A method of monitoring for leaks in a radioactive process system and a monitoring apparatus

Abstract

The application discloses a kind of radioactive process system leakage monitoring methods, according to the dose rate level value of acquisition judges whether leakage occurs;And according to the typical nuclide spectrum analysis data of acquisition inversion leakage source item in the space to be measured, the activity concentration of typical radioactive nuclide in the space to be measured is obtained.The radioactive process system leakage monitoring method of the application strictly monitors leakage situation, so that relevant personnel can respond in time.The application also discloses a kind of radioactive process system leakage monitoring equipment.

Description

TECHNICAL FIELD

[0001] The present application belongs to the technical field of nuclear industry, and particularly relates to a monitoring method and a monitoring device for leakage of a radioactive process system. BACKGROUND

[0002] In a radioactive-related plant of a nuclear power plant, such as a nuclear island plant, if a rupture accident or a leakage phenomenon occurs in radioactive equipment, pipelines, etc., radioactive liquid may exist on the ground in the nuclear island plant, and airborne radioactive substances may exist in the atmosphere in the plant. On the one hand, this may affect the system operation and the safe operation of the nuclear power plant. On the other hand, when workers work in the nuclear island plant, they may inhale the airborne radioactive substances, causing inhalation internal exposure. Meanwhile, part of the radioactive gas as airborne radioactive effluent is discharged from the nuclear island to the environment, which may cause environmental public radiation dose.

[0003] Therefore, in order to ensure the safe operation of the nuclear power plant and the radiation safety of workers and the public, it is necessary to strictly monitor or diagnose the above-mentioned situations so as to timely control and handle the relevant consequences.

[0004] At present, the monitoring method either collects the leaked radioactive liquid by using a pit arranged in the room, which is meaningless when the leakage amount is small or the leakage only exists in a gaseous state, or obtains the leakage by using a room ventilation pipeline, which is not sensitive and cannot accurately determine the leakage position in the first time, which is not conducive to the control of radioactive risks. SUMMARY

[0005] The present application provides a monitoring method for leakage of a radioactive process system, which can strictly monitor the leakage situation and enable relevant personnel to respond in time, and also provides a monitoring device for leakage of a radioactive process system.

[0006] The monitoring method for leakage of a radioactive process system provided by the present application comprises the following steps:

[0007] Obtaining a dose rate level value in a to-be-measured space;

[0008] Determining whether leakage occurs according to the obtained dose rate level value;

[0009] After determining that leakage occurs, obtaining typical nuclide spectrum analysis data in the to-be-measured space, and inversely calculating a leakage source term in the to-be-measured space according to the obtained typical nuclide spectrum analysis data to obtain an activity concentration of a typical radioactive nuclide in the to-be-measured space.

[0010] Preferably, the specific steps of determining whether leakage occurs according to the obtained dose rate level value comprise:

[0011] The obtained dose rate level value is compared with the predetermined threshold value, and when the comparison result is that the dose rate level value exceeds the predetermined threshold value range, it is determined that leakage occurs, otherwise, it is determined that no leakage occurs.

[0012] Preferably, the dose rate level value includes a first dose rate level value and a second dose rate level value, the first dose rate level value is a dose rate level value at the top of the space to be measured, and the second dose rate level value is a dose rate level value at the bottom of the space to be measured, and determining whether leakage occurs further includes the following steps:

[0013] When the first dose rate level value and / or the second dose rate level value exceeds the predetermined threshold value range, the first dose rate level value and the second dose rate level value are compared:

[0014] A: When the difference between the first dose rate level value and the second dose rate level value is less than or equal to a set value, it is determined that the leakage in the space to be measured is mostly in gaseous form;

[0015] B: When the second dose rate level value is greater than the first dose rate level value, and the difference between them is greater than the set value, it is determined that the gaseous leakage source in the space to be measured is less than the liquid leakage source.

[0016] Preferably, the typical nuclide spectrum analysis data includes first analysis data A1 and second analysis data A2, the first analysis data A1 is typical nuclide spectrum analysis data at the top of the space to be measured, and the second analysis data A2 is typical nuclide spectrum analysis data at the bottom of the space to be measured, and the activity concentration of the typical radionuclide in the space to be measured is obtained according to the typical nuclide spectrum analysis data and is calculated by the following formula:

[0017] When the difference between the first dose rate level value and the second dose rate level value is less than or equal to a set value:

[0018] A0=A1=A2

[0019] At=A0*Vg;

[0020] When the second dose rate level value is greater than the first dose rate level value, and the difference between them is greater than the set value:

[0021] A0=A1+(A2*Vl / Vg)

[0022] At=A0*Vg;

[0023] Wherein, A0 is the equivalent radionuclide activity concentration in the space to be measured, At is the total radionuclide activity concentration in the space to be measured, Vl is the volume of the leaked liquid in the space to be measured, and Vg is the volume of the gas space in the space to be measured.

[0024] This invention provides a monitoring device for leaks in a radioactive process system, comprising:

[0025] Acquisition component, used to acquire dose rate level values ​​within the space to be measured;

[0026] A determination component, connected to the acquisition component, is used to determine whether a leak has occurred based on the acquired dose rate level value;

[0027] An analysis component, connected to the judgment component, is used to acquire typical nuclide spectrum analysis data in the space to be tested after the judgment component determines that a leak has occurred, and to invert the leakage source term in the space to be tested based on the acquired typical nuclide spectrum analysis data, so as to obtain the activity concentration of typical radionuclides in the space to be tested.

[0028] Preferably, the acquisition component includes an outlet pipe and a dose rate monitoring instrument for acquiring the dose rate level value in the space to be tested. One end of the outlet pipe is open and passes through a through hole provided on the outer wall of the space to be tested. The other end of the outlet pipe is closed and placed outside the space to be tested together with the dose rate monitoring instrument.

[0029] Preferably, the outlet pipe is a bend arranged in an L-shape, with one section of the outlet pipe extending horizontally into the space to be measured, and the other section arranged vertically outside the space to be measured. The dose rate monitoring instrument is located at the vertical section of the outlet pipe.

[0030] Preferably, the acquisition components are provided in multiple sets. In at least one set of acquisition components, the opening of the lead-out pipe is located at the bottom of the space to be measured; in at least another set of acquisition components, the opening of the lead-out pipe is located at the top of the space to be measured.

[0031] Preferably, the analysis component includes a gamma spectrometer for acquiring typical nuclide spectrum analysis data within the space to be tested, and the gamma spectrometer is located at the pipe section where the outlet pipe extends out of the space to be tested.

[0032] Preferably, the analysis component further includes an inversion module, which is communicatively connected to the gamma spectrometer. The inversion module receives typical nuclide spectrum analysis data acquired by the gamma spectrometer and obtains the activity concentration of typical radionuclides based on the typical nuclide spectrum analysis data.

[0033] The method for monitoring leaks in a radioactive process system according to this invention determines in real time whether a leak has occurred in the monitored space based on the acquired dose rate level. This allows for an immediate response upon the occurrence of a leak, timely notification of personnel, and avoidance of delays in handling the situation. More importantly, once a leak is determined, the monitoring method of this invention inverts the leak source term within the monitored space based on real-time typical nuclide spectrum analysis data, obtaining the activity concentration of typical radionuclides within the monitored space. This provides a more detailed leak scenario, further assessing the leak situation in the process system and providing reference conditions for subsequent handling by nuclear power plant operation and maintenance personnel. This enables personnel to take correct and effective measures based on various leak scenarios, and to promptly control and handle related consequences.

[0034] The monitoring device of this invention includes an acquisition component, a judgment component, and an analysis component. It can determine in real time whether a leak has occurred in the space under test based on the acquired dose rate level value. Furthermore, it can invert the leakage source term within the space under test based on real-time typical radionuclide spectrum analysis data to obtain the activity concentration of typical radionuclides within the space under test. Therefore, it can achieve timely, accurate, and effective monitoring, providing important reference data for personnel performing subsequent processing. Attached Figure Description

[0035] Figure 1 This is a schematic diagram of the layout of the monitoring equipment for leakage in the radioactive process system in Embodiment 2 of the present invention.

