CN112037946A - Leakage detection method and device for steam generator of nuclear power station - Google Patents
Leakage detection method and device for steam generator of nuclear power station Download PDFInfo
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- CN112037946A CN112037946A CN202010704077.2A CN202010704077A CN112037946A CN 112037946 A CN112037946 A CN 112037946A CN 202010704077 A CN202010704077 A CN 202010704077A CN 112037946 A CN112037946 A CN 112037946A
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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- G21C17/002—Detection of leaks
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- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/04—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point
- G01M3/20—Investigating fluid-tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
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Abstract
The application belongs to the technical field of nuclear power station steam generators, and particularly relates to a leakage detection method and device for a nuclear power station steam generator. The method comprises the following steps: acquiring a first radioactivity obtained by detecting a preset radioactive element in water of a loop by an element analysis device; presetting radioactive elements in the water of the second loop to be respectively detected at two different time points by the element analysis equipment, and then obtaining second radioactivity obtained by detection; determining the water supplement amount in unit time corresponding to the two loops; determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate of the steam generator according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; dynamic adjustment parameters of energy balance; and performing leakage detection processing on the steam generator according to the target mass leakage rate. The method has wider application range.
Description
Technical Field
The application relates to the technical field of steam generators of nuclear power plants, in particular to a leakage detection method and device for the steam generators of the nuclear power plants.
Background
In a pressurized water reactor nuclear power plant, coolant in a primary circuit passes through the reactor to convert nuclear energy into coolant heat energy. The primary loop and the secondary loop are connected through a steam generator. The heat energy of the primary loop coolant is transferred to the secondary loop through the steam generator, so that steam is generated, and the steam turbine drives the generator to generate electricity. The steam generator, which is a key device for transferring heat from the primary circuit to the secondary circuit, must reliably separate the primary circuit from the secondary circuit. If the steam generator leaks, the water quality of the secondary loop and the safe operation of the system are greatly deteriorated, radiation can directly enter the nuclear secondary loop system, and the consequence hidden danger is very serious. Therefore, it is important to enhance the detection of the leakage of the steam generator.
A traditional method for detecting leakage of a steam generator of a nuclear power station is mainly used for judging the leakage condition of the steam generator by measuring the tritium content of main steam. However, the current method for detecting leakage of a steam generator in a nuclear power plant is only suitable for detecting leakage of a steam generator with steam in a normal operation state, and for a steam generator in other states or a steam generator which does not generate steam temporarily, the method cannot perform leakage detection, has a narrow application range, and has great limitations.
Disclosure of Invention
In view of the above, there is a need to provide a leak detection method and apparatus for a steam generator of a nuclear power plant, which have wider applicability.
A method of leak detection of a nuclear power plant steam generator, the method comprising:
acquiring a first radioactivity obtained by detecting a preset radioactive element in water of a loop by an element analysis device;
after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
determining the water supplement amount in unit time corresponding to the two loops;
determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and performing leakage detection processing on the steam generator according to the target mass leakage rate.
In one embodiment, the two different time points include a previous time point and a subsequent time point; the second radioactivity comprises a preceding second radioactivity corresponding to the preceding point in time and a following second reflected radioactivity corresponding to the following point in time; the method further comprises the following steps:
when the time difference between the two different time points is less than or equal to a preset time length, executing the step of determining the dynamic energy balance adjustment parameter and the subsequent steps;
and when the time difference between the two different time points is greater than a preset time length, determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second later reflected radioactivity and the water supplement amount in unit time.
In one embodiment, the determining the energy balance dynamic adjustment parameter includes:
determining the mass of water in the secondary loop;
and determining an energy balance dynamic adjusting parameter according to the mass of the water, the water replenishing amount in the unit time and the time difference between the two different time points.
In one embodiment, the acquiring a second detected radioactivity after the elemental analysis device detects the predetermined radioactive element in the water of the two loops at two different time points respectively includes:
when the leakage detection mode of the steam generator is a rapid detection mode, respectively detecting the preset radioactive elements in the first sample at two different time points by the element analysis equipment, and acquiring second detected radioactivity;
and the first sample is obtained by sampling from the water of the two loops according to a first sampling mode corresponding to the rapid detection mode.
In one embodiment, the acquiring a second detected radioactivity after the elemental analysis device detects the predetermined radioactive element in the water in the two loops at two different time points respectively further includes:
when the leakage detection mode of the steam generator is an accurate detection mode, respectively detecting the preset radioactive elements in the second sample at two different time points by the element analysis equipment, and acquiring second detected radioactivity;
the second sample is obtained by sampling from the water of the second loop according to a second sampling mode corresponding to the accurate detection mode; the preset water taking amount corresponding to the second sampling mode is larger than the preset water taking amount corresponding to the first sampling mode, and the preset analysis time corresponding to the second sampling mode is larger than the preset analysis time corresponding to the first sampling mode.
In one embodiment, the method further comprises:
when a nuclear power station radiation monitoring system is in an unavailable state or when a nuclear power unit corresponding to the steam generator is in a starting state, judging that a leakage detection mode of the steam generator is a quick detection mode;
the nuclear power station radiation monitoring system is used for monitoring the leakage condition of the steam generator.
