CN110727020B - Measuring and scaling method, device and system for medium-low level waste and storage medium - Google Patents
Measuring and scaling method, device and system for medium-low level waste and storage medium Download PDFInfo
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Abstract
The invention discloses a method for measuring scales of medium and low-level waste, which measures the scales of the medium and low-level waste by detecting the type of an object to be measured, starting an alpha neutron measurement scale mode if the medium and low-level waste is alpha waste, and starting a gamma measurement scale mode if the medium and low-level waste is not alpha waste; the invention also provides a measuring and calibration device, a system and a computer readable storage medium for the medium and low-level waste, thereby realizing the measurement application of different radioactive elements to the waste, solving the problem that the existing mode is difficult to be suitable for the neutron detection of most radioactive elements, improving the measurement precision of the measurement of the medium and low-level waste due to the compatibility of the two modes, and also improving the safety and reliability of the measurement and classification treatment of the medium and low-level waste.
Description
Technical Field
The invention relates to the technical field of radioactive waste detection, in particular to a method, a device and a system for measuring and calibrating medium and low-level radioactive waste and a computer readable storage medium.
Background
Neutron detection technology is commonly used for detection of barreled nuclear waste, and is non-destructive (NDA) detection technology, and the key of the technology is to obtain a reasonable calibration curve. Because the distribution randomness of the density distribution of the medium and the distribution of the radioactive nuclide in the waste barrel is very strong, when the neutron measuring device is calibrated, the detection efficiency (or counting rate) of different positions in the barrel is difficult to obtain, and a reasonable calibration curve is difficult to obtain.
At present, the field of detection of medium and low-level waste storage and transportation containers has been separately researched on an alpha neutron detection calibration method, but the alpha neutron detection method only has certain representativeness, a corresponding system cannot realize measurement of different wastes, the alpha neutron measurement method is difficult to be applied to neutron detection of most radioactive elements, if the alpha neutron detection method is applied to other radioactive elements, the measurement deviation is large, the classification is inaccurate, and even the classified utilization has a large safety problem.
Disclosure of Invention
The invention mainly aims to provide a method, a device and a system for measuring and calibrating medium and low-level waste and a computer readable storage medium, and aims to solve the technical problem that the existing alpha neutron detection mode is applied to other radioactive elements and causes low measurement precision.
In order to achieve the above object, the present invention provides a method for measuring calibration of low-level and medium-level waste, the method comprising:
detecting the type of the low-level waste placed in the cylindrical measuring cavity, wherein the type comprises alpha waste and gamma waste;
judging whether the low-level waste is alpha waste or not according to the type;
if the medium and low-level waste is alpha waste, acquiring scale experimental data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model, and calculating a neutron counting relational expression between all the measuring points according to the scale experimental data, wherein the scale experimental data is neutron counting generated by the medium and low-level waste at the measuring points of the cylindrical measuring cavity;
if the medium and low-level waste is not alpha waste, obtaining basic parameters of the medium and low-level waste, determining position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression between all the position points according to the experimental data;
and processing the measured data of the neutron counting relation by utilizing a Monte Carlo principle to obtain a measurement scale curve of the medium and low-level waste, wherein the measurement scale curve is a regular curve of the neutron counting of the medium and low-level waste.
Optionally, the step of acquiring, by using a preset cylindrical data acquisition model, scale experiment data of measurement points arranged on different sides in the cylindrical measurement cavity, and calculating a neutron count relation between all the measurement points according to the scale experiment data includes:
selecting an upper bottom surface, a lower bottom surface and a middle surface of the cylindrical measuring cavity, and respectively setting measuring points on the upper bottom surface, the lower bottom surface and the middle section, wherein the middle surface is the circular section of the cylindrical measuring cavity;
placing a radionuclide on the measuring points, collecting neutron counts generated by the radionuclide on the corresponding measuring points, and classifying the neutron counts according to the upper bottom surface, the lower bottom surface and the middle surface;
and carrying out data processing according to the classified neutron count to obtain a neutron count relational expression between the measuring points on each surface.
Optionally, if the radionuclide is a radioactive source 240 Pu, placing radioactive nuclide on the measuring point, and collectingThe neutron counts generated by the radionuclide on the corresponding measuring points and classified according to the upper bottom surface, the lower bottom surface and the middle surface comprise:
a radioactive source is arranged at the center of the circle of the upper bottom surface 240 Pu and recording first neutron counts of all measuring points on the upper bottom surface, wherein all measuring points on the upper bottom surface comprise four points symmetrically arranged on the circumference of the upper bottom surface and four points symmetrically arranged in the upper bottom surface;
radioactive sources are placed at four symmetrical positions in the middle plane 240 Pu and recording second neutron counts of all the measuring points on the middle surface, wherein all the measuring points on the middle surface comprise four points symmetrically arranged on the circumference of the middle surface;
placing radioactive sources at the center of the circle of the lower bottom surface and four points based on the symmetry of the center of the circle 240 Pu and recording a third neutron count of all measurement points on the bottom surface, wherein all measurement points on the middle surface comprise four points symmetrically arranged on the circumference of the bottom surface.