[0036] In the diagram: 1. Outlet pipe; 2. Dose rate monitoring instrument; 3. Space to be tested; 31. Radioactive pipe; 32. Container; 33. Thermometer; 34. Pressure gauge; 35. Valve; 4. Gamma spectrometer. Detailed Implementation

[0037] The technical solutions of the invention will now be clearly and completely described with reference to the accompanying drawings. Obviously, the described embodiments are only a part of the embodiments of the invention, not all of them. All other embodiments obtained by those skilled in the art based on the embodiments of the invention without creative effort are within the scope of the invention.

[0038] In the description of this invention, it should be noted that the terms "upper" and "lower" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are only for the convenience and simplification of the description and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0039] In the description of this invention, the terms "first," "second," and "third" are used for descriptive purposes only and should not be construed as indicating or implying relative importance.

[0040] In the description of this invention, it should be noted that, unless otherwise explicitly specified and limited, the terms "connection," "setting," "installation," "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a direct connection or an indirect connection through an intermediate medium; and they can refer to the internal communication between two components. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.

[0041] Example 1

[0042] The method for monitoring leakage in a radioactive process system according to the present invention includes the following steps:

[0043] Obtain the dose rate level value within the test space 3;

[0044] Determine whether a leak has occurred based on the obtained dose rate level values;

[0045] In this embodiment, the dose rate level value is obtained in real time, so a response can be made immediately when a leak occurs, and staff can be notified in a timely manner to avoid delaying the handling time.

[0046] After determining that a leak has occurred, typical nuclide spectrum analysis data are obtained in the space to be tested 3, and the leakage source term in the space to be tested 3 is inverted based on the obtained typical nuclide spectrum analysis data to obtain the activity concentration of typical radionuclides in the space to be tested 3.

[0047] This provides more detailed information about the leak, allowing for a more refined assessment of the leak situation in the process system. It also provides reference information for nuclear power plant maintenance personnel to handle the situation later, enabling them to respond correctly and effectively based on various leak scenarios and to control and manage the related consequences in a timely manner.

[0048] In this embodiment, the obtained dose rate level values ​​include at least the dose rate level values ​​at the top and bottom of the space to be tested 3, that is, the dose rate level values ​​include a first dose rate level value and a second dose rate level value, wherein the first dose rate level value is the dose rate level value at the top of the space to be tested 3, and the second dose rate level value is the dose rate level value at the bottom of the space to be tested 3.

[0049] The specific steps for determining whether a leak has occurred based on the obtained dose rate level include:

[0050] The acquired dose rate level value is compared with a predetermined threshold. If the comparison result shows that the dose rate level value exceeds the predetermined threshold range, a leak is determined to have occurred; otherwise, no leak is determined to have occurred.

[0051] Since multiple dose rate level values ​​are obtained, a leak is determined to have occurred when either the first dose rate level value or the second dose rate level value exceeds a predetermined threshold range, and no leak is determined to have occurred only when both the first dose rate level value and the second dose rate level value are within the predetermined threshold range.

[0052] In this embodiment, the predetermined threshold is selected based on the normal value, which is a preset value. There are different setting schemes depending on the size of the space to be tested 3, the leakage standard, etc., and it is set by the staff. Let the normal value be M, then the range of the predetermined threshold is (M, M+10%M).

[0053] In this embodiment, determining whether a leak has occurred also includes the following steps:

[0054] When the first dose rate level value and / or the second dose rate level value (i.e., at least one of them) exceed the predetermined threshold range, the first dose rate level value and the second dose rate level value are compared:

[0055] A: When the difference between the first dose rate level value and the second dose rate level value is less than the set value, it proves that only gaseous leakage has occurred or the gaseous leakage source is much larger than the liquid leakage source. Therefore, it is determined that most of the leakage in the space to be tested 3 exists in gaseous form.

[0056] B: When the value of the second dose rate level is greater than the value of the first dose rate level, and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be tested 3 is smaller than the liquid leakage source.

[0057] Under normal leakage conditions, the second dose rate level will not be lower than the first dose rate level. If this happens, it may indicate that the instrument has malfunctioned.

[0058] In this embodiment, the set value is 10% of the first dose rate level value. For example, if the first dose rate level value is N, then when the second dose rate level value is not greater than 110%N, it is case A above, and otherwise it is case B above.

[0059] In this embodiment, the typical nuclide spectrum analysis data includes first analysis data A1 and second analysis data A2. The first analysis data A1 is the typical nuclide spectrum analysis data at the top of the space to be tested 3, and the second analysis data A2 is the typical nuclide spectrum analysis data at the bottom of the space to be tested 3. Based on the above typical nuclide spectrum analysis data, the activity concentration of typical radionuclides in the space to be tested 3 is specifically calculated using the following formula:

[0060] When the difference between the first dose rate level value and the second dose rate level value is less than or equal to the set value:

[0061] A0 = A1 = A2

[0062] At = A0 * Vg;

[0063] When the second dose rate level is greater than the first dose rate level, and the difference between the two is greater than a set value:

[0064] A0 = A1 + (A2 * Vl / Vg)

[0065] At = A0 * Vg;

[0066] Wherein, A0 is the equivalent radionuclide activity concentration in the space to be tested 3, At is the total radionuclide activity concentration in the space to be tested 3, Vl is the volume of leaked liquid in the space to be tested (which can be automatically determined by image recognition, gravity sensing and other equipment, and its principle and specific structure are the same as conventional equipment on the market, and will not be described in detail here), and Vg is the volume of gas space in the space to be tested.

[0067] The method for monitoring leakage in the radioactive process system in this embodiment, when combined with monitoring equipment, can be further detailed as follows:

[0068] S1: The dose rate monitoring instrument 2 acquires the dose rate level value in the lead-out pipe 1 and sends it to the judgment component;

[0069] S2: The judgment component compares each dose rate level value (i.e., both the first dose rate level value and the second dose rate level value) with a predetermined threshold. When each dose rate level value is within the predetermined threshold range, it returns to step S1. When at least one dose rate level value exceeds the predetermined threshold range, it outputs an abnormal signal and executes step S3.

[0070] S3: The judgment component compares the first dose rate level value and the second dose rate level value, and executes the following instructions based on the comparison result:

[0071] A: When the difference between the first dose rate level value and the second dose rate level value is less than the set value, it is determined that most of the leakage in the space to be tested 3 exists in gaseous form, and a signal is output that most of the leakage exists in gaseous form.

[0072] B: When the second dose rate level value is greater than the first dose rate level value, and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be measured 3 is less than the liquid leakage source, and a signal that the gaseous leakage source is less than the liquid leakage source is output.

[0073] S4: The gamma spectrometer 4 obtains typical nuclide spectrum analysis data of the radiation source term from the extraction pipe 1. The inversion module receives the dose rate measurement value of the radiation source term and performs inversion on the leakage source term in the room. The activity concentration of typical radionuclides in the room (including the equivalent radionuclide activity concentration A0 and the total radionuclide activity concentration At) is obtained through the following calculations:

[0074] When the difference between the first dose rate level value and the second dose rate level value is less than or equal to the set value:

[0075] A0 = A1 = A2

[0076] At = A0 * Vg;

[0077] When the second dose rate level is greater than the first dose rate level, and the difference between the two is greater than a set value:

[0078] A0 = A1 + (A2 * Vl / Vg)

[0079] At = A0 * Vg.

[0080] The monitoring method of this invention can quickly and accurately obtain detailed radiation source terms within the test space 3 where the radioactive process system is located, the distribution of radiation source terms in the gas space and liquid phase, and the activity concentration of typical radionuclides, thereby obtaining accurate leakage information of the process system.

[0081] Example 2

[0082] like Figure 1 As shown, the radioactive process system leakage monitoring device of the present invention includes:

[0083] Acquisition component, used to acquire dose rate level values ​​within the test space 3;

[0084] The judgment component, connected to the acquisition component, is used to determine whether a leak has occurred based on the acquired dose rate level value.

[0085] The analysis component, connected to the judgment component, is used to acquire typical nuclide spectrum analysis data in the test space 3 after the judgment component determines that a leak has occurred, and to invert the leakage source term in the test space 3 based on the acquired typical nuclide spectrum analysis data, so as to obtain the activity concentration of typical radionuclides in the test space 3.

[0086] The acquisition components include an outlet pipe 1 and a dose rate monitoring instrument 2 for acquiring dose rate level values ​​within the test space 3. The analysis components include a gamma spectrometer 4 for acquiring typical radionuclide spectrum analysis data within the test space 3. One end of the outlet pipe 1 is open and passes through a through-hole in the outer wall of the test space 3. The other end of the outlet pipe 1 is closed and placed outside the test space 3 along with the dose rate monitoring instrument 2. The gamma spectrometer 4 is also located at the section of the outlet pipe 1 that extends outside the test space 3.

[0087] Current radioactive leak monitoring equipment needs to be installed within the space to be tested (space 3), which occupies internal space. However, space 3 typically houses many devices, such as... Figure 1As shown, there are radioactive pipes 31, containers 32, thermometers 33, pressure gauges 34, and valves 35, etc. The additional monitoring equipment would affect the planning of other equipment within the space, and personnel would need to enter the space to be tested 3 to set up and adjust the monitoring equipment, posing certain safety risks.

[0088] For the monitoring equipment for leaks in radioactive process systems disclosed in this invention, please refer to [link / reference needed]. Figure 1 Pipe 1 extends through the space to be tested 3, and by utilizing the penetrating irradiation of the radiation source in the space to be tested 3, the dose rate monitoring instrument 2 and the gamma spectrometer 4 can also achieve radioactive leakage monitoring outside the space to be tested 3.

[0089] Since the lead-out pipe 1 can be directly installed at the existing through-hole in the space to be tested 3, or simply installed by opening a hole, and its main measurement is located on the outside of the space, it does not occupy internal space and therefore will not affect the layout of the equipment inside the space to be tested 3. Furthermore, personnel can monitor, set up, and observe the dose rate monitoring instrument 2 and the gamma spectrometer 4 from outside the space to be tested 3, without needing to enter the space to be tested 3 to operate them, eliminating any risk of exposure and greatly improving the safety of the monitoring process.

[0090] Furthermore, precisely because of this, this monitoring equipment can be used in high-radiation areas and other similar conditions, demonstrating good environmental adaptability. In addition, the overall structure of the monitoring equipment is simple and inexpensive, and it can be disassembled, spliced, and assembled according to various applications, making maintenance convenient.

[0091] In this embodiment, the outlet pipe 1 is a bend pipe arranged in an L-shape. One section of the outlet pipe 1 is inserted into the space to be measured 3 in a horizontal direction, and the other section is arranged outside the space to be measured 3 in a vertical direction. The dose rate monitoring instrument 2 and the gamma spectrometer 4 are both arranged at the vertical section of the outlet pipe 1.

[0092] In this embodiment, the acquisition components are provided in two groups. In one group of acquisition components, the opening of the outlet pipe 1 is set at the bottom of the space to be measured 3 and as close as possible to the ground of the space to be measured 3, or an existing through pipe close to the ground is used as the outlet pipe 1. It is best to allow the liquid that leaks to the ground to enter the outlet pipe. The dose rate monitoring instrument 2 of this group of acquisition components is set to acquire the second dose rate level value.

[0093] In another set of acquisition components, the opening of the lead-out pipe 1 is set at the top of the space to be measured 3, or an existing through pipe near the top of the space to be measured 3 is used as the lead-out pipe 1, and the dose rate monitoring instrument 2 of this set of acquisition components is set to acquire the first dose rate level value.

[0094] The two sets of acquisition components should be placed away from the pipes (or existing pipes) in the space to be tested 3, that is, away from the radioactive pipe 31. They should be positioned directly inside the space to be tested 3.

[0095] Each of the two acquisition units is equipped with a gamma spectrometer 4. Both the dose rate monitoring instrument 2 and the gamma spectrometer 4 of the two acquisition units can perform numerical monitoring within the space under test 3 using penetrating irradiation from the radiation source. A sudden and significant change in the reading of the dose rate monitoring instrument 2 indicates a rupture in equipment or pipes within the room.

[0096] The purpose of setting up two sets of acquisition components, one at the top and one at the bottom, is to have the top acquisition component monitor the dose rate level in the top region of the test space 3, and the bottom acquisition component monitor the dose rate level in the bottom region of the test space 3. The readings from the two sets can be compared. If the readings from the two dose rate monitoring instruments 2 are close or not significantly different, it indicates that the leaked process liquid exists mainly in gaseous form within the test space 3; if the difference is large, it indicates that the leaked process liquid exists mainly in liquid or gaseous form within the test space 3 (depending on the relative size ratio). By comparing the readings, the state of the leak can be further determined, providing important reference information for personnel.

[0097] The monitoring device provided by the present invention has a judgment component that receives dose rate level values ​​within the test space 3 acquired by each acquisition component, compares each dose rate level value with a predetermined threshold, and issues an abnormal signal when any dose rate level value exceeds the predetermined threshold range.

[0098] To provide more accurate information and more detailed instructions to staff, when the dose rate level of a component exceeds a predetermined threshold range, the dose rate levels are compared. This means that the internal leakage situation is determined by referring to each value, and the following instructions are executed based on the comparison results:

[0099] A: When the difference between the first dose rate level value and the second dose rate level value is less than the set value, it is determined that most of the leakage in the space to be tested 3 exists in gaseous form, and a signal is output that most of the leakage exists in gaseous form.

[0100] B: When the second dose rate level value is greater than the first dose rate level value, and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be measured 3 is less than the liquid leakage source, and a signal that the gaseous leakage source is less than the liquid leakage source is output.

[0101] In this embodiment, the predetermined threshold and the set value are preset and can be adjusted according to the monitoring situation. Specifically, the predetermined threshold is selected based on the normal value, which is a preset value. There are different setting schemes according to the size of the space to be tested 3, the leakage standard, etc., and it is set by the staff. If the normal value is M, then the range of the predetermined threshold is (M, M+10%M).

[0102] In this embodiment, the set value is 10% of the first dose rate level value. For example, if the first dose rate level value is N, then when the second dose rate level value is not greater than 110%N, it is case A above, and otherwise it is case B above.

[0103] Abnormal signals, as well as the aforementioned signals, can be one or more combinations of vibration, sound, flashing lights, text messages, etc. Monitoring equipment can be additionally equipped with buzzers, indicator lights, and mobile or fixed information receivers to assist in receiving abnormal signals; these details will not be elaborated upon here. The judgment component itself can be located on a terminal or in the cloud. Its comparison and signal transmission functions are those that can be achieved by conventional modules currently on the market; therefore, its specific structure and principles will not be detailed.

[0104] In this embodiment, the analysis component also includes an inversion module, which is communicatively connected to the gamma spectrometer 4. The inversion module receives typical nuclide spectrum analysis data acquired by the gamma spectrometer 4 and obtains the activity concentration of typical radionuclides based on the typical nuclide spectrum analysis data.