In one embodiment, the predetermined radioactive element comprises tritium; the method further comprises the following steps:
when the detection mode of the steam generator is monitored to be a tritium specific activity detection mode, executing the step of obtaining a first activity obtained by detecting a preset radioactive element in water in a loop by the element analysis equipment and the subsequent steps;
when the detection mode of the steam generator is monitored to be a ray detection mode, acquiring radioactivity data of a preset ray corresponding to the preset radioactivity element, which is detected by radioactivity analysis equipment, and performing leakage detection processing on the steam generator according to the radioactivity data.
A leak detection apparatus for a steam generator of a nuclear power plant, the apparatus comprising:
the system comprises an acquisition module, a detection module and a control module, wherein the acquisition module is used for acquiring first radioactivity obtained by detecting preset radioactive elements in water of a loop by element analysis equipment; after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
the determining module is used for determining the water supplementing amount in unit time corresponding to the two loops; determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and the detection module is used for detecting and processing the leakage of the steam generator according to the target mass leakage rate.
A computer device comprising a memory, a processor and a computer program stored on the memory and executable on the processor, wherein the processor when executing the computer program implements the steps of:
acquiring a first radioactivity obtained by detecting a preset radioactive element in water of a loop by an element analysis device;
after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
determining the water supplement amount in unit time corresponding to the two loops;
determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and performing leakage detection processing on the steam generator according to the target mass leakage rate.
A computer-readable storage medium, on which a computer program is stored, which, when being executed by a processor, carries out the steps of:
acquiring a first radioactivity obtained by detecting a preset radioactive element in water of a loop by an element analysis device;
after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
determining the water supplement amount in unit time corresponding to the two loops;
determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and performing leakage detection processing on the steam generator according to the target mass leakage rate.
According to the leakage detection method and device for the steam generator of the nuclear power station, the first radioactivity obtained by detecting the preset radioactive elements in the water of the primary loop through the element analysis equipment is obtained. After the element analysis equipment detects the preset radioactive elements in the water of the two loops at two different time points respectively, the second radioactivity activity obtained by detection is obtained, so that the leakage rate of the steam generator of the nuclear power station is converted into the leakage rate of the first loop. And determining the water supplement amount in unit time corresponding to the two loops, and supplementing the water loss amount in the two loops through the water supplement amount so as to keep the quality of water in the two loops unchanged. And determining an energy balance dynamic adjustment parameter so that the amount of the liquid in the first loop and the second loop is kept in dynamic balance. And determining a target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first activity, the second activity, the dynamic energy balance adjustment parameter and the water supplement amount in unit time. And performing leakage detection processing on the steam generator according to the target mass leakage rate. Therefore, the leakage detection is carried out on the corresponding steam generator through the water in the primary loop and the secondary loop, the leakage detection device is not only suitable for the leakage detection of the steam generator with steam in a normal operation state, but also can be used for the leakage detection of the steam generator in other states or the steam generator which does not generate steam temporarily, and the application range is wide.
Drawings
FIG. 1 is a diagram illustrating an exemplary method for leak detection in a steam generator of a nuclear power plant;
FIG. 2 is a schematic flow chart illustrating a leak detection method for a steam generator of a nuclear power plant according to one embodiment;
FIG. 3 is a schematic flow chart of the steps for determining dynamic adjustment parameters for energy balance in one embodiment;
FIG. 4 is a block diagram showing a leak detection apparatus for a steam generator of a nuclear power plant according to an embodiment;
FIG. 5 is a block diagram showing a leak detection apparatus for a steam generator of a nuclear power plant according to another embodiment;
FIG. 6 is a diagram illustrating an internal structure of a computer device according to an embodiment.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application is described in further 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 present application and are not intended to limit the present application.
The method for detecting the leakage of the steam generator of the nuclear power station can be applied to the application environment shown in the figure 1. The application environment includes a terminal 102, an elemental analysis device 104, and a steam generator 106. The terminal 102 and the element analysis device 104 communicate via a network. The terminal 102 communicates with the steam generator 106 through a network. Elemental analysis device 104 is in communication with steam generator 106 via a network. The terminal 102 may specifically include a desktop terminal or a mobile terminal. The mobile terminal may specifically include at least one of a mobile phone, a tablet computer, a notebook computer, and the like. Those skilled in the art will understand that the application environment shown in fig. 1 is only a part of the scenario related to the present application, and does not constitute a limitation to the application environment of the present application.
The terminal 102 obtains a first activity detected by the elemental analysis device 104 on a predetermined radioactive element in water in a loop corresponding to the steam generator 106. After the element analysis device 104 detects the preset radioactive elements in the two loops of water corresponding to the steam generator 106 at two different time points, the terminal 102 obtains a second detected activity. The terminal 102 determines the amount of make-up water per unit time for the two circuits. The terminal 102 determines the dynamic energy balance adjustment parameter, and determines a target mass leakage rate corresponding to the steam generator between the first and second circuits according to the first and second radioactivity, the dynamic energy balance adjustment parameter, and the water supplement amount per unit time. And the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop. The terminal 102 performs a leak detection process on the steam generator 106 based on the target mass leak rate.
In one embodiment, as shown in fig. 2, a leak detection method for a steam generator in a nuclear power plant is provided, which is described by taking the method as an example applied to a terminal 102 in fig. 1, and comprises the following steps:
s202, acquiring first radioactivity obtained by detecting preset radioactive elements in water of a loop by the element analysis equipment.