Optionally, the placing of the radionuclide on the measurement points, collecting neutron counts generated by the radionuclide on the corresponding measurement points, and classifying the neutron counts according to the upper bottom surface, the lower bottom surface, and the middle surface, further includes:
respectively calculating the positions of the upper bottom surface, the lower bottom surface and the middle surface when no radioactive source is placed 240 Pu, background neutron count of four measurement points on the circumference of each face.
Optionally, the data processing according to the classified neutron count to obtain a neutron count relational expression between the measurement points on each surface includes:
analyzing a first neutron counting rule of four points on the circumference of the upper bottom surface relative to four points in the upper bottom surface according to the first neutron counting, and calculating a first neutron counting relational expression based on the first neutron counting rule;
analyzing the circle center of the middle surface and a second neutron counting rule of the circle center relative to the four measuring points according to the second neutron counting, and calculating a second neutron counting relational expression based on the second neutron counting rule;
and analyzing a third neutron counting rule of the circle center of the lower bottom surface relative to four measuring points on the circumference of the lower bottom surface according to the third neutron count and the background neutron count, and calculating a third neutron counting relational expression based on the third neutron counting rule.
Optionally, the processing the measurement data of the neutron counting relation by using the monte carlo principle to obtain the measurement calibration curve of the medium and low level waste comprises:
processing by using a Monte Carlo method according to a neutron counting relation between the measuring points on each surface to obtain a neutron counting formula of the low-and-medium-level radioactive waste in the cylindrical measuring cavity;
and establishing a measurement scale curve of the medium and low level waste according to the neutron counting formula.
Optionally, the step of acquiring basic parameters of the low-and-medium-level waste, determining position points of a measurement scale of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relation between all the position points according to the experimental data includes:
obtaining basic parameters of the medium and low-level waste according to a gamma measurement scale principle, wherein the basic parameters comprise at least one of a base material, waste loading density, nuclide characteristic gamma ray energy to be detected and geometric dimensions;
simulating a neutron emission scene of the low-level and medium-level waste in the cylindrical measuring cavity according to the basic parameters, and calculating the overall efficiency of the low-level and medium-level waste in the cylindrical measuring cavity based on the neutron emission scene;
determining the position point according to the overall efficiency;
based on the position points, carrying out gamma ray counting measurement on the medium and low-level waste, and recording corresponding experimental data;
and analyzing the neutron emission rule of the medium and low-level waste according to the experimental data, and generating the neutron counting relational expression based on the neutron emission rule.
In order to solve the technical problem, the invention further provides a measuring scale device for low-medium level waste, which comprises:
a detection module for detecting the types of the low-level and medium-level waste placed in the cylindrical measurement cavity, wherein the types include alpha waste and gamma waste;
the judging module is used for judging whether the medium-low level waste is alpha waste or not according to the type;
the first measurement module is used for acquiring scale experimental data of measurement points arranged on different sides in the cylindrical measurement cavity by using a preset cylindrical data acquisition model when the medium and low-level waste is alpha waste, and calculating a neutron counting relational expression between all the measurement points according to the scale experimental data, wherein the scale experimental data is neutron counting generated by the medium and low-level waste at the measurement points of the cylindrical measurement cavity;
the second measurement module is used for acquiring basic parameters of the low-and-medium-level waste when the low-and-medium-level waste is not alpha waste, determining position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression among all the position points according to the experimental data;
and the scale processing module is used for processing the measured data of the neutron counting relation by utilizing a Monte Carlo principle to obtain a measured scale curve of the medium and low-level waste, and the measured scale curve is a regular curve of the neutron counting of the medium and low-level waste.