[0105] More specifically, gamma spectrometer 4 obtains typical nuclide spectrum analysis data for the outlet pipe 1. This typical nuclide spectrum analysis data includes first analysis data A1 and second analysis data A2. First analysis data A1 is the typical nuclide spectrum analysis data from the top of the space to be tested 3, i.e., the data obtained by the gamma spectrometer at the top; second analysis data A2 is the typical nuclide spectrum analysis data from the bottom of the space to be tested 3, i.e., the data obtained by the gamma spectrometer at the bottom. The inversion module receives this data and inverts the leakage source term within the room using the following formula to obtain the activity concentration of typical radionuclides within the room:

[0106] When the difference between the first dose rate level value and the second dose rate level value is less than or equal to the set value:

[0107] A0 = A1 = A2

[0108] At = A0 * Vg;

[0109] When the second dose rate level is greater than the first dose rate level, and the difference between the two is greater than a set value:

[0110] A0 = A1 + (A2 * Vl / Vg)

[0111] At = A0 * Vg;

[0112] Where A0 represents the equivalent radionuclide activity concentration in space 3 under test, At represents the total radionuclide activity concentration in space 3 under test, Vl represents the volume of the leaked liquid in space 3 under test, and Vg represents the volume of the gas space in space 3 under test. This activity concentration information, including the equivalent radionuclide activity concentration and the total radionuclide activity concentration, provides personnel with more specific and reliable information about the leak, enabling them to develop appropriate handling plans in a timely manner and avoid delays in handling the situation.

[0113] It is understood that the above embodiments are merely exemplary implementations used to illustrate the principles of the present invention, and the present invention is not limited thereto. For those skilled in the art, various modifications and improvements can be made without departing from the spirit and essence of the present invention, and these modifications and improvements are also considered to be within the scope of protection of the present invention.

Claims

1. A method for monitoring leaks in a radioactive process system, characterized in that, Includes the following steps: Obtain the dose rate level value within the space to be tested (3); The dose rate level values ​​include a first dose rate level value and a second dose rate level value. The first dose rate level value is the dose rate level value at the top of the space to be measured (3), and the second dose rate level value is the dose rate level value at the bottom of the space to be measured (3). Determine whether a leak has occurred based on the obtained dose rate level values; After determining that a leak has occurred, typical nuclide spectrum analysis data in the space to be tested (3) are obtained, and the leakage source term in the space to be tested (3) is inverted based on the obtained typical nuclide spectrum analysis data to obtain the activity concentration of typical radionuclides in the space to be tested (3). Specifically, the typical nuclide spectrum analysis data includes first analysis data A1 and second analysis data A2. The first analysis data A1 is the typical nuclide spectrum analysis data at the top of the space to be tested (3), and the second analysis data A2 is the typical nuclide spectrum analysis data at the bottom of the space to be tested (3). The activity concentrations of typical radionuclides within the target space (3) obtained from the typical nuclide spectrum analysis data are specifically calculated using the following formula: When the difference between the first dose rate level and the second dose rate level is less than or equal to the set value, it is determined that most of the leakage in the space to be measured (3) exists in gaseous form. A0=A1=A2 At = A0 * Vg; When the second dose rate level is greater than the first dose rate level and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be measured (3) is smaller than the liquid leakage source. A0 = A1 + (A2 * Vl / Vg) At = A0 * Vg; Where A0 is the equivalent radionuclide activity concentration in the space to be tested (3), At is the total radionuclide activity concentration in the space to be tested (3), Vl is the volume of the leaked liquid in the space to be tested (3), and Vg is the volume of the gas space in the space to be tested.

2. The method for monitoring leakage in a radioactive process system according to claim 1, characterized in that, The specific steps for determining whether a leak has occurred based on the obtained dose rate level include: The acquired dose rate level value is compared with a predetermined threshold. If the comparison result shows that the dose rate level value exceeds the predetermined threshold range, a leak is determined to have occurred; otherwise, no leak is determined to have occurred.

3. The method for monitoring leakage in a radioactive process system according to claim 2, characterized in that, Determining whether a leak has occurred also includes the following steps: When the first dose rate level value and / or the second dose rate level value exceed the predetermined threshold range, the first dose rate level value and the second dose rate level value are compared: A: When the difference between the first dose rate level value and the second dose rate level value is less than or equal to the set value, it is determined that most of the leakage in the space to be tested (3) exists in gaseous form; B: When the value of the second dose rate level is greater than the value of the first dose rate level, and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be tested (3) is smaller than the liquid leakage source.

4. A monitoring device for leaks in a radioactive process system, characterized in that, include: Acquisition component, used to acquire dose rate level values ​​within the space to be tested (3); The dose rate level values ​​include a first dose rate level value and a second dose rate level value. The first dose rate level value is the dose rate level value at the top of the space to be measured (3), and the second dose rate level value is the dose rate level value at the bottom of the space to be measured (3). A judgment component, connected to the acquisition component, is used to determine whether a leak has occurred based on the acquired dose rate level value; The analysis component, connected to the judgment component, is used to obtain typical nuclide spectrum analysis data in the space to be tested (3) after the judgment component determines that a leak has occurred, and to invert the leakage source term in the space to be tested (3) based on the obtained typical nuclide spectrum analysis data, so as to obtain the activity concentration of typical radionuclides in the space to be tested (3). The typical nuclide spectrum analysis data includes first analysis data A1 and second analysis data A2. The first analysis data A1 is the typical nuclide spectrum analysis data at the top of the space to be tested (3), and the second analysis data A2 is the typical nuclide spectrum analysis data at the bottom of the space to be tested (3). The activity concentrations of typical radionuclides within the target space (3) obtained from the typical nuclide spectrum analysis data are specifically calculated using the following formula: When the difference between the first dose rate level and the second dose rate level is less than or equal to the set value, it is determined that most of the leakage in the space to be measured (3) exists in gaseous form. A0=A1=A2 At = A0 * Vg; When the second dose rate level is greater than the first dose rate level and the difference between the two is greater than the set value, it is determined that the gaseous leakage source in the space to be measured (3) is smaller than the liquid leakage source. A0 = A1 + (A2 * Vl / Vg) At = A0 * Vg; Where A0 is the equivalent radionuclide activity concentration in the space to be tested (3), At is the total radionuclide activity concentration in the space to be tested (3), Vl is the volume of the leaked liquid in the space to be tested (3), and Vg is the volume of the gas space in the space to be tested.

5. The monitoring device for leakage in a radioactive process system according to claim 4, characterized in that: The acquisition components include an outlet pipe (1) and a dose rate monitoring instrument (2) for acquiring dose rate level values ​​within the space to be measured (3). One end of the outlet pipe (1) is open and passes through the through hole set on the outer wall of the space to be tested (3) into the space to be tested (3). The other end of the outlet pipe (1) is closed and placed outside the space to be tested (3) together with the dose rate monitoring instrument (2).

6. The monitoring device for leakage in a radioactive process system according to claim 5, characterized in that: The outlet pipe (1) is a bend pipe arranged in an L-shape. One section of the outlet pipe (1) is inserted into the space to be measured (3) in a horizontal direction, and the other section is arranged outside the space to be measured (3) in a vertical direction. The dose rate monitoring instrument (2) is set at the vertical section of the outlet pipe (1).

7. The monitoring device for leakage in a radioactive process system according to claim 5, characterized in that: The acquisition components are provided in multiple groups, and in at least one acquisition component, the opening of the lead-out pipe (1) is set at the bottom of the space to be measured (3); In at least one other set of acquisition components, the opening of the lead-out pipe (1) is located at the top of the space to be measured (3).

8. The monitoring device for leakage in a radioactive process system according to claim 5, characterized in that: The analysis component includes a gamma spectrometer (4) for acquiring typical nuclide spectrum analysis data within the space to be tested (3), the gamma spectrometer (4) being located at the pipe section where the outlet pipe (1) extends out of the space to be tested (3).

9. The monitoring device for leakage in a radioactive process system according to claim 8, characterized in that: The analysis components also include an inversion module, which is communicatively connected to the gamma spectrometer (4). The inversion module receives typical nuclide spectrum analysis data acquired by the gamma spectrometer (4) and obtains the activity concentration of typical radionuclides in the space to be tested (3) based on the typical nuclide spectrum analysis data.

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