It is understood that the pressurized water reactor of current nuclear power plants may include a primary circuit and a secondary circuit. The apparatus of a loop may comprise: the reactor, the voltage stabilizer, the main pump, the primary side of the steam generator and the like. The two-loop apparatus may include: the system comprises a steam turbine generator set, a condenser, a condensate pump, a feed water heater, a deaerator, a feed water pump, a steam generator secondary side, a steam-water separation reheater and the like. The steam generator is a heat exchange device located between the primary and secondary circuits. The steam generator transfers the heat of the water in the primary loop to the water in the secondary loop, so that the water is changed into steam for the steam turbine to do work.
The preset radioactive element is an element with radioactivity in a reactor used for power generation in a nuclear power station. The first activity is a predetermined activity of a radioactive element in the water of the circuit.
Specifically, the water in the primary circuit carries a predetermined radioactive element. The radioactivity analysis equipment can be used for analyzing the radioactivity of the preset radioactive elements in the water sampled from the loop to obtain first radioactivity. The terminal can obtain a first radioactivity which is obtained by detecting the preset radioactive elements in the water of the loop by the element analysis equipment.
In one embodiment, after the element analysis device detects the first radioactivity detected by the preset radioactive elements in the water in the loop, the first radioactivity may be stored in a corresponding server for storage. Furthermore, the terminal can obtain a first radioactivity detected by the preset radioactive elements in the water of the loop from the server.
In one embodiment, the elemental analysis device may communicate with the terminal over a network. After the elemental analysis device detects the first radioactivity obtained by detecting the preset radioactive elements in the water of the loop, the elemental analysis device may send the first radioactivity to the terminal. Furthermore, the terminal can receive a first radioactivity which is sent by the element analysis equipment and is obtained by detecting the preset radioactive elements in the water of the loop.
In one embodiment, after the elemental analysis device detects the first radioactivity detected by the predetermined radioactive element in the water of the loop, the user may directly read the corresponding first radioactivity from the elemental analysis device. Further, the user may input the read first radioactivity into the terminal. The terminal can obtain a first radioactivity which is input by a user and obtained by detecting a preset radioactive element in water of a loop.
In one embodiment, the terminal may obtain a first activity detected by sampling water in any device in the primary circuit (e.g., any of the reactor, the pressurizer, the main pump, and the primary side of the steam generator).
And S204, after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, acquiring second radioactivity obtained by detection.
Wherein the second activity is the activity of a predetermined radioactive element in the water of the second circuit.
Specifically, when the steam generator leaks, i.e., the water in the primary circuit leaks to the secondary circuit, the water in the secondary circuit will also carry the predetermined radioactive elements. The element analysis equipment can detect the radioactive elements in the water of the two loops at two different time points respectively, and then the terminal can acquire the second radioactivity obtained by detection after the element analysis equipment detects the radioactive elements in the water of the two loops at two different time points respectively.
In one embodiment, after the elemental analysis device detects the second radioactivity detected by the preset radioactive elements in the water in the two loops, the second radioactivity may be stored in a corresponding server for storage. Furthermore, the terminal can acquire second radioactivity detected by the preset radioactive elements in the water of the two loops from the server.
In one embodiment, the elemental analysis device may communicate with the terminal over a network. After the elemental analysis device detects the second radioactivity, which is obtained by detecting the preset radioactive elements in the water of the two loops, the elemental analysis device can send the second radioactivity to the terminal. And then, the terminal can receive second radioactivity which is sent by the element analysis equipment and is obtained by detecting the preset radioactive elements in the water of the two loops.
In one embodiment, after the elemental analysis device detects the second activity obtained by detecting the predetermined radioactive element in the water of the two-circuit, the user can directly read the corresponding second activity from the elemental analysis device. Further, the user may input the read second radioactivity into the terminal. The terminal can obtain second radioactivity which is input by a user and obtained by detecting the preset radioactive elements in the water of the two loops.
In one embodiment, the terminal may obtain a second radioactivity detected by sampling water in any one of the two circuits (e.g., any one of a steam turbine generator set, a condenser, a condensate pump, a feedwater heater, a deaerator, a feedwater pump, a steam generator secondary side, and a moisture separator reheater).
And S206, determining the water replenishing amount in unit time corresponding to the two loops.
Specifically, the water in the two corresponding circuits of the same unit is fixed. After the water in the two circuits becomes part of the steam loss, the water in the two circuits needs to be replenished. The water loss amount in the two loops is fixed in unit time, and the corresponding water replenishing amount in unit time is also fixed. The terminal can directly determine the water supplement amount in unit time corresponding to the two loops.
For example, in the case of the auxiliary water supply system, the water supply amount of the single steam generator is fixed to 20 tons/hour. In the case of the main water supply system, the total amount of water supply to the secondary-circuit-side condenser of the steam generator was fixed to 10 tons/hour.
S208, determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the first loop and the second loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; and the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop.
The energy balance dynamic adjustment parameter is a parameter for dynamically adjusting energy balance and is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop. The target mass leakage rate is the mass of water leaking from one circuit to the second circuit per unit time, i.e., the rate at which water in the first circuit leaks to the second circuit.