In order to solve the technical problem, the invention further provides a measuring scale system for low-and-medium-level waste, which comprises:
a detection device for detecting the types of the low-level and medium-level waste placed in the cylindrical measurement cavity, wherein the types comprise alpha waste and gamma waste; and judging whether the low-level waste is alpha waste or not according to the type;
the alpha neutron measuring device is used for acquiring scale experimental data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model when the medium and low level waste is alpha waste, and calculating a neutron counting relational expression among all the measuring points according to the scale experimental data, wherein the scale experimental data is the neutron counting relational expression generated by the medium and low level waste at the measuring points of the cylindrical measuring cavity
The gamma measuring device is used for acquiring basic parameters of the low-level and medium-level waste when the low-level and medium-level waste is not alpha waste, determining position points of measuring scales of the cylindrical measuring cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression among all the position points according to the experimental data;
and the scale processing device is used for processing the measured data of the neutron counting relation by utilizing the Monte Carlo principle to obtain a measured scale curve of the medium and low-level radioactive waste, and the measured scale curve is a regular curve of the neutron counting of the medium and low-level radioactive waste.
In order to solve the technical problem, the invention further provides a computer-readable storage medium, on which a measurement and calibration program for low and medium level waste is stored, and when the measurement and calibration program for low and medium level waste is executed by a processor, the steps of the measurement and calibration method for low and medium level waste as described in any one of the above are implemented.
According to the method for measuring the scales of the medium-low-level waste, the type of an object to be measured is detected, if the medium-low-level waste is alpha waste, the alpha neutron measurement scale mode is started to measure the scales of the medium-low-level waste, and if the medium-low-level waste is not alpha waste, the gamma measurement scale mode is started to measure the scales of the medium-low-level waste; the alpha neutron measurement scale mode is suitable for the measurement scale calibration of the alpha neutron measurement subsystem of the integrated measurement device for the medium and low-level radioactive waste storage and transportation container, and the gamma measurement scale mode is suitable for the measurement scale calibration of the gamma measurement subsystem of the integrated measurement device for the medium and low-level radioactive waste storage and transportation container; based on the implementation, the measurement application of different radioactive elements to the waste is realized, the problem that the conventional mode is difficult to be suitable for neutron detection of most radioactive elements is solved, the measurement precision of the measurement of the medium and low-level waste is improved due to the compatibility of the two modes, and the safety and the reliability of the measurement and the classification treatment of the medium and low-level waste are also improved.
Drawings
FIG. 1 is a schematic flow chart of a method for measuring and calibrating low-level waste provided by the present invention;
FIG. 2 is a schematic flow chart of alpha neutron measurement provided by the present invention;
FIG. 3 is a schematic flow chart of gamma neutron measurement provided by the present invention;
FIG. 4 is a schematic view of a cylindrical measurement chamber provided by the present invention;
FIG. 5 is a schematic view of a measurement cross-section provided by the present invention;
FIG. 6 is a schematic view of an empty, low-to-medium storage and shipping container provided by the present invention;
FIG. 7 is a schematic structural diagram of a measurement calibration device for low-level and medium-level waste provided by the invention;
fig. 8 is a schematic structural diagram of a measurement calibration system for low-and-medium-level waste provided by the invention.
The implementation, functional features and advantages of the objects of the present invention will be further explained with reference to the accompanying drawings.
Detailed Description
It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
The first embodiment:
the invention provides a measurement calibration method applied to a medium-low-level waste storage and transportation container integrated measurement system.
In this embodiment, the system is operated to detect whether the low-level waste is alpha waste; if the alpha waste is the alpha waste, directly performing the warehousing treatment of the alpha waste according to the warehousing treatment standard of the alpha waste; if not, then entering a gamma waste detection program for gamma waste detection. According to the detection process of detecting alpha waste and then detecting gamma waste, in order to match the detection process, the alpha neutron measurement system needs to be calibrated, and then the gamma measurement subsystem needs to be calibrated.
The measurement scale proposed in this embodiment may also be a calibration method, and generally, in practical applications, the measurement scales for wastes on the measurement chamber are set according to the test experience of a test or a developer, but these measurement scales may be adjusted again according to the practical use or test, and in this embodiment, measurement of α and γ neutrons is implemented by being compatible on one system, so that mutual calibration in measurement can be implemented, and thus, a certain accuracy adjustment is obtained in the process of using one of the measurement scales. Therefore, in use, according to a detection process of detecting alpha waste and then detecting gamma waste, in order to match with the detection process, the alpha neutron measurement system needs to be calibrated, then the gamma measurement subsystem needs to be calibrated, and finally one of the modes is selected to realize the measurement classification of the waste.
As shown in fig. 1, a method for measuring and calibrating low-level waste is provided for an embodiment of the present invention, and the method specifically includes the following steps:
step S110, detecting the types of the low-level and medium-level waste placed in a cylindrical measuring cavity, wherein the types comprise alpha waste and gamma waste;
in the present embodiment, α waste and γ waste are understood to be emissive objects that can only be measured by α neutrons and emissive objects that can only be measured by non- α neutrons, respectively, and preferably, gamma radioactive elements are used for emissive objects that can only be measured by non- α neutrons.
