A nuclear waste drum measuring device

Abstract

The application discloses a nuclear waste barrel measuring device which can effectively reduce the problem of large deviation of measuring precision caused by non-uniform radioactive substances in the barrel. A plurality of surface dose rate measuring devices are used to measure the surface dose rate values of the waste barrel, so that the surface dose rate distribution of the waste barrel is obtained, accurate data basis is provided for subsequent calculation and measurement route planning, and the radioactive distribution of the waste barrel can be roughly judged. Under the cooperation of the dose rate values and the total weight, the accurate calculation of the attenuation coefficient is completed, and accurate basis is provided for subsequent measurement. The dose rate value vector measured based on the dose rate is used, and the system flexibly changes the opening size of the attenuation device during measurement according to the value, so that the measuring precision is effectively improved, and the dead time increase of the detector caused by high dose is reduced.

Description

Technical Field

[0001] This invention relates to the field of radiation measurement equipment technology, and in particular to a nuclear waste container measurement device that can ensure measurement accuracy even when the radioactive material inside the container is uneven. Background Technology

[0002] With the increasingly widespread application of nuclear energy and nuclear technology in energy, military, industry, and medical fields, nuclear fuel plants, reactors, military facilities, hospitals, and research institutions generate large amounts of radioactive solid waste annually. This radioactive waste is often compressed into waste containers. To handle, transport, and dispose of this radioactive solid waste, it is essential to estimate the content of radionuclides within the waste. However, due to the uneven distribution and significant differences in matrix density of containerized nuclear waste, it is difficult to obtain representative samples for chemical analysis. Currently, both domestically and internationally, the commonly used method is non-destructive analysis (NDA) combining neutron detection technology and X-ray detection technology to perform overall testing of containerized nuclear waste.

[0003] Compared to earlier techniques such as chemistry, mass spectrometry, electrophysiological analysis, and dispersed wavelength X-ray fluorescence analysis, non-destructive detection techniques such as gamma-ray measurement, neutron measurement, X-ray fluorescence K-absorption edge analysis, and calorimetry do not require destructive sampling of radioactive waste, thus controlling detection costs and reducing the risk of radiation and other hazardous substances to personnel and the public. Among these, gamma-ray measurement technology has a wide range of applications and does not require prior determination of the relative proportion of nuclides in the waste, allowing direct determination of the absolute content of nuclides.

[0004] Currently, the general process for non-destructive testing (NDT) waste bin detection devices involves calculating the attenuation coefficient based on the bin's model and weight, adjusting the relative position of the detector and the bin according to a function, and finally performing a comprehensive inspection of the bin to obtain measurement results. The detection efficiency, nuclide distribution, and total activity are then calculated based on these results. While this method can accurately measure waste bins with uniformly distributed media, in reality, the distribution of the filling material within a waste bin is uneven. Therefore, this method can lead to significant measurement biases.

[0005] Therefore, how to provide a measuring device that can effectively reduce the large deviation in measurement accuracy caused by the uneven distribution of radioactive materials inside the container is a technical problem that urgently needs to be solved by those skilled in the art. Summary of the Invention

[0006] In view of the above problems, the present invention provides a nuclear waste container measuring device to overcome or at least partially solve the above problems. It can effectively reduce the problem of large measurement accuracy deviations caused by the uneven distribution of radioactive material within the container.

[0007] This invention provides the following solution:

[0008] A nuclear waste container measuring device, comprising:

[0009] A measuring rotary table, wherein the measuring rotary table is equipped with a weighing device;

[0010] A surface dose rate detection mechanism is disposed on the side of the measuring rotary table;

[0011] An energy spectrum measuring device, wherein the energy spectrum measuring device is connected to a moving drive mechanism; the moving drive mechanism is used to drive the energy spectrum measuring device to move back and forth and up and down.

[0012] The controller is electrically connected to the measuring rotary table, the weighing device, the surface dose rate detection mechanism, the energy spectrum measurement device, and the moving drive mechanism, respectively.

[0013] The controller is used to perform the following operations:

[0014] Receive the total weight of the waste bin to be tested placed on the measuring rotary table, obtained by the weighing device;

[0015] The surface dose rate detection mechanism receives the surface dose rate value of the waste bin to be tested.

[0016] The model of the waste bin to be tested and the corresponding attenuation coefficient are obtained using the total weight and the surface dose rate value through spectral analysis software.

[0017] The measurement path of the energy spectrum measuring device is generated using the attenuation coefficient.

[0018] The mobile drive mechanism is controlled to drive the energy spectrum measuring device to move along the measurement route to perform energy spectrum measurement on the waste bin to be tested and obtain the energy spectrum measurement result, so that the spectrum interpretation software can perform nuclide identification, efficiency calculation and total activity calculation of the waste bin to be tested based on the energy spectrum measurement result.

[0019] Preferably, the measuring rotary table is provided with an alignment mechanism, which is used to align the waste bin to be tested conveyed by the conveying device.

[0020] Preferably, the alignment mechanism includes three laser alignment devices evenly distributed along the circumference of the rotary table.

[0021] Preferably, the surface dose rate detection mechanism includes multiple surface dose rate meters, which are used to detect the surface of multiple parts of the waste bin to be tested.

[0022] Preferably, a plurality of the surface dose rate meters are mounted on the side of the measuring rotary table via a bracket.

[0023] Preferably, the surface dose rate meter comprises five, and the five surface dose rate meters are respectively disposed at the bottom, lower middle, middle, upper middle and top of the support.

[0024] Preferably, the bracket is connected to a rotary drive mechanism, which drives the bracket to carry multiple surface dose rate meters closer to or further away from the waste bin to be tested.

[0025] Preferably, a collimating shield is provided in front of the energy spectrum measuring device, and the controller is also used to control the opening size of the collimating shield according to the dose rate value.

[0026] According to specific embodiments provided by the present invention, the present invention discloses the following technical effects:

[0027] This application provides a nuclear waste container measurement device that effectively reduces the problem of large measurement accuracy deviations caused by the uneven distribution of radioactive material inside the container. Multiple surface dose rate measurements are used to obtain the dose rate distribution on the surface of the waste container, providing accurate data for subsequent calculations and measurement route planning, and also allowing for a preliminary assessment of the radioactive distribution within the waste container. By coordinating the dose rate values ​​and the total weight, the attenuation coefficient is accurately calculated, providing a reliable basis for subsequent measurements. Using a dose rate vector based on the measured dose rate values, the system flexibly adjusts the opening size of the attenuation device during measurement, thereby effectively improving measurement accuracy and reducing the increase in detector dead time caused by high doses.

[0028] Of course, any product implementing this invention does not necessarily need to achieve all of the advantages described above at the same time. Attached Figure Description

[0029] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the embodiments will be briefly described below. Obviously, the drawings described below are merely some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without any creative effort.

[0030] Figure 1 This is a schematic diagram of the structure of a nuclear waste bin measuring device provided in an embodiment of the present invention.

[0031] In the figure: 1. Measuring rotary table; 2. Weighing device; 3. Surface dose rate detection mechanism; 31. Surface dose rate meter; 32. Support; 4. Energy spectrum measurement device; 5. Motion drive mechanism; 6. Controller; 7. Laser alignment device; 8. Collimation shield. Detailed Implementation

[0032] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only a part of the embodiments of the present invention, and not all of them. All other embodiments obtained by those skilled in the art based on the embodiments of the present invention are within the scope of protection of the present invention.

[0033] See Figure 1 This invention provides a nuclear waste container measuring device, such as... Figure 1 As shown, the device may include:

[0034] A measuring rotary table 1, wherein the measuring rotary table 1 is equipped with a weighing device 2;

[0035] A surface dose rate detection mechanism 3 is disposed on the side of the measuring rotary table 1;

[0036] An energy spectrum measuring device 4 is provided, and a moving drive mechanism 5 is connected to the energy spectrum measuring device 4; the moving drive mechanism 5 is used to drive the energy spectrum measuring device 4 to move back and forth and up and down.

[0037] Controller 6 is electrically connected to the measuring rotary table 1, the weighing device 2, the surface dose rate detection mechanism 3, the energy spectrum measurement device 4, and the moving drive mechanism 5, respectively.