In particular, steam generator leakage is a dynamic process. In order to keep the amount of water leaked in the first loop in dynamic balance with the amount of water added in the second loop, the terminal can directly determine the dynamic adjustment parameter of the energy balance. Furthermore, the terminal can determine a target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first radioactivity, the second radioactivity, the dynamic energy balance adjustment parameter and the water supplement amount in unit time.
And S210, performing leakage detection processing on the steam generator according to the target mass leakage rate.
Specifically, after the target mass leakage rate corresponding to the steam generator is determined, the terminal may perform leakage detection processing on the steam generator according to the target mass leakage rate.
In one embodiment, the terminal may determine a preset mass leakage rate set for the steam generator in the operating specification (e.g., the preset mass leakage rate is 44 tons/hour). After the target mass leakage rate corresponding to the steam generator is determined by the terminal, the target mass leakage rate can be compared with the preset mass leakage rate by the terminal. When the target mass leakage rate is greater than the preset mass leakage rate, the terminal may determine that the corresponding steam generator has leaked. Further, the terminal can generate a corresponding alarm signal and alarm.
According to the leakage detection method of the nuclear power station steam generator, the first radioactivity obtained by detecting the preset radioactive elements in the water of the primary loop through the element analysis equipment is obtained. After the element analysis equipment detects the preset radioactive elements in the water of the two loops at two different time points respectively, the second radioactivity activity obtained by detection is obtained, so that the leakage rate of the steam generator of the nuclear power station is converted into the leakage rate of the first loop. And determining the water supplement amount in unit time corresponding to the two loops, and supplementing the water loss amount in the two loops through the water supplement amount so as to keep the quality of water in the two loops unchanged. And determining an energy balance dynamic adjustment parameter so that the amount of the liquid in the first loop and the second loop is kept in dynamic balance. And determining a target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first activity, the second activity, the dynamic energy balance adjustment parameter and the water supplement amount in unit time. And performing leakage detection processing on the steam generator according to the target mass leakage rate. Therefore, the leakage detection is carried out on the corresponding steam generator through the water in the primary loop and the secondary loop, the leakage detection device is not only suitable for the leakage detection of the steam generator with steam in a normal operation state, but also can be used for the leakage detection of the steam generator in other states or the steam generator which does not generate steam temporarily, and the application range is wide.
And, conventional methods for leak detection of steam generators based on nuclear power plant radiation monitoring systems require that the operating program require monitoring every 12 hours during periods when the nuclear power plant radiation monitoring system is unavailable. The sampling and sample preparation process is adopted, and the steam generator can be detected in a relatively short time (for example, 8 hours) by using the accurate detection mode in the invention. The sampling and sample preparation process is included, and if the rapid detection mode is used, the detection of the steam generator can be completed in a shorter time (for example, 60 minutes). Compared with the traditional method for detecting the leakage of the steam generator based on the nuclear power station radiation monitoring system, the method can detect the leakage of the steam generator without interval of twelve hours, and can feed back the leakage detection result in time.
In one embodiment, the two different time points comprise a preceding time point and a following time point; the second radioactivity comprises a preceding second radioactivity corresponding to a preceding point in time and a following second reflected radioactivity corresponding to a following point in time; the leakage detection method of the steam generator of the nuclear power station further comprises the following steps: when the time difference between two different time points is less than or equal to the preset time length, executing the step of determining the dynamic energy balance adjustment parameter and the subsequent steps; and when the time difference between the two different time points is greater than the preset time length, determining the target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first radioactivity, the second reflected radioactivity and the water supplement amount in unit time.
Wherein the previous second activity is a second activity obtained by detecting a predetermined radioactive element in the water of the two circuits at a previous time point of the two different time points. The second radioactivity is the second radioactivity detected by detecting the predetermined radioactive element in the water of the two circuits at the later one of the two different time points.
Specifically, the terminal may compare a time difference between two different time points with a preset duration. And when the time difference between the two different time points is less than or equal to the preset time length, the terminal can execute the step of determining the dynamic energy balance adjustment parameter and the subsequent steps. Namely, the terminal can determine the dynamic energy balance adjustment parameter and determine a target mass leakage rate corresponding to the steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the dynamic energy balance adjustment parameter and the water supplement amount in unit time; and performing leakage detection processing on the steam generator according to the target mass leakage rate. When the time difference between the two different time points is greater than the preset time length, the terminal can determine the target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first radioactivity, the second reflected radioactivity and the water supplement amount in unit time.
In one embodiment, when the time difference between two different time points is less than or equal to a preset time length, the target mass leakage rate F may be calculated by the following formula:
wherein A is a first radioactivity obtained by detecting a preset radioactive element in water in a loop. P is the water supplement amount in the unit time corresponding to the two loops, namely the water loss amount in the unit time corresponding to the two loops. C1 is a previous second activity obtained by detecting a predetermined radioactive element in the water of the second circuit at a previous time T1. C2 is the later second radioactivity measured by the detection of the predetermined radioactive element in the water of the second circuit at the later time point T2. K is an energy balance dynamic adjusting parameter.