Step S120, judging whether the low-level and medium-level waste is alpha waste or not according to the type;
in this step, at the time of judgment, judgment and detection can be made specifically by a common non-destructive analysis method (NDA) by detecting the radiation of α activity emitted from the waste.
Step S130, if the medium and low-level waste is alpha waste, acquiring scale experiment data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model, and calculating a neutron counting relational expression between all the measuring points according to the scale experiment data, wherein the scale experiment data is neutron counting generated by the medium and low-level waste at the measuring points of the cylindrical measuring cavity;
in this step, when calculating the neutron counting relational expression, measurement may be implemented by setting multiple measurement points at multiple levels in a manner of setting multiple measurement surfaces for the cylindrical measurement cavity, and such a measurement setting manner may improve the counting uniformity of neutrons.
In this embodiment, the method may specifically be implemented by the following steps:
selecting an upper bottom surface, a lower bottom surface and a middle surface of the cylindrical measuring cavity, and respectively setting measuring points on the upper bottom surface, the lower bottom surface and the middle section, wherein the middle surface is the circular section of the cylindrical measuring cavity;
placing a radionuclide on the measuring points, collecting neutron counts generated by the radionuclide on the corresponding measuring points, and classifying the neutron counts according to the upper bottom surface, the lower bottom surface and the middle surface;
and carrying out data processing according to the classified neutron counts to obtain a neutron count relational expression between the measuring points on each surface.
In order to further improve the measurement accuracy of neutron count, in this step, counting and detecting the original radiation neutrons in the measurement surface, specifically, calculating the positions of the upper bottom surface, the lower bottom surface and the middle surface without placing radioactive sources respectively 240 Pu, background neutron count of four measurement points on the circumference of each face.
Step S140, if the medium and low level waste is not alpha waste, obtaining basic parameters of the medium and low level waste, determining position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression between all the position points according to the experimental data;
in this embodiment, for the measurement scale for measuring the medium and low-level waste by using gamma neutrons, firstly, a simulation is performed by using basic parameters of the measurement object to obtain an overall effect, then, an optimal neutron radiation measurement position in the cylindrical measurement cavity is calculated based on the overall effect, and the neutron count of the object to be measured is collected based on the position, so that the neutron count rule of the object to be measured is analyzed, and a corresponding neutron count relational expression is obtained.
And S150, processing the measured data of the neutron counting relation by utilizing a Monte Carlo principle to obtain a measurement scale curve of the medium and low-level waste, wherein the measurement scale curve is a regular curve of the neutron counting of the medium and low-level waste.
In this embodiment, the measurement scale for obtaining the low-level and medium-level waste by the monte carlo principle can be specifically divided into three main steps: constructing or describing a probabilistic process; sampling from a known probability distribution is achieved; various estimates are established.
In this embodiment, a neutron counting formula of the low-medium waste in the cylindrical measurement cavity is obtained by processing the medium-low waste by using a monte carlo method according to a neutron counting relation between measurement points on each surface;
and establishing a measurement scale curve of the medium and low-level waste according to the neutron counting formula.
Or, firstly, constructing a blank storage container which is consistent with the base material of the low-and-medium-level waste and has the same geometric dimension and waste loading density, placing standard line sources with different activities in the blank storage container and corresponding to the calibration positions of the three groups of radiation sources and detector assemblies with corresponding heights, and establishing a calibration curve required by the gamma quantitative measurement analysis of the low-and-medium-level waste storage container through measurement so as to calibrate a gamma measuring device of the low-and-medium-level waste storage container, thereby obtaining a corresponding measurement scale curve.
In this embodiment, the implementation of step S130 can be specifically implemented in the following manner, that is:
the method comprises the following steps of acquiring scale experimental data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model, and calculating a neutron counting relational expression among all the measuring points according to the scale experimental data, wherein the scale experimental data comprises the following steps:
selecting an upper bottom surface, a lower bottom surface and a middle surface of the cylindrical measuring cavity, and respectively setting measuring points on the upper bottom surface, the lower bottom surface and the middle section, wherein the middle surface is the circular section of the cylindrical measuring cavity;
placing a radionuclide on the measuring points, collecting neutron counts generated by the radionuclide on the corresponding measuring points, and classifying the neutron counts according to the upper bottom surface, the lower bottom surface and the middle surface;
and carrying out data processing according to the classified neutron counts to obtain a neutron count relational expression between the measuring points on each surface.
In practical application, if the radionuclide is a radioactive source 240 Pu, said placing a radionuclide on said measurement point, collecting neutron counts produced by said radionuclide on corresponding measurement points, and classifying said neutron counts according to said top, bottom, and middle planes comprising:
a radioactive source is arranged on the circle center of the upper bottom surface 240 Pu and recording first neutron counts of all measuring points on the upper bottom surface, wherein all measuring points on the upper bottom surface comprise four points symmetrically arranged on the circumference of the upper bottom surface and four points symmetrically arranged in the upper bottom surface;
placing radioactive sources at four symmetrical positions in the middle plane 240 Pu and recording a second neutron count of all measurement points on the midplane, whereinAll the measuring points on the middle surface comprise four points symmetrically arranged on the circumference of the middle surface;
placing radioactive sources on the circle center of the lower bottom surface and four points based on the circle center symmetry 240 Pu and recording third neutron counts of all the measuring points on the lower bottom surface, wherein all the measuring points on the middle surface comprise four points symmetrically arranged on the circumference of the lower bottom surface;
respectively calculating the positions of the upper bottom surface, the lower bottom surface and the middle surface without radioactive sources 240 Pu, background neutron count of four measurement points on the circumference of each face.
Finally, when calculating the relational expression, the data processing is performed according to the classified neutron count, and obtaining the neutron count relational expression between the measurement points on each surface includes:
analyzing a first neutron counting rule of four points on the circumference of the upper bottom surface relative to four points in the upper bottom surface according to the first neutron counting, and calculating a first neutron counting relational expression based on the first neutron counting rule;
analyzing the center of the middle surface and a second neutron counting rule of the center of the circle relative to four measuring points according to the second neutron counting, and calculating a second neutron counting relational expression based on the second neutron counting rule;
and analyzing a third neutron counting rule of the circle center of the lower bottom surface relative to four measuring points on the circumference of the lower bottom surface according to the third neutron count and the background neutron count, and calculating a third neutron counting relational expression based on the third neutron counting rule.
The α measurement process is described in detail in a specific application scenario, as shown in fig. 2, in the α neutron measurement process, the measurement cavity used is a cylindrical measurement cavity, so that the calibration method adopts a cylindrical data acquisition model when calibration experiment data is collected; the principle is that a measurement calibration model is established first, representative radioactive nuclides are selected as radioactive sources, neutron counting measurement and data processing of different sides and different positions are carried out, a calibration rule of alpha neutron measurement is obtained and is used as a measurement calibration method of an alpha neutron measurement subsystem, and the specific implementation flow is as follows:
step S131, establishing a measurement calibration model;
in this embodiment, the model is the same size as the cylindrical measurement chamber to ensure that the calibrated data is reliable. Selecting an upper bottom surface circle or a lower bottom surface circle of the cylindrical model, wherein the circle center of the upper bottom surface circle or the lower bottom surface circle is an e point, and two mutually perpendicular diameters are taken when the e point passes through the e point; two points of which the diameters are intersected with the circumference are respectively designated as a, b, c and d; forming straight lines ae, be, ce and de; then, midpoint A, midpoint B, midpoint C and midpoint D of straight lines ae, be, ce and de are taken; selecting upper and lower bottom surfaces and a middle section as measurement scale measurement data collection points in the model, and marking the points of the upper bottom surface as a, B, C, D, A, B, C and D; the point of the middle section is denoted as a 1 ，b 1 ，c 1 ，d 1 ，A 1 ，B 1 ，C 1 ，D 1 (ii) a The point of the bottom surface is denoted as a 2 ，b 2 ，c 2 ，d 2 ，A 2 ，B 2 ，C 2 ，D 2 (ii) a Wherein, the circle centers of the upper bottom surface, the lower bottom surface and the middle section are respectively marked as e and e 1 ，e 2 ；
Step S132, selecting a radioactive source sample: selecting several representative radionuclides capable of emitting neutrons with different masses, and placing the radionuclides in batches according to the same mass;
step S133, measuring and collecting data: the radioactive source is placed in three batches, and the specific setting process is as follows:
(1) placing a radioactive source at the point e, measuring at the points A, B, C, D, a, B, C, D and the like, and recording the neutron count of the point;
(2) in A 1 、B 1 、C 1 、D 1 Placing radioactive sources at four-point positions respectively at e 1 、a 1 、b 1 、c 1 、d 1 Measuring data of the point and recording neutron count of the point;
(3) at e 2 、A 2 、B 2 、C 2 、D 2 The radioactive sources are respectively placed at points a 2 、b 2 、c 2 、d 2 Measuring and recording neutron count by the point;
(4) to better handle the neutron flux at various points of low-level waste in a tank, it is necessary to measure e, e 1 、e 2 、A、B、C、D、A 1 、B 1 、C 1 、D 1 、A 2 、B 2 、C 2 、D 2 A, b, c, d, a of the radioactive source is not placed at the point 1 、b 1 、c 1 、d 1 、a 2 、b 2 、c 2 、d 2 Neutron counts of points, i.e. background neutron counts, to facilitate calculation at e, e respectively 1 、e 2 True neutron count of corresponding points after placement of the source at three points, i.e.
n Fruit of Chinese wolfberry ＝n Measuring -n Background of the invention (1)
And a relational expression between the neutron count at the point and the neutron count at the corresponding point can be obtained according to the calculated real neutron count value;
step S134, data processing: the data processing is performed according to the three radiation source placement categories described in step S133, and the classification processing is as follows:
(1) performing data grouping processing by taking the straight lines Aa, bb, cc and Dd as categories to obtain the relation between the neutron counts of the points A and a, B and B, C and C, D and D, and listing a relational expression; the following were used:
setting:
Wherein, is defined as
Within the volume element dV of each point, the energy E and the direction of motion
Belong to
Average neutron track length of (1). Then there are:
since the geometry of the neutron flux is calculated to be circular, it can be known from the geometric knowledge of the circle that: calculating the neutron flux rate of each point B/C/D and the neutron flux rate of each point A by the same calculation method, namely calculating the neutron flux rate of each point B/C/D by the formula (1); the calculation scheme for each point of each measurement plane is also the same.
(2) By a straight line a 1 e 1 、b 1 e 1 、c 1 e 1 、d 1 e 1 Processing the data packet for the class to obtain a 1 And e 1 Point, b 1 Point and e 1 Point, c 1 And e 1 Dot, d 1 And e 1 The relation among the point neutron counts and the relational expression are listed;
(3) by a straight line a 2 e 2 、b 2 e 2 、c 2 e 2 、d 2 e 2 Processing the data packets for the class, e 2 、A 2 、B 2 、C 2 、D 2 Subtracting background neutron count from five points respectively to obtain e 2 、A 2 、B 2 、C 2 、D 2 Counting neutrons after five points are respectively placed with radioactive sources, and then processing a 2 Point and e 2 Point, b 2 Point and e 2 Point, c 2 Point and e 2 Point, d 2 Point and e 2 And (3) according to the deduction, obtaining the relation between the sub-counts in the point as follows:
step S135, result processing: synthesizing the neutron counting relational expression obtained, processing by using a Monte Carlo method to obtain a neutron counting rule of a measurement calibration model, and using the rule formula as a measurement data calibration formula of the alpha neutron measurement system; there is the following process:
let V be the volume of the waste bin and N be the density of neutrons after the ith neutron decay i ，S V The number of fission neutrons generated by source neutrons after multiple collisions, wherein I' is the collision frequency; then according to equation (4), there are:
wherein,
is the state that a source neutron has after the ith collision
The contribution to the neutron flux density in the waste bin, which can be given in the MCNP program in track length counts, i.e.:
wherein L is I Is the track length，W I Is neutron weight, σ f (E I ) Is the total cross-section after the i-th fracture at energy E, Γ σ The number of slow fission neutrons. The measurement data calibration formula of the alpha neutron measurement system obtained by the method is the formula (5).
As shown in fig. 4, the specific implementation principle of the alpha neutron measurement is as follows:
step 1, establishing a cylindrical scale measurement model 2 of a scale measurement method, and taking an upper bottom surface 1, a lower bottom surface 4 and a middle section 3 as scale measurement sections; the measuring points and the radioactive source placing points are shown in the attached figure 5, taking the upper bottom surface 1 of the cylindrical model 2 as an example, two mutually perpendicular diameters are made through the center of a cross-section circle, the center of the circle is marked as a point e, and the points of intersection of the two diameters and the circumference are respectively marked as a, b, c and d; dividing two diameters into four straight lines at the circle center point e, wherein the four straight lines are ae, be, ce and de respectively; respectively taking the midpoints of the four straight lines, and respectively marking the midpoints as A, B, C and D; then, a middle section 3 and a lower bottom surface 4 are selected from the model, and the point of the middle section 3 is marked as a 1 ，b 1 ，c 1 ，d 1 ，A 1 ，B 1 ，C 1 ，D 1 (ii) a The point of the lower bottom surface 4 is marked as a 2 ，b 2 ，c 2 ，d 2 ，A 2 ，B 2 ，C 2 ，D 2 (ii) a Wherein, the circle centers of the middle section 3 and the lower bottom surface 4 are respectively marked as e 1 ，e 2 ；
and 5, comprehensively processing the results obtained in the steps 3, 4, namely the neutron counting relational expression, processing by using a Monte Carlo method to obtain a neutron counting rule of the measurement calibration model, and taking the rule formula as a measurement data calibration formula of the alpha neutron measurement system.
In this embodiment, the specific implementation of step S140 may be:
obtaining basic parameters of the low-level and medium-level waste according to a gamma measurement calibration principle, wherein the basic parameters comprise at least one of a base material, waste loading density, nuclide characteristic gamma ray energy to be detected and geometric dimensions;
simulating a neutron emission scene of the low-level and medium-level waste in the cylindrical measuring cavity according to the basic parameters, and calculating the overall efficiency of the low-level and medium-level waste in the cylindrical measuring cavity based on the neutron emission scene;
determining the position point according to the overall efficiency;
based on the position points, carrying out gamma ray counting measurement on the medium and low-level waste, and recording corresponding experimental data;
and analyzing the neutron emission rule of the medium and low-level waste according to the experimental data, and generating the neutron counting relational expression based on the neutron emission rule.
In practical application, when the gamma scale is measured, the gamma scale can be specifically measured by three groups of radioactive sources and detector assemblies with corresponding heights; based on the device, the measuring and calibration method adopts a standard line source to replace a standard radioactive nuclide source to carry out efficiency activity (or quality) calibration on the device, the principle is based on a Monte Carlo simulation calculation method, the relation between the detection efficiency of linear standard samples (the standard line source) placed at different radius positions in the rotating self-emission line of the low-level waste storage and transportation container in the same matrix and the detection efficiency of the low-level waste storage and transportation container is researched, the equivalent activity (or quality) calibration method of the standard line source to the measured object (namely the low-level waste) is established, the requirement that the standard line source can be used for calibrating various geometric shapes and sizes and various nuclides to be measured is met, and the relation between the counting rate of the standard line source energy gamma rays and the activity (or quality) of the measuring device, namely a gamma measurement calibration curve, is established. The calibration method can well solve the problem that the measurement result is inaccurate due to the fact that radioactive substances in the low-level waste storage and transportation container are uneven in density and different in shape, radioactive substance sources are large in distribution difference and the like, and can better treat low-level waste.
Based on the above γ measurement calibration principle, as shown in fig. 3 and 6, the γ measurement calibration method of the present embodiment adopts the following technical solutions:
step S141, determining various parameters of a calibrated measurement object according to the requirements of a gamma measurement calibration principle, wherein the parameters comprise base material, waste loading density, nuclide characteristic gamma ray energy to be measured, geometric size and the like;
step S142, inputting the parameters of the object to be measured determined in the step S141 into a Monte Carlo transportation program Geant4, simulating a neutron emission scene of a medium-low level waste bucket, and calculating the overall efficiency of the object to be measured;
step S143, according to the principle of the gamma measurement calibration method and the parameters determined in step S141, a blank object (5) which is the same as the parameters of the measurement object in step S141 is constructed, namely, a medium-low-level waste storage and transportation container which is not loaded with nuclear waste;
step S144, calculating data which are consistent with the step S141 by utilizing a Geant4 transport program, simulating and determining the position of a measurement scale which is the same as the overall efficiency of the medium and low-level waste storage and transportation container by utilizing a Monte Carlo method, namely determining the efficiency of each position by utilizing a model which is the same as the overall efficiency calculated by utilizing the Monte Carlo method and is in the medium and low-level waste storage and transportation container without loading nuclear waste;
step S145, according to the requirement of the gamma measurement scale principle, standard line sources with different activities are placed in a blank measurement object (5), namely an empty medium and low-level waste storage and transportation container, gamma ray counting measurement of the medium and low-level waste is carried out, and experimental data are recorded;
and S146, inputting each measured data into a Geant4 transport program, and processing the measured data by using the transport software method to obtain a calibration curve of gamma measurement quantitative analysis.
The invention provides a calibration method of an integrated measurement system of a medium and low-level waste storage and transportation container, which comprises a calibration method of an alpha neutron measurement device and a gamma measurement device, so as to realize the integrated measurement of the medium and low-level waste storage and transportation container, improve the measurement precision of the medium and low-level waste measurement, and improve the safety and reliability of the measurement and classification treatment of the medium and low-level waste.
Second embodiment:
fig. 7 is a measurement calibration apparatus for low-and-medium-level waste provided in an embodiment of the present invention, specifically including: a detection module 71, a determination module 72, a first measurement module 73, a second measurement module 74, and a scale processing module 75, wherein:
a detection module 71 for detecting the types of the low-level and medium-level waste placed in the cylindrical measurement chamber, wherein the types include alpha waste and gamma waste;
a judging module 72, configured to judge whether the low-level waste is alpha waste according to the type;
the first measurement module 73 is configured to, when the low-and-medium-level waste is α waste, acquire, by using a preset cylindrical data acquisition model, scale experiment data of measurement points arranged on different sides in the cylindrical measurement cavity, and calculate a neutron count relation between all the measurement points according to the scale experiment data, where the scale experiment data is a neutron count generated by the low-and-medium-level waste at the measurement points of the cylindrical measurement cavity;
the second measurement module 74 is configured to, when the low-level and medium-level waste is not alpha waste, obtain basic parameters of the low-level and medium-level waste, determine position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquire experimental data of the position points according to a gamma ray counting manner, and calculate a neutron counting relational expression between all the position points according to the experimental data;
and the scale processing module 75 is configured to process the measurement data of the neutron counting relationship by using a monte carlo principle to obtain a measurement scale curve of the medium and low level waste, where the measurement scale curve is a regular curve of the neutron counting of the medium and low level waste.
Based on the same embodiment as the method for measuring and calibrating medium and low level waste in the embodiment of the present invention, the content of the embodiment of the measuring and calibrating device is not described in detail in this embodiment.
In an embodiment of the present invention, there is also provided a measurement and calibration system for low-level and medium-level waste, as shown in fig. 8, the system includes:
a detecting device 81 for detecting the type of the low-level waste placed in the cylindrical measuring chamber, wherein the type includes alpha waste and gamma waste; and judging whether the low-level waste is alpha waste or not according to the type;
an alpha neutron measuring device 82, configured to, when the low-level and medium-level waste is alpha waste, acquire, by using a preset cylindrical data acquisition model, scale experiment data of measurement points arranged on different sides in the cylindrical measurement cavity, and calculate a neutron count relation between all measurement points according to the scale experiment data, where the scale experiment data is a neutron count relation generated by the low-level and medium-level waste at the measurement points of the cylindrical measurement cavity
The gamma measuring device 83 is used for acquiring basic parameters of the low-and-medium-level waste when the low-and-medium-level waste is not alpha waste, determining position points of measuring scales of the cylindrical measuring cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression among all the position points according to the experimental data;
and the scale processing device 84 is used for processing the measured data of the neutron counting relation by utilizing the Monte Carlo principle to obtain a measured scale curve of the medium and low-level waste, wherein the measured scale curve is a regular curve of the neutron counting of the medium and low-level waste.
Based on the same embodiment description as the measuring and calibration method for low-and-medium-level waste in the embodiment of the invention, the embodiment of the measuring and calibration system will not be described in detail in this embodiment.
In order to solve the above problem, an embodiment of the present invention further provides a computer-readable storage medium.
In this embodiment, the computer readable storage medium stores a measurement calibration program for low-and-medium waste, and the measurement calibration program for low-and-medium waste is executed by a processor to implement the steps of the measurement calibration method for low-and-medium waste as described in any one of the above embodiments. The method for implementing the measurement calibration program of the low-and-medium-level waste when executed by the processor can refer to each embodiment of the fleet control method based on the internet of vehicles, and therefore redundant description is omitted.
Through the above description of the embodiments, those skilled in the art will clearly understand that the method of the above embodiments can be implemented by software plus a necessary general hardware platform, and certainly can also be implemented by hardware, but in many cases, the former is a better implementation manner. Based on such understanding, the technical solutions of the present invention or portions thereof contributing to the prior art may be embodied in the form of a software product, which is stored in a storage medium (such as ROM/RAM) and includes several instructions for enabling a terminal (which may be a mobile phone, a computer, a server, or a network device) to execute the methods according to the embodiments of the present invention.
The present invention is described in connection with the accompanying drawings, but the present invention is not limited to the above embodiments, which are only illustrative and not restrictive, and those skilled in the art can make various changes without departing from the spirit and scope of the invention as defined by the appended claims, and all changes that come within the meaning and range of equivalency of the specification and drawings that are obvious from the description and the attached claims are intended to be embraced therein.
Claims (10)
1. A method for measuring and calibrating medium and low-level waste is characterized by comprising the following steps:
detecting the type of the low-level waste placed in the cylindrical measuring cavity, wherein the type comprises alpha waste and gamma waste;
judging whether the low-level waste is alpha waste or not according