liquid in the barrel is lower than the low liquid level setting value (5), the liquid level meter automatically triggers the liquid discharge control valve (6) to be closed, and the liquid level meter and the timer (8) start the real-time recording of a new cycle, so that the cycle recording is automatically carried out without manual intervention.
4. The nuclear power plant nuclear island plant liquid leakage rate measuring device of claim 3, characterized by: the barrel is further provided with an anti-overflow drainage bypass (1), and when the liquid level (4) of the radioactive liquid in the barrel exceeds the high liquid level setting value (2) and continues to rise, the radioactive liquid can enter the nuclear island waste liquid treatment system through the anti-overflow drainage bypass (1).
5. The nuclear power plant nuclear island plant liquid leakage rate measuring device of claim 1, characterized by: the level gauge and the timer (8) are located outside the barrel.
6. The nuclear power plant nuclear island plant liquid leakage rate measuring device of claim 1, characterized by: the bottom of the cylinder body is of a cone-shaped structure protruding downwards, and the liquid discharge pipeline (7) is connected to the middle of the cone-shaped structure, so that the radioactive liquid can flow out of the cylinder body conveniently.
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| CN110955962B (en) * | 2019-11-14 | 2023-04-11 | 中国核电工程有限公司 | Method for determining dilution diffusion control requirements for liquid effluent discharge |
| CN111695762B (en) * | 2020-04-29 | 2023-05-05 | 中国核电工程有限公司 | Correction method and device for nuclear accident diffusion result and result evaluation method and system |
| CN114061857A (en) * | 2021-11-03 | 2022-02-18 | 中核核电运行管理有限公司 | Liquid leakage rate monitoring device |
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