In one embodiment, when the time difference between two different time points is greater than the predetermined time period, it can be understood that the two circuits reach an equilibrium state, i.e., the value of C2 is much greater than the value of C1, and the target mass leakage rate F can be calculated by the following formula:
in the above embodiment, the target mass leakage rate corresponding to the steam generator located between the first loop and the second loop is selected and calculated correspondingly by determining the relationship between the time difference between the two different time points and the preset time duration. In this way, the calculation speed of the target mass leakage efficiency can be improved.
In an embodiment, as shown in fig. 3, the step of determining the dynamic energy balance adjustment parameter in step S208 specifically includes: steps S302 to S304:
s302, determining the quality of water in the two loops.
Specifically, the quality of the water in the two circuits is kept constant for the same unit. The terminal can directly determine the quality of the water in the two circuits.
And S304, determining an energy balance dynamic adjusting parameter according to the mass of the water, the water replenishing amount in unit time and the time difference between two different time points.
Specifically, the terminal may acquire the amount of make-up water per unit time and the time difference between two different points in time after determining the quality of the water in the two circuits. Furthermore, the terminal can determine the dynamic energy balance adjusting parameter according to the water quality, the water replenishing amount in unit time and the time difference between two different time points.
In one embodiment, the energy balance dynamic adjustment parameter K may be expressed as:
where M is the mass of water in the two circuits. The time difference between the two different time points is T2-T1, and the larger the Δ T, the closer the K value approaches 0. For example, for a condenser with 3 tons/hour of make-up water, the change in K value can be shown in the following table:
| Δ T (hours) | 10 | 50 | 100 | 500 | 1000 |
| K | 0.96 | 0.80 | 0.65 | 0.11 | 0.01 |
In the above embodiment, the dynamic energy balance adjustment parameter is determined by determining the mass of water in the two circuits, the amount of make-up water per unit time, and the time difference between two different time points. In this way, a dynamic balancing of the mass between the primary and secondary circuits is achieved.
In an embodiment, the step S204, that is, the step of obtaining the second detected radioactivity after the elemental analysis device detects the preset radioactive elements in the water of the second loop at two different time points, specifically includes: when the leakage detection mode of the steam generator is a quick detection mode, after the element analysis equipment respectively detects the preset radioactive elements in the first sample at two different time points, obtaining second radioactivity obtained by detection; and the first sample is obtained by sampling from the water of the two loops according to a first sampling mode corresponding to the rapid detection mode.
Wherein, the rapid detection mode is a detection mode for rapidly detecting the leakage condition of the steam generator. The first sampling mode is a sampling mode for realizing rapid detection of leakage of the steam generator. The first sample is obtained by sampling the water in the two loops according to a first sampling mode corresponding to the rapid detection mode.
Specifically, the terminal may monitor a locally selected leak detection mode of the steam generator in real time. When the terminal monitors that the leakage detection mode of the steam generator is a quick detection mode, the terminal can obtain second radioactivity activity obtained through detection after the element analysis equipment detects the preset radioactive elements in the first sample at two different time points respectively.
It can be understood that when the leakage rate analysis result needs to be given quickly, the terminal can select a quick detection mode. The first sampling mode may specifically be: for example, the water intake for the water in the two circuits is 1 ml and the analysis time is 1 minute.
In the above embodiment, by setting the fast detection mode, on the premise of ensuring the detection accuracy, the time spent on detection is shortened, and the obtained second radioactivity can be detected fast, so that the detection speed of the leakage of the steam generator is increased.
In an embodiment, the step S204, that is, the step of obtaining a second detected radioactivity after the elemental analysis device detects the preset radioactive elements in the water in the two loops at two different time points, further includes: when the leakage detection mode of the steam generator is the accurate detection mode, detecting preset radioactive elements in a second sample at two different time points respectively by the element analysis equipment, and acquiring second detected radioactivity; the second sample is obtained by sampling from the water of the second loop according to a second sampling mode corresponding to the accurate detection mode; the preset water intake amount corresponding to the second sampling mode is larger than the preset water intake amount corresponding to the first sampling mode, and the preset analysis time corresponding to the second sampling mode is larger than the preset analysis time corresponding to the first sampling mode.
Wherein, the accurate detection mode is a detection mode for accurately detecting the leakage condition of the steam generator. The second sampling mode is a sampling mode for realizing accurate detection of the leakage condition of the steam generator. The second sample is obtained by sampling the water in the two loops according to a second sampling mode corresponding to the accurate detection mode. The preset water intake amount corresponding to the second sampling mode is larger than the preset water intake amount corresponding to the first sampling mode, and the preset analysis time corresponding to the second sampling mode is larger than the preset analysis time corresponding to the first sampling mode.
Specifically, the terminal may monitor a locally selected leak detection mode of the steam generator in real time. When the terminal monitors that the leakage detection mode of the steam generator is the accurate detection mode, the terminal can obtain the second radioactivity activity obtained through detection after the element analysis equipment detects the preset radioactive elements in the second sample at two different time points respectively.
It will be appreciated that the terminal may choose a fast and accurate way when it is desired to give accurate leak rate analysis results. The second sampling mode may specifically be: for example, the water intake for the water in the two circuits is 3 ml and the analysis time is 100 minutes.
In the above embodiment, by setting the accurate detection mode, when the steam generator has a micro leak, the obtained second activity may be accurately detected. Thereby improving the detection accuracy of the leakage of the steam generator.
In one embodiment, the method for detecting leakage of a steam generator in a nuclear power plant specifically further includes: when the nuclear power station radiation monitoring system is in an unavailable state or when a nuclear power unit corresponding to a steam generator is in a starting state, judging that the leakage detection mode of the steam generator is a quick detection mode; the nuclear power station radiation monitoring system is used for monitoring the leakage condition of the steam generator.
Specifically, the terminal may determine a leak detection manner of the steam generator in real time. The terminal can be respectively communicated with a nuclear power station radiation monitoring system and a nuclear power unit corresponding to the steam generator. When the terminal monitors that the nuclear power station radiation monitoring system is in an unavailable state, or when a nuclear power unit corresponding to the steam generator is in a starting state, the terminal can judge that the leakage detection mode of the steam generator is a quick detection mode.
In the above embodiment, the leak detection mode of the steam generator is determined by monitoring the starting state of the nuclear power plant radiation monitoring system or the nuclear power generating unit corresponding to the steam generator. Thus, the leakage detection efficiency of the steam generator is further improved.
In one embodiment, the predetermined radioactive element comprises tritium. The method for detecting the leakage of the steam generator of the nuclear power station specifically comprises the following steps: when the detection mode of the steam generator is monitored to be a tritium specific activity detection mode, executing a step of acquiring a first activity obtained by detecting a preset radioactive element in water in a loop by an element analysis device and subsequent steps; when the detection mode of the steam generator is monitored to be a ray detection mode, acquiring radioactivity data of a preset ray corresponding to a preset radioactive element, which is detected by a radioactivity analysis device, and performing leakage detection processing on the steam generator according to the radioactivity data.
Wherein tritium is a radioactive element having radioactivity in a reactor of a nuclear power plant. The tritium specific activity detection mode is a detection mode for performing detection treatment on the steam generator according to tritium radioactivity. The radiation detection mode is a detection mode in which a detection process is performed on the steam generator based on a radiation (e.g., a γ -ray) of tritium.
Specifically, the terminal may monitor a detection mode of the locally selected steam generator in real time. When the detection mode of the steam generator is monitored to be a tritium specific activity detection mode, the terminal can execute the step of obtaining the first radioactivity obtained by detecting the preset radioactive elements in the water of the primary loop by the element analysis equipment and the subsequent steps. Namely, the terminal can execute the first radioactivity obtained by detecting the preset radioactive elements in the water of the loop by the element analysis equipment. And after the element analysis equipment detects the preset radioactive elements in the water of the second loop at two different time points respectively, acquiring second radioactivity obtained by detection. And determining the water supplement amount in unit time corresponding to the two loops. And determining an energy balance dynamic adjusting parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjusting parameter and the water supplement amount in unit time. And performing leakage detection processing on the steam generator according to the target mass leakage rate. When the detection mode of the steam generator is monitored to be a ray detection mode, the terminal can acquire radioactivity data of the preset rays corresponding to the preset radioactive elements, which are detected by the radioactivity analysis equipment, and perform leakage detection processing on the steam generator according to the radioactivity data.
In one embodiment, the elemental analysis device may specifically be a tritium analyzer (e.g., a scintillation counter). The radioactivity analyzing device may particularly be a total gamma meter.
In the above embodiment, the method of performing the leak detection process on the steam generator is selected by determining the current detection mode of the steam generator. Thus, the detection mode of the steam generator is more flexible.
It should be understood that although the various steps of fig. 2 and 3 are shown sequentially in order, these steps are not necessarily performed sequentially in order. The steps are not performed in the exact order shown and described, and may be performed in other orders, unless explicitly stated otherwise. Moreover, at least some of the steps in fig. 2 and 3 may include multiple sub-steps or multiple stages, which are not necessarily performed at the same time, but may be performed at different times, and the order of performing the sub-steps or stages is not necessarily sequential, but may be performed alternately or alternately with other steps or at least some of the sub-steps or stages of other steps.
In one embodiment, as shown in fig. 4, there is provided a leak detection apparatus 400 of a steam generator of a nuclear power plant, including: an obtaining module 401, a determining module 402 and a detecting module 403, wherein:
an obtaining module 401, configured to obtain a first radioactivity obtained by detecting a preset radioactive element in water in a loop by an element analysis device; and after the element analysis equipment detects the preset radioactive elements in the water of the second loop at two different time points respectively, acquiring second radioactivity obtained by detection.
A determining module 402, configured to determine a water supplement amount in a unit time corresponding to the two loops; determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; and the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop.
And the detection module 403 is used for performing leakage detection processing on the steam generator according to the target mass leakage rate.
In one embodiment, the determining module 402 is further configured to determine a target mass leakage rate of the steam generator between the first and second circuits according to the first radioactivity, the second reflected radioactivity, and the amount of water replenished per unit time when the time difference between the two different time points is greater than a predetermined time.
In one embodiment, the determination module 402 is also used to determine the quality of the water in the secondary loop; and determining an energy balance dynamic adjusting parameter according to the mass of the water, the water supplement amount in unit time and the time difference between two different time points.
In one embodiment, the obtaining module 401 is further configured to, when the leak detection mode of the steam generator is a fast detection mode, obtain a second detected radioactivity after the elemental analysis device detects the preset radioactive elements in the first sample at two different time points, respectively; and the first sample is obtained by sampling from the water of the two loops according to a first sampling mode corresponding to the rapid detection mode.
In one embodiment, the obtaining module 401 is further configured to, when the leak detection mode of the steam generator is the accurate detection mode, obtain the detected second radioactivity after the elemental analysis device detects the preset radioactive elements in the second sample at two different time points, respectively; the second sample is obtained by sampling from the water of the second loop according to a second sampling mode corresponding to the accurate detection mode; the preset water intake amount corresponding to the second sampling mode is larger than the preset water intake amount corresponding to the first sampling mode, and the preset analysis time corresponding to the second sampling mode is larger than the preset analysis time corresponding to the first sampling mode.
In one embodiment, the obtaining module 401 is further configured to, when it is monitored that the detection mode of the steam generator is a radiation detection mode, obtain radioactivity data of a predetermined radiation corresponding to a preset radioactive element detected by a radioactivity analyzing device, and perform a leakage detection process on the steam generator according to the radioactivity data.
Referring to fig. 5, in one embodiment, the leak detection apparatus 400 of a steam generator of a nuclear power plant further includes: a control module 404 and a decision module 405, wherein:
and a control module 404, configured to execute the step of determining the dynamic energy balance adjustment parameter and subsequent steps when a time difference between two different time points is smaller than or equal to a preset time length.
The determination module 405 is used for determining that the leakage detection mode of the steam generator is a quick detection mode when the nuclear power plant radiation monitoring system is in an unavailable state or when a nuclear power unit corresponding to the steam generator is in a starting state; the nuclear power station radiation monitoring system is used for monitoring the leakage condition of the steam generator.
In one embodiment, the control module 404 is further configured to, when the detection mode of the steam generator is detected to be the tritium specific activity detection mode, perform the step of obtaining a first radioactivity detected by the elemental analysis device on the preset radioactive elements in the water of the loop and the subsequent steps.
According to the leakage detection device of the nuclear power station steam generator, the first radioactivity obtained by detecting the preset radioactive elements in the water of the loop through the acquired element analysis equipment is obtained. After the element analysis equipment detects the preset radioactive elements in the water of the two loops at two different time points respectively, the second radioactivity activity obtained by detection is obtained, so that the leakage rate of the steam generator of the nuclear power station is converted into the leakage rate of the first loop. And determining the water supplement amount in unit time corresponding to the two loops, and supplementing the water loss amount in the two loops through the water supplement amount so as to keep the quality of water in the two loops unchanged. And determining an energy balance dynamic adjustment parameter so that the amount of the liquid in the first loop and the second loop is kept in dynamic balance. And determining a target mass leakage rate corresponding to the steam generator between the first loop and the second loop according to the first activity, the second activity, the dynamic energy balance adjustment parameter and the water supplement amount in unit time. And performing leakage detection processing on the steam generator according to the target mass leakage rate. Therefore, the leakage detection is carried out on the corresponding steam generator through the water in the primary loop and the secondary loop, the leakage detection device is not only suitable for the leakage detection of the steam generator with steam in a normal operation state, but also can be used for the leakage detection of the steam generator in other states or the steam generator which does not generate steam temporarily, and the application range is wide.
For specific limitations of the leak detection apparatus for a nuclear power plant steam generator, reference may be made to the above limitations of the leak detection method for a nuclear power plant steam generator, and details thereof will not be described herein. Each module in the leak detection apparatus for a steam generator of a nuclear power plant may be implemented in whole or in part by software, hardware, and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
In one embodiment, a computer device is provided, which may be the terminal 102 in fig. 1, and its internal structure diagram may be as shown in fig. 6. The computer device includes a processor, a memory, a network interface, a display screen, and an input device connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device comprises a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of an operating system and computer programs in the non-volatile storage medium. The network interface of the computer device is used for communicating with an external terminal through a network connection. The computer program is executed by a processor to implement a method of leak detection of a nuclear power plant steam generator. The display screen of the computer equipment can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer equipment can be a touch layer covered on the display screen, a key, a track ball or a touch pad arranged on the shell of the computer equipment, an external keyboard, a touch pad or a mouse and the like.
Those skilled in the art will appreciate that the architecture shown in fig. 6 is merely a block diagram of some of the structures associated with the disclosed aspects and is not intended to limit the computing devices to which the disclosed aspects apply, as particular computing devices may include more or less components than those shown, or may combine certain components, or have a different arrangement of components.
In one embodiment, a computer arrangement is provided, comprising a memory and a processor, the memory storing a computer program which, when executed by the processor, causes the processor to carry out the steps of the above-mentioned method of leak detection of a nuclear power plant steam generator. Here, the steps of the leak detection method of the steam generator of the nuclear power plant may be the steps of the leak detection method of the steam generator of the nuclear power plant of each of the above embodiments.
In one embodiment, a computer readable storage medium is provided, storing a computer program which, when executed by a processor, causes the processor to perform the steps of the above-described method of leak detection of a nuclear power plant steam generator. Here, the steps of the leak detection method of the steam generator of the nuclear power plant may be the steps of the leak detection method of the steam generator of the nuclear power plant of each of the above embodiments.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in the embodiments provided herein may include non-volatile and/or volatile memory, among others. Non-volatile memory can include read-only memory (ROM), Programmable ROM (PROM), Electrically Programmable ROM (EPROM), Electrically Erasable Programmable ROM (EEPROM), or flash memory. Volatile memory can include Random Access Memory (RAM) or external cache memory. By way of illustration and not limitation, RAM is available in a variety of forms such as Static RAM (SRAM), Dynamic RAM (DRAM), Synchronous DRAM (SDRAM), Double Data Rate SDRAM (DDRSDRAM), Enhanced SDRAM (ESDRAM), Synchronous Link DRAM (SLDRAM), Rambus Direct RAM (RDRAM), direct bus dynamic RAM (DRDRAM), and memory bus dynamic RAM (RDRAM).
The technical features of the above embodiments can be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the above embodiments are not described, but should be considered as the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present application, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the concept of the present application, which falls within the scope of protection of the present application. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A method of leak detection in a steam generator of a nuclear power plant, the method comprising:
acquiring a first radioactivity obtained by detecting a preset radioactive element in water of a loop by an element analysis device;
after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
determining the water supplement amount in unit time corresponding to the two loops;
determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and performing leakage detection processing on the steam generator according to the target mass leakage rate.
2. The method of claim 1, wherein the two different time points comprise a preceding time point and a following time point; the second radioactivity comprises a preceding second radioactivity corresponding to the preceding point in time and a following second reflected radioactivity corresponding to the following point in time; the method further comprises the following steps:
when the time difference between the two different time points is less than or equal to a preset time length, executing the step of determining the dynamic energy balance adjustment parameter and the subsequent steps;
and when the time difference between the two different time points is greater than a preset time length, determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second later reflected radioactivity and the water supplement amount in unit time.
3. The method of claim 2, wherein determining the energy balance dynamic adjustment parameter comprises:
determining the mass of water in the secondary loop;
and determining an energy balance dynamic adjusting parameter according to the mass of the water, the water replenishing amount in the unit time and the time difference between the two different time points.
4. The method according to claim 1, wherein the obtaining of the second detected radioactivity after the elemental analysis device detects the predetermined radioactive element in the two-circuit water at two different time points comprises:
when the leakage detection mode of the steam generator is a rapid detection mode, respectively detecting the preset radioactive elements in the first sample at two different time points by the element analysis equipment, and acquiring second detected radioactivity;
and the first sample is obtained by sampling from the water of the two loops according to a first sampling mode corresponding to the rapid detection mode.
5. The method according to claim 4, wherein the obtaining of the second detected radioactivity after the elemental analysis device detects the predetermined radioactive element in the two-circuit water at two different time points, further comprises:
when the leakage detection mode of the steam generator is an accurate detection mode, respectively detecting the preset radioactive elements in the second sample at two different time points by the element analysis equipment, and acquiring second detected radioactivity;
the second sample is obtained by sampling from the water of the second loop according to a second sampling mode corresponding to the accurate detection mode; the preset water taking amount corresponding to the second sampling mode is larger than the preset water taking amount corresponding to the first sampling mode, and the preset analysis time corresponding to the second sampling mode is larger than the preset analysis time corresponding to the first sampling mode.
6. The method of claim 4, further comprising:
when a nuclear power station radiation monitoring system is in an unavailable state or when a nuclear power unit corresponding to the steam generator is in a starting state, judging that a leakage detection mode of the steam generator is a quick detection mode;
the nuclear power station radiation monitoring system is used for monitoring the leakage condition of the steam generator.
7. The method according to any one of claims 1 to 6, wherein the predetermined radioactive element comprises tritium; the method further comprises the following steps:
when the detection mode of the steam generator is monitored to be a tritium specific activity detection mode, executing the step of obtaining a first activity obtained by detecting a preset radioactive element in water in a loop by the element analysis equipment and the subsequent steps;
when the detection mode of the steam generator is monitored to be a ray detection mode, acquiring radioactivity data of a preset ray corresponding to the preset radioactivity element, which is detected by radioactivity analysis equipment, and performing leakage detection processing on the steam generator according to the radioactivity data.
8. A leak detection apparatus for a steam generator of a nuclear power plant, the apparatus comprising:
the system comprises an acquisition module, a detection module and a control module, wherein the acquisition module is used for acquiring first radioactivity obtained by detecting preset radioactive elements in water of a loop by element analysis equipment; after the element analysis equipment respectively detects the preset radioactive elements in the water of the second loop at two different time points, second radioactivity obtained by detection is obtained;
the determining module is used for determining the water supplementing amount in unit time corresponding to the two loops; determining an energy balance dynamic adjustment parameter, and determining a target mass leakage rate corresponding to a steam generator between the primary loop and the secondary loop according to the first radioactivity, the second radioactivity, the energy balance dynamic adjustment parameter and the water supplement amount in unit time; the energy balance dynamic adjusting parameter is used for keeping dynamic conservation between energy leaked in the first loop and energy obtained in the second loop;
and the detection module is used for detecting and processing the leakage of the steam generator according to the target mass leakage rate.
9. A computer device comprising a memory, a processor and a computer program stored on the memory and executable on the processor, characterized in that the steps of the method of any of claims 1 to 7 are implemented by the processor when executing the computer program.
10. A computer-readable storage medium, on which a computer program is stored, which, when being executed by a processor, carries out the steps of the method of any one of claims 1 to 7.
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