[0038] The controller 6 is used to perform the following operations:

[0039] Receive the total weight of the waste bin to be tested, which is placed on the measuring rotary table 1, obtained by the weighing device 2;

[0040] The surface dose rate detection mechanism 3 receives the surface dose rate value of the waste bin to be tested.

[0041] The model of the waste bin to be tested and the corresponding attenuation coefficient are obtained using the total weight and the surface dose rate value through spectral analysis software.

[0042] The measurement path of the energy spectrum measuring device 4 is generated using the attenuation coefficient;

[0043] The mobile drive mechanism 5 is controlled to drive the energy spectrum measuring device 4 to move along the measurement route to perform energy spectrum measurement on the waste bin to be tested and obtain the energy spectrum measurement result, so that the spectrum interpretation software can perform nuclide identification, efficiency calculation and total activity calculation of the waste bin to be tested based on the energy spectrum measurement result.

[0044] The nuclear waste bin measuring device provided in this application embodiment can weigh the waste bin to be tested placed on top of the measuring rotary table 1 using a weighing device 2. The surface dose rate detection mechanism 3 can detect the surface dose rate value of the waste bin. The controller 6 can obtain the model of the waste bin and its corresponding attenuation coefficient using spectral analysis software based on the total weight and the surface dose rate value. Then, it uses the attenuation coefficient to generate the measurement path of the energy spectrum measuring device 4. The controller 6 can then control the moving drive mechanism 5 to drive the energy spectrum measuring device 4 along the measurement path to perform energy spectrum measurement on the waste bin and obtain the measurement result. Even when the distribution of the filling material inside the waste bin is uneven, this method of measurement still results in a small measurement deviation.

[0045] To ensure accurate positioning of the waste bin to be tested after it is placed on the measuring rotary table 1, this embodiment of the application further provides an alignment mechanism for the measuring rotary table 1. This alignment mechanism is used to align the waste bin to be tested as conveyed by the conveying device. Specifically, the alignment mechanism includes three laser alignment devices 7 evenly distributed along the circumference of the rotary table.

[0046] In order to perform a complete inspection of the surface of the waste bin to be inspected when performing surface dose rate value detection, the embodiments of this application may also provide that the surface dose rate detection mechanism 3 includes a plurality of surface dose rate meters 31, and the plurality of dose rate meters are used to detect the surface of multiple parts of the waste bin to be inspected.

[0047] Specifically, to facilitate the fixing of multiple surface dose rate meters 31, this embodiment of the application may also provide that multiple surface dose rate meters 31 are mounted on the side of the measuring rotary table 1 via a bracket 32. In practical applications, the number of surface dose rate meters 31 can be determined according to the height and diameter of the waste bin to be tested. For example, in one implementation, this embodiment of the application may provide five surface dose rate meters 31, which are respectively mounted at the bottom, lower middle, middle, upper middle, and top of the bracket 32. To allow each surface dose rate meter 31 to move closer to or further away from the waste bin to be tested as needed, facilitating the entry and exit of the waste bin from the rotary table, and ensuring that the distance from the waste bin to be tested during measurement meets design requirements, this embodiment of the application may also provide that the bracket 32 ​​is connected to a rotary drive mechanism, which drives the bracket 32 ​​to carry multiple surface dose rate meters 31 closer to or further away from the waste bin to be tested.

[0048] To further improve measurement accuracy, this application embodiment may also provide a collimating shield 8 disposed in front of the energy spectrum measuring device 4, and the controller 6 may also be used to control the opening size of the collimating shield 8 according to the dose rate value.

[0049] The following section provides a detailed description of the device provided in the embodiments of this application, taking the setting of five surface dose rate meters 31 as an example.

[0050] This application embodiment provides a measuring device consisting of five surface dose rate meters, a weighing device 2, a measuring rotary table 1, and an energy spectrum measuring device 4, which, with the assistance of spectroscopic software, completes the detection of waste bins. The device first, through the combined action of the five surface dose rate meters, the measuring rotary table 1, and the weighing device 2, completes the radioactivity detection of the waste bin surface and measures the total weight. The spectroscopic software then calculates the attenuation coefficient based on the surface dose rate, total weight, and a model of the waste bin. After obtaining the attenuation coefficient, the software automatically calculates the path of the energy spectrum detector (energy spectrum measuring device 4) and the distance between the detector and the waste bin surface. Under the automatic control of the software, the energy spectrum detector collects the energy spectrum of the waste bin. After the measurement is completed, the spectroscopic software calculates the efficiency and the total activity of the radionuclides based on the measurement results. This method effectively reduces the problem of large measurement accuracy deviations caused by the inhomogeneity of radioactive materials inside the bin.

[0051] The measuring device and measurement process of this waste bin detection device can be briefly described as follows:

[0052] 1. The measuring rotating table 1 of the waste bin measuring device is equipped with three laser alignment devices 7, spaced 120° apart. The waste bin is automatically placed under the action of the conveying device and the three laser alignment devices 7, and the total weight of the waste bin is measured.

[0053] 2. Surface dose rate meters 31 are located at the bottom, lower-middle, middle, upper-middle, and top of the detection device, respectively, and are mainly used to measure the surface dose rate of the waste bins. The dose rate meters, in conjunction with the rotating measuring stage, measure the dose rate on the surface of the waste bins and transmit the measured values ​​to the spectral analysis software for a preliminary assessment of the radioactivity distribution.

[0054] 3. On the measurement software, based on the dose rate value obtained in step 2 and the measured total weight, generate a model of the waste bin and calculate the corresponding attenuation coefficient. Set the measurement route of the energy spectrum detector according to the function;

[0055] 4. Based on the parameters obtained in step 3, the detection device moves to the corresponding initial position and adjusts the opening size of the attenuator (spectral measurement device).

[0056] 5. The detection device completes the measurement of the entire waste bin according to the measurement route calculated in step 3;

[0057] 6. After the measurement is completed, the spectral analysis software automatically performs nuclide identification, efficiency calculation, and total activity calculation, thus completing the measurement of the entire waste container.

[0058] In the measuring device, a dose rate meter is mounted on a specific transfer device to measure the dose rate distribution on the surface of the waste bin; a weighing device 2 is mounted on the bottom of the measuring rotary table 1 to accurately measure the weight of the waste bin placed on the measuring table; three laser measuring devices are evenly distributed on the rotating measuring table to accurately locate the position of the waste bin. An energy spectrum measuring device 4 is mounted on a device that can move back and forth and up and down, and during measurement, it moves up and down and back and forth according to the measurement route to accurately measure the energy spectrum and total count of the waste bin; an automatically opening and closing collimating shield 8 is installed in front of the energy spectrum measuring device 4, and the opening size of the collimating shield 8 is automatically adjusted according to the dose rate value during the measurement process.

[0059] Measurement procedure of waste bin measuring device:

[0060] In step S1, the waste bin device automatically works with the transfer device to complete the installation of the waste bin, and then automatically measures the total weight of the waste bin.

[0061] In step S2, the surface dose rate meter 31 measures the dose rate value on the surface of the waste bin to obtain the dose rate distribution, providing strong data for subsequent measurements.

[0062] In step S3, the spectral analysis software, under the combined influence of the dose rate value and the total weight of the waste container, calculates the attenuation coefficient and pre-plans the measurement route, providing support for subsequent measurements. Using a positive feedback neural network algorithm, the measurement path is first calculated based on the measured dose rate vector, and then corrected according to the obtained attenuation coefficient.

[0063] In step S4, the energy spectrum measuring device 4, under the control of the software, completes the measurement of the entire waste bin and acquires energy spectrum data and count rate. The energy spectrum measuring device performs energy spectrum measurements along a preset path, and simultaneously corrects the measurement route based on the measured energy spectrum data, thus completing the overall measurement of the waste bin.

[0064] In step S5, the spectral analysis software automatically completes the identification of nuclides, efficiency calculation, and total activity calculation.

[0065] In summary, the nuclear waste container measuring device provided in this application effectively reduces the problem of large measurement accuracy deviations caused by the uneven distribution of radioactive material inside the container. Multiple surface dose rate measurements are used to obtain the dose rate distribution on the surface of the waste container, providing accurate data for subsequent calculations and measurement route planning, while also allowing for a preliminary assessment of the radioactive distribution within the waste container. By coordinating the dose rate values ​​and the total weight, the attenuation coefficient is accurately calculated, providing a reliable basis for subsequent measurements. Using a dose rate vector based on the measured dose rate values, the system flexibly adjusts the opening size of the attenuation device during measurement, thereby effectively improving measurement accuracy and reducing the increase in detector dead time caused by high doses.

[0066] It should be noted that, in this document, relational terms such as "first" and "second" are used only to distinguish one entity or operation from another, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Furthermore, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Without further limitations, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes said element.

[0067] As can be seen from the above description of the embodiments, those skilled in the art can clearly understand that this application can be implemented by means of software plus necessary general-purpose hardware platforms. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, can be embodied in the form of a software product. This computer software product can be stored in a storage medium, such as ROM / RAM, magnetic disk, optical disk, etc., and includes several instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute the methods described in various embodiments or some parts of the embodiments of this application.

[0068] The various embodiments in this specification are described in a progressive manner. Similar or identical parts between embodiments can be referred to mutually. Each embodiment focuses on describing the differences from other embodiments. In particular, for system or system embodiments, since they are basically similar to method embodiments, the description is relatively simple, and relevant parts can be referred to the descriptions in the method embodiments. The systems and system embodiments described above are merely illustrative. The units described as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the modules can be selected to achieve the purpose of this embodiment according to actual needs. Those skilled in the art can understand and implement this without creative effort.

[0069] The above description is merely a preferred embodiment of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention are included within the scope of protection of the present invention.

Claims

1. A nuclear waste container measuring device, characterized in that, include: A measuring rotary table is provided with a weighing device; the measuring rotary table is also provided with an alignment mechanism, which is used to align the waste bin to be tested conveyed by the conveying device. A surface dose rate detection mechanism is disposed on the side of the measuring rotary table; An energy spectrum measuring device, wherein the energy spectrum measuring device is connected to a moving drive mechanism; the moving drive mechanism is used to drive the energy spectrum measuring device to move back and forth and up and down. The controller is electrically connected to the measuring rotary table, the weighing device, the surface dose rate detection mechanism, the energy spectrum measurement device, and the moving drive mechanism, respectively. The controller is used to perform the following operations: Receive the total weight of the waste bin to be tested placed on the measuring rotary table, obtained by the weighing device; The surface dose rate detection mechanism receives the surface dose rate value of the waste bin to be tested. The model of the waste bin to be tested and the corresponding attenuation coefficient are obtained using the total weight and the surface dose rate value through spectral analysis software. The measurement path of the energy spectrum measuring device is generated using the attenuation coefficient. The mobile drive mechanism is controlled to drive the energy spectrum measuring device to move along the measurement route to perform energy spectrum measurement on the waste bin to be tested and obtain the energy spectrum measurement result, so that the spectrum interpretation software can perform nuclide identification, efficiency calculation and total activity calculation of the waste bin to be tested based on the energy spectrum measurement result; A collimating shield is provided in front of the energy spectrum measuring device, and the controller is also used to control the opening size of the collimating shield according to the dose rate value.

2. The nuclear waste container measuring device according to claim 1, characterized in that, The alignment mechanism includes three laser alignment devices evenly distributed along the circumference of the rotary table.

3. The nuclear waste container measuring device according to claim 1, characterized in that, The surface dose rate detection mechanism includes multiple surface dose rate meters, which are used to detect the surface of multiple parts of the waste bin to be tested.

4. The nuclear waste container measuring device according to claim 3, characterized in that, Multiple surface dose rate meters are mounted on the side of the measuring rotary table via supports.

5. The nuclear waste container measuring device according to claim 4, characterized in that, The surface dose rate meter includes five units, which are respectively located at the bottom, lower middle, middle, upper middle, and top of the support.

6. The nuclear waste container measuring device according to claim 4, characterized in that, The bracket is connected to a rotary drive mechanism, which drives the bracket to carry multiple surface dose rate meters closer to or further away from the waste bin to be tested.

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