CN116009051A - Method and equipment for monitoring leakage of radioactive process system - Google Patents
Method and equipment for monitoring leakage of radioactive process system Download PDFInfo
- Publication number
- CN116009051A CN116009051A CN202211548925.0A CN202211548925A CN116009051A CN 116009051 A CN116009051 A CN 116009051A CN 202211548925 A CN202211548925 A CN 202211548925A CN 116009051 A CN116009051 A CN 116009051A
- Authority
- CN
- China
- Prior art keywords
- space
- rate level
- level value
- leakage
- analysis data
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Measurement Of Radiation (AREA)
Abstract
The invention discloses a monitoring method for leakage of a radioactive process system, which judges whether leakage occurs or not according to an obtained dosage rate level value; and inverting the leakage source item in the space to be detected according to the obtained analysis data of the typical radionuclide spectrum to obtain the activity concentration of the typical radionuclide in the space to be detected. The monitoring method for the leakage of the radioactive process system closely monitors the leakage condition, so that related personnel can deal with the leakage condition in time. The invention also discloses a monitoring device for the leakage of the radioactive process system.
Description
Technical Field
The invention belongs to the technical field of nuclear industry, and particularly relates to a monitoring method and monitoring equipment for leakage of a radioactive process system.
Background
The radioactive related plants of the nuclear power plant, such as the nuclear island plant, in which radioactive equipment, pipelines and the like are broken or leak and drip, may cause the conditions of radioactive liquid on the ground in the nuclear island plant, airborne radioactive substances in the atmosphere in the plant and the like. On the one hand, the system operation and the safe operation of the nuclear power plant are influenced; on the other hand, radioactive gas is reserved in the nuclear island factory building, and workers can inhale the airborne radioactive substances when working in the nuclear island factory building, so that inhalation internal irradiation is caused; at the same time, part of the radioactive gas is discharged into the environment from the nuclear island as airborne radioactive effluent, which causes radiation dose to the environment public.
Therefore, to ensure safe operation of the nuclear power plant, and radiation safety of workers and the public, it is necessary to closely monitor or diagnose the above conditions so as to control and process the related results in time.
The current monitoring mode is to collect radioactive leaked liquid by using a pit arranged in a room, and the treatment mode has no meaning when the leakage amount is small or the leakage exists only in a gaseous state; or the leakage is obtained by using a room ventilation pipeline, but the monitoring in the mode is insensitive, and the leakage occurrence position cannot be accurately judged at the first time, so that the control of the radioactivity risk is not facilitated.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a monitoring method for leakage of a radioactive process system aiming at the defects in the prior art, which can closely monitor the leakage situation, so that related personnel can deal with the leakage in time, and also provides monitoring equipment for the leakage of the radioactive process system.
The invention provides a method for monitoring leakage of a radioactive process system, which comprises the following steps:
obtaining a dosage rate level value in a space to be measured;
judging whether leakage occurs or not according to the obtained dosage rate level value;
after the leakage is judged, the analysis data of the typical nuclide spectrum in the space to be detected is obtained, and the leakage source item in the space to be detected is inverted according to the obtained analysis data of the typical nuclide spectrum, so that the activity concentration of the typical radionuclide in the space to be detected is obtained.
Preferably, the specific step of judging whether leakage occurs according to the obtained dosage rate level value comprises the following steps:
comparing the obtained dosage rate level value with a preset threshold value, and judging that leakage occurs when the comparison result is that the dosage rate level value exceeds the preset threshold value range, or judging that leakage does not occur.
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 of a top in the space to be measured, the second dose rate level value is a dose rate level value of a bottom in the space to be measured, and the step of judging whether leakage occurs further includes the following steps:
when the first and/or second dose rate level values are outside of a predetermined threshold range, comparing the first and second dose rate level values:
a: when the difference value between the first dosage rate level value and the second dosage rate level value is smaller than or equal to a set value, judging that most of leakage in the space to be detected exists in a gaseous form;
b: when the second dosage rate level value is larger than the first dosage rate level value and the difference value is larger than the set value, determining that the gaseous leakage source in the space to be detected is smaller than the liquid leakage source.
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 of the top in the space to be measured, the second analysis data A2 is typical nuclide spectrum analysis data of the bottom in 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 by specifically calculating by the following formula:
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:
A0＝A1＝A2
At＝A0*Vg；
when the second dosage rate level value is greater than the first dosage rate level value and the difference is greater than the set value:
A0＝A1+(A2*V l/Vg)
At＝A0*Vg；
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 leakage liquid volume in the space to be measured, and Vg is the gas space volume in the space to be measured.
The invention provides a monitoring device for leakage of a radioactive process system, which comprises:
the acquisition component is used for acquiring a dosage rate level value in the space to be measured;
the judging component is connected with the acquisition component and is used for judging whether leakage occurs according to the acquired dosage rate level value;
the analysis component is connected with the judging component and is used for acquiring typical nuclide spectrum analysis data in the space to be detected after the judging component judges that leakage occurs, and inverting leakage source items in the space to be detected according to the acquired typical nuclide spectrum analysis data so as to obtain the activity concentration of typical radionuclides in the space to be detected.
Preferably, the acquisition component comprises an extraction pipeline and a dose rate monitoring instrument for acquiring a dose rate level value in the space to be measured, one end of the extraction pipeline is opened and penetrates into the space to be measured through a through hole arranged on the outer wall of the space to be measured, and the other end of the extraction pipeline is closed and is arranged outside the space to be measured together with the dose rate monitoring instrument.
Preferably, the extraction pipeline is an elbow arranged along an L-shaped trend, one pipe section of the extraction pipeline penetrates into a space to be detected along a horizontal trend, the other pipe section is arranged outside the space to be detected along a vertical trend, and the dose rate monitoring instrument is arranged at a vertical pipe section of the extraction pipeline.
Preferably, the acquisition components are provided with a plurality of groups, and in at least one group of acquisition components, the opening of the lead-out pipeline is arranged at the bottom of the space to be tested; in addition, in at least one group of acquisition components, the opening of the leading-out pipeline is arranged at the top of the space to be measured.
Preferably, the analysis assembly comprises a gamma spectrometer for acquiring analysis data of typical nuclide spectra in the space to be measured, and the gamma spectrometer is arranged at a pipe section of the lead-out pipeline penetrating out of the space to be measured.
Preferably, the analysis assembly further comprises an inversion module, the inversion module is in communication connection with the gamma spectrometer, and the inversion module receives typical nuclide spectrum analysis data acquired by the gamma spectrometer and obtains the activity concentration of the typical radionuclide according to the typical nuclide spectrum analysis data.
According to the monitoring method for the leakage condition of the radioactive process system, whether the leakage occurs in the space to be detected is judged in real time according to the obtained dosage rate level value, so that the leakage condition can be immediately reacted, workers are timely notified, and delay of treatment time is avoided. More importantly, once the leakage is judged, the monitoring method can invert the leakage source item in the space to be detected according to real-time typical nuclide spectrum analysis data to obtain the activity concentration of typical radionuclides in the space to be detected. The leakage condition of the process system is further judged, reference conditions are provided for the post-treatment of operation and maintenance personnel of the nuclear power plant, and the personnel can make correct and effective coping modes according to various leakage conditions, and timely control and treat related results.
The monitoring equipment comprises an acquisition component, a judging component and an analysis component, can judge whether leakage occurs in the space to be detected in real time according to the acquired dosage rate level value, and can invert leakage source items in the space to be detected according to real-time typical nuclide spectrum analysis data to obtain the activity concentration of typical radionuclides in the space to be detected. Therefore, the monitoring effect can be timely, accurately and effectively achieved, and important reference data is given to workers for subsequent processing.
Drawings
FIG. 1 is a schematic diagram of the arrangement of the monitoring equipment for radioactive process system leaks in example 2 of the present invention.
In the figure: 1. a lead-out pipe; 2. a dose rate monitoring instrument; 3. a space to be measured; 31. a radioactive tube; 32. a container; 33. a thermometer; 34. a pressure gauge; 35. a valve; 4. gamma spectrometer.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that, the terms "upper," "lower," and the like indicate an orientation or a positional relationship based on the orientation or the positional relationship shown in the drawings, and are merely for convenience and simplicity of description, and do not indicate or imply that the apparatus or element in question must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," "third," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention can be understood by those skilled in the art according to the specific circumstances.
Example 1
The method for monitoring the leakage of the radioactive process system comprises the following steps:
acquiring a dosage rate level value in a space 3 to be measured;
judging whether leakage occurs or not according to the obtained dosage rate level value;
in this embodiment, the obtained dosage rate level value is a real-time obtained value, so that the operator can be immediately notified of the immediate response when the leakage occurs, and delay of the processing time is avoided.
After judging that leakage occurs, acquiring typical nuclide spectrum analysis data in the space to be detected 3, and inverting leakage source items in the space to be detected 3 according to the acquired typical nuclide spectrum analysis data to obtain the activity concentration of typical radionuclides in the space to be detected 3.
The leakage situation is obtained in more detail, the leakage situation of the process system is further refined and judged, reference conditions are provided for the post-treatment of operation and maintenance personnel of the nuclear power plant, and the personnel can make correct and effective coping modes according to various leakage situations, and timely control and treat related results.
In this embodiment, the obtained dose rate level values at least include the dose rate level values at the top and bottom in the space to be measured 3, that is, the dose rate level values include a first dose rate level value and a second dose rate level value, where the first dose rate level value is the dose rate level value at the top in the space to be measured 3, and the second dose rate level value is the dose rate level value at the bottom in the space to be measured 3.
The specific steps for judging whether leakage occurs or not according to the obtained dosage rate level value comprise the following steps:
comparing the obtained dosage rate level value with a preset threshold value, and judging that leakage occurs when the comparison result is that the dosage rate level value exceeds the preset threshold value range, or judging that leakage does not occur.
Since the number of the obtained dose rate level values is plural, it is determined that leakage occurs when either one of the first dose rate level value and the second dose rate level value exceeds a predetermined threshold range, and it is determined that no leakage occurs when both the first dose rate level value and the second dose rate level value are within the predetermined threshold range.
In this embodiment, the predetermined threshold is selected based on a normal value, which is a preset value, and is set by a worker according to different setting schemes such as the size of the space 3 to be measured and the leakage standard, and the range of the predetermined threshold is (M, m+10%m) if the normal value is set as M.
In this embodiment, the step of judging whether leakage occurs further includes the steps of:
when the first and/or second dose rate level values (i.e., at least one of the two) are outside of a predetermined threshold range, the first and second dose rate level values are compared:
a: when the difference between the first dosage rate level value and the second dosage rate level value is smaller than the set value, only the gaseous leakage or the gaseous leakage source is proved to be much larger than the liquid leakage source, so that the leakage in the space 3 to be measured is judged to exist in a gaseous form mostly;
b: when the second dosage rate level value is larger than the first dosage rate level value and the difference value is larger than the set value, the gaseous leakage source in the space 3 to be measured is judged to be smaller than the liquid leakage source.
In normal leakage situations, no situation occurs where the second dose rate level value is smaller than the first dose rate level value, which may represent a malfunction of the meter.
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, the second dose rate level value is not greater than 110% N, the case a is the case a, and vice versa, the case B is the case B.
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 typical nuclide spectrum analysis data of the top in the space 3 to be measured, the second analysis data A2 is typical nuclide spectrum analysis data of the bottom in the space 3 to be measured, and the activity concentration of the typical radionuclide in the space 3 to be measured is obtained according to the above typical nuclide spectrum analysis data by the following formula:
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:
A0＝A1＝A2
At＝A0*Vg；
when the second dosage rate level value is greater than the first dosage rate level value and the difference is greater than the set value:
A0＝A1+(A2*Vl/Vg)
At＝A0*Vg；
wherein, A0 is the equivalent radionuclide activity concentration in the space to be measured 3, at is the total radionuclide activity concentration in the space to be measured 3, vl is the leakage liquid volume of the space to be measured (which can be automatically measured by image recognition, gravity sensing and other devices, the principle is consistent with the specific structure of the conventional device on the market, and details are not repeated here), and Vg is the gas space volume of the space to be measured.
The method for monitoring leakage of the radioactive process system in this embodiment, after being combined with the monitoring device, can be further described as the following steps:
s1: the dosage rate monitoring instrument 2 acquires the dosage rate level value in the leading-out pipeline 1 and sends the dosage rate level value to the judging component;
s2: the judging component compares each dosage rate level value (namely, the first dosage rate level value and the second dosage rate level value) with a preset threshold value, returns to the step S1 when each dosage rate level value is within the preset threshold value range, outputs an abnormal signal when at least one dosage rate level value exceeds the preset threshold value range, and executes the step S3;
s3: the judging component compares the first dosage rate level value with the second dosage rate level value, and executes the following instructions according to the comparison result:
a: when the difference value between the first dosage rate level value and the second dosage rate level value is smaller than the set value, judging that most of leakage in the space 3 to be detected exists in a gaseous form, and outputting a signal that most of leakage exists in the gaseous form;
b: when the second dosage rate level value is larger than the first dosage rate level value and the difference value is larger than the set value, judging that the gaseous leakage source in the space 3 to be detected is smaller than the liquid leakage source, and outputting a signal that the gaseous leakage source is smaller than the liquid leakage source.
S4: the gamma spectrometer 4 obtains typical nuclide spectrum analysis data of a radiation source item led out of the pipeline 1, the inversion module receives a radiation source item dose rate measurement value, inverts a leakage source item in a room, and obtains the activity concentration of typical radionuclides in the room (comprising an equivalent radionuclide activity concentration A0 and a total radionuclide activity concentration At) through the following calculation:
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:
A0＝A1＝A2
At＝A0*Vg；
when the second dosage rate level value is greater than the first dosage rate level value and the difference is greater than the set value:
A0＝A1+(A2*Vl/Vg)
At＝A0*Vg。
by the monitoring method, detailed radiation source items in the space 3 to be detected, where the radioactive process system is located, distribution conditions of the radiation source items in the gas space and the liquid phase and activity concentration of typical radionuclides can be rapidly and accurately obtained, and therefore accurate leakage conditions of the process system can be obtained.
Example 2
As shown in fig. 1, the monitoring device for leakage of a radioactive process system of the present invention comprises:
the acquisition component is used for acquiring the dosage rate level value in the space to be measured 3;
the judging component is connected with the acquisition component and is used for judging whether leakage occurs according to the acquired dosage rate level value;
the analysis component is connected with the judging component and is used for acquiring typical nuclide spectrum analysis data in the space to be detected 3 after the judging component judges that leakage occurs, and inverting leakage source items in the space to be detected 3 according to the acquired typical nuclide spectrum analysis data so as to obtain the activity concentration of typical radionuclides in the space to be detected 3.
The acquisition component comprises an extraction pipeline 1 and a dose rate monitoring instrument 2 for acquiring a dose rate level value in a space to be measured 3, and the analysis component comprises a gamma spectrometer 4 for acquiring typical nuclide spectrum analysis data in the space to be measured 3. One end of the leading-out pipeline 1 is opened and penetrates into the space to be measured 3 through a through hole arranged on the outer wall of the space to be measured 3, and the other end of the leading-out pipeline 1 is closed and is arranged outside the space to be measured 3 together with the dosage rate monitoring instrument 2. The gamma spectrometer 4 is also arranged at the pipe section of the lead-out pipe 1 penetrating out of the space 3 to be measured.
The current radioactive leakage monitoring apparatus needs to be disposed in the space 3 to be measured, and needs to occupy an internal space, and many apparatuses are generally disposed in the space 3 to be measured, as shown in fig. 1, such as a radioactive pipe 31, a container 32, a thermometer 33, a pressure gauge 34, a valve 35, and the like. The planning of other equipment in the space can be influenced by the excessive monitoring equipment, and staff also need to enter the space 3 to be monitored, set and adjusted, so that certain safety risks are realized.
Referring to fig. 1, an extraction pipe 1 penetrates through a space 3 to be detected, and radiation source penetrating irradiation in the space 3 to be detected is utilized to enable a dose rate monitor instrument 2 and a gamma spectrometer 4 to realize radioactive leakage monitoring outside the space 3 to be detected.
The leading-out pipeline 1 can be directly arranged at the existing through hole of the space 3 to be measured, or can be directly arranged by punching, and the main measurement of the leading-out pipeline is positioned outside the space, so that the internal space is not occupied, and the layout planning of the internal equipment of the space 3 to be measured is not influenced. And the staff just can monitor setting and observing dose rate monitor instrument 2 and gamma spectrometer 4 outside the space to be measured 3, need not get into the space to be measured 3 in the in-process and operate, do not have the exposure risk, improved the security of monitoring process greatly.
And because of this, the monitoring equipment can be used for working conditions such as high radiation areas, and the like, and has good environmental applicability. In addition, the whole structure of the device for realizing monitoring is simple, the cost is low, the device can be split, spliced and assembled according to various application conditions, and the maintenance is convenient.
In this embodiment, the leading-out pipe 1 is an elbow pipe arranged along an L-shaped trend, one section of the leading-out pipe 1 penetrates into the space to be measured 3 along a horizontal trend, the other section of the leading-out pipe is arranged outside the space to be measured 3 along a vertical trend, and the dose rate monitoring instrument 2 and the gamma spectrometer 4 are both arranged at the vertical section of the leading-out pipe 1.
In this embodiment, two sets of acquisition components are provided, in one set of acquisition components, the opening of the extraction pipe 1 is disposed at the bottom of the space 3 to be measured and is as close to the ground of the space 3 to be measured as possible, or an existing through pipe close to the ground is used as the extraction pipe 1, so that the liquid leaking to the ground can enter the extraction pipe, and the second dosage rate level value is obtained by the dosage rate monitoring instrument 2 of the set of acquisition components.
In another set of acquisition components, the opening of the extraction pipe 1 is arranged at the top of the space to be measured 3, or an existing through pipe close to the top of the space to be measured 3 is used as the extraction pipe 1, and the dosage rate monitoring instrument 2 of the set of acquisition components acquires a first dosage rate level value.
The two sets of acquisition assemblies are arranged at positions which avoid being close to the pipeline (or the existing pipeline) in the space 3 to be measured, namely, avoid being close to the radioactive pipeline 31, and are opposite to the space 3 to be measured.
The two sets of acquisition assemblies are each provided with a gamma spectrometer 4. The dose rate monitoring instrument 2 and the gamma spectrometer 4 of the two groups of acquisition components can monitor the numerical value in the space 3 to be measured by using penetrating irradiation of the radiation source. When a sudden large change in the readings of the dose rate monitoring meter 2 occurs, this indicates that a break in the equipment or tubing in the room has occurred.
The purpose of the two sets of acquisition components is that the top acquisition component monitors the dosage rate level of the top area of the space to be measured 3, and the bottom acquisition component monitors the dosage rate level of the bottom area of the space to be measured 3. The readings between the two groups can be compared, if the measured readings of the two dosage rate monitoring meters 2 are relatively close or have little difference, the leaked process liquid mainly exists in a gaseous form in the space to be detected 3; if the phase difference is large, it means that the leaked process liquid is mainly present in liquid or gaseous form (depending on the relative size ratio) in the space 3 to be measured. The leakage state can be further determined through comparison between the readings, and important reference conditions are provided for staff.
The monitoring equipment provided by the invention has the advantages that the judging component receives the dosage rate level values in the space to be detected 3 acquired by the acquiring components, compares each dosage rate level value with the preset threshold value, and sends out an abnormal signal when any dosage rate level value exceeds the preset threshold value range.
In order to further provide more accurate information, and give more detailed instructions to the staff, the judging component compares the dosage rate level values when the dosage rate level values exceed the preset threshold range, namely, obtains the internal leakage condition by referring to the values, and executes the following instructions according to the comparison result:
a: when the difference value between the first dosage rate level value and the second dosage rate level value is smaller than the set value, judging that most of leakage in the space 3 to be detected exists in a gaseous form, and outputting a signal that most of leakage exists in the gaseous form;
b: when the second dosage rate level value is larger than the first dosage rate level value and the difference value is larger than the set value, judging that the gaseous leakage source in the space 3 to be detected is smaller than the liquid leakage source, and outputting a signal that the gaseous leakage source is smaller than the liquid leakage source.
In this embodiment, the predetermined threshold and the set value are preset and may be adjusted according to the monitoring situation, specifically, the predetermined threshold is selected based on a normal value, the normal value is a preset value, different setting schemes are set by a worker according to the size of the space 3 to be tested, the leakage standard, and the like, and if the normal value is set as M, the range of the predetermined threshold is (M, m+10%m).
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, the second dose rate level value is not greater than 110% N, the case a is the case a, and vice versa, the case B is the case B.
The abnormal signal and the above signals may be one or more of vibration, sound, flash, text information, etc., and the monitoring device may be additionally equipped with a buzzer, an indicator light, a mobile or fixed information receiving terminal, etc. to cooperate to receive the abnormal signal, which is not described herein in detail. The judging component can be arranged at the terminal or the cloud, and the comparison function and the signal sending function realized by the judging component are functions which can be realized by the conventional module in the market at present, so that the specific structure and the principle of the judging component are not repeated.
In this embodiment, the analysis component further includes an inversion module, where the inversion module is in communication connection with the gamma spectrometer 4, and the inversion module receives typical nuclide spectrum analysis data obtained by the gamma spectrometer 4, and obtains an activity concentration of a typical radionuclide according to the typical nuclide spectrum analysis data.
More specifically, the gamma spectrometer 4 obtains typical nuclide spectrum analysis data of the outgoing pipeline 1. The typical nuclide spectrum analysis data comprises first analysis data A1 and second analysis data A2, wherein the first analysis data A1 is typical nuclide spectrum analysis data of the top part in a space 3 to be detected, namely data obtained by a gamma spectrometer of the top part; the second analysis data A2 is typical nuclide spectrum analysis data of the bottom in the space to be detected 3, namely data obtained by a gamma spectrometer of the bottom. The inversion module receives the data and inverts the leakage source term in the room to obtain the activity concentration of the typical radionuclide in the room by the following formula:
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:
A0＝A1＝A2
At＝A0*Vg；
when the second dosage rate level value is greater than the first dosage rate level value and the difference is greater than the set value:
A0＝A1+(A2*Vl/Vg)
At＝A0*Vg；
wherein A0 is the equivalent radionuclide activity concentration in the space to be measured 3, at is the total radionuclide activity concentration in the space to be measured 3, vl is the leakage liquid volume of the space to be measured 3, and Vg is the gas space volume of the space to be measured. The activity concentration information comprises equivalent radionuclide activity concentration and total radionuclide activity concentration, so that more specific and reliable leakage conditions are provided for staff, the staff can timely obtain corresponding treatment schemes, and delay of treatment time is avoided.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (10)
1. A method of monitoring leakage from a radioactive process system, comprising the steps of:
obtaining a dosage rate level value in a space (3) to be measured;
judging whether leakage occurs or not according to the obtained dosage rate level value;
after the occurrence of leakage is judged, typical nuclide spectrum analysis data in the space (3) to be detected are obtained, and leakage source items in the space (3) to be detected are inverted according to the obtained typical nuclide spectrum analysis data so as to obtain the activity concentration of typical radionuclides in the space (3) to be detected.
2. The method of claim 1, wherein the step of determining whether a leak has occurred based on the obtained dose rate level value comprises:
comparing the obtained dosage rate level value with a preset threshold value, and judging that leakage occurs when the comparison result is that the dosage rate level value exceeds the preset threshold value range, or judging that leakage does not occur.
3. The method of monitoring leakage of a radioactive process system according to claim 2, wherein the dose rate level values comprise a first dose rate level value and a second dose rate level value, the first dose rate level value being a dose rate level value at the top in the space (3) under test, the second dose rate level value being a dose rate level value at the bottom in the space (3) under test,
determining whether a leak has occurred further comprises the steps of:
when the first and/or second dose rate level values are outside of a predetermined threshold range, comparing the first and second dose rate level values:
a: when the difference value between the first dosage rate level value and the second dosage rate level value is smaller than or equal to a set value, judging that most of leakage in the space (3) to be detected exists in a gaseous form;
b: when the second dosage rate level value is larger than the first dosage rate level value and the difference value is larger than the set value, the gaseous leakage source in the space (3) to be detected is judged to be smaller than the liquid leakage source.
4. The method for monitoring leakage of a radioactive process system according to claim 3, wherein the typical nuclide spectrum analysis data comprises first analysis data A1 and second analysis data A2, the first analysis data A1 is typical nuclide spectrum analysis data of the top part in the space (3) to be measured, the second analysis data A2 is typical nuclide spectrum analysis data of the bottom part in the space (3) to be measured,
the activity concentration of the typical radionuclide in the space (3) to be detected is obtained according to the analysis data of the typical radionuclide spectrum, and is specifically calculated by the following formula:
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:
A0＝A1＝A2
At＝A0*Vg；
when the second dosage rate level value is greater than the first dosage rate level value and the difference is greater than the set value:
A0＝A1+(A2*Vl/Vg)
At＝A0*Vg；
wherein A0 is the equivalent radionuclide activity concentration in the space (3) to be measured, at is the total radionuclide activity concentration in the space (3) to be measured, vl is the leakage liquid volume of the space (3) to be measured, and Vg is the gas space volume of the space to be measured.
5. A radioactive process system leak monitoring apparatus, comprising:
the acquisition component is used for acquiring a dosage rate level value in the space (3) to be measured;
the judging component is connected with the acquisition component and is used for judging whether leakage occurs according to the acquired dosage rate level value;
the analysis component is connected with the judging component and is used for acquiring typical nuclide spectrum analysis data in the space (3) to be detected after the judging component judges that leakage occurs, and inverting leakage source items in the space (3) to be detected according to the acquired typical nuclide spectrum analysis data so as to obtain the activity concentration of typical radionuclides in the space (3) to be detected.
6. The radioactive process system leak monitoring apparatus of claim 5, wherein: the acquisition component comprises an extraction pipeline (1) and a dose rate monitoring instrument (2) for acquiring the dose rate level value in the space (3) to be measured,
one end of the leading-out pipeline (1) is opened, and penetrates into the space (3) to be tested through a through hole arranged on the outer wall of the space (3) to be tested, and the other end of the leading-out pipeline (1) is closed and is arranged outside the space (3) to be tested together with the dosage rate monitoring instrument (2).
7. The radioactive process system leakage monitoring apparatus of claim 6, wherein: the utility model discloses a dose rate monitoring device, including drawing pipeline (1), dose rate monitoring instrument (2), wherein draw pipeline (1) is the return bend that sets up along L type trend, draw pipeline (1) one section pipeline section to penetrate in the space (3) of awaiting measuring along the horizontal trend, another section pipeline section sets up outside space (3) of awaiting measuring along vertical trend, dose rate monitoring instrument (2) set up in draw pipeline (1) vertical pipeline section department.
8. The radioactive process system leakage monitoring apparatus of claim 6, wherein: the acquisition components are provided with a plurality of groups, and in at least one group of acquisition components, the opening of the lead-out pipeline (1) is arranged at the bottom of the space (3) to be tested;
in addition, in at least one group of acquisition components, the opening of the leading-out pipeline (1) is arranged at the top of the space (3) to be measured.
9. The radioactive process system leakage monitoring apparatus of claim 6, wherein: the analysis assembly comprises a gamma spectrometer (4) for acquiring typical nuclide spectrum analysis data in the space (3) to be tested, and the gamma spectrometer (4) is arranged at a pipe section of the lead-out pipeline (1) penetrating out of the space (3) to be tested.
10. The radioactive process system leakage monitoring apparatus of claim 9, wherein: the analysis assembly further comprises an inversion module which is in communication connection with 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 (3) to be detected according to the typical nuclide spectrum analysis data.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211548925.0A CN116009051A (en) | 2022-12-05 | 2022-12-05 | Method and equipment for monitoring leakage of radioactive process system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211548925.0A CN116009051A (en) | 2022-12-05 | 2022-12-05 | Method and equipment for monitoring leakage of radioactive process system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116009051A true CN116009051A (en) | 2023-04-25 |
Family
ID=86019997
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202211548925.0A Pending CN116009051A (en) | 2022-12-05 | 2022-12-05 | Method and equipment for monitoring leakage of radioactive process system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116009051A (en) |
-
2022
- 2022-12-05 CN CN202211548925.0A patent/CN116009051A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US5297421A (en) | Leak detection system for gas, steam or the like that involves multi-point sampling | |
| US20140042309A1 (en) | In-situ calibration system and method for radiation monitors | |
| CA3029181C (en) | Leakage control system for spent fuel cooling pool | |
| CN105203717A (en) | Inert gas monitor field calibration device and application method thereof | |
| KR101122987B1 (en) | Apparatus for inspecting error rate of watergauge | |
| KR101717943B1 (en) | Airtight Test Apparatus for Nuclear Facility | |
| CN116009051A (en) | Method and equipment for monitoring leakage of radioactive process system | |
| KR101604306B1 (en) | Radioactivity leak monitoring system for radioactivity containment building | |
| JP4875880B2 (en) | The latest HIT skid data collection method | |
| RU91779U1 (en) | GAS GAS MEDIA DETECTION DETECTION DEVICE AND SPECTOMETRIC GAS GAMMA RADIATION MONITOR | |
| KR100765969B1 (en) | Digital radiation monitoring system for auto radionuclide analysis | |
| Hayes et al. | Requirements for Xenon International | |
| KR102450248B1 (en) | System and method of monitoring environmental radioactivities | |
| US20110100095A1 (en) | Passive Glovebox Glove Leak Detector | |
| US20110000282A1 (en) | Passive glovebox glove leak detector | |
| Diana et al. | Industrial internet of things solution for monitoring ammonia and carbon monoxide in industrial staging areas | |
| Price | The Foundation for ASTM D6620, Standard Practice for Asbestos Detection Limit Based on Counts and Its Application as a Study Design Parameter | |
| CN210803731U (en) | Standard liquid source method calibrating device for sampling type liquid effluent monitor | |
| RU223700U1 (en) | Multiphase flow meter | |
| CN210766915U (en) | Foundation pit real-time monitoring system based on HTM (high-speed transmission) hierarchical time memory algorithm | |
| RU2727072C1 (en) | Method for detecting depressurization of process equipment at an early stage by reducing the value of the minimum detectable fluid activity of a radiometric unit (versions) | |
| CN213275976U (en) | Device for rapidly detecting protection equivalent of radiation protection material | |
| JPH05231979A (en) | Leakage sensing system such as gas and vapor, method and apparatus for measuring wind direction and speed | |
| Ha et al. | Digital Radiation Monitoring System for High-functioning Auto Radionuclide Analysis | |
| Slavov et al. | Detection of primary coolant leaks in NPP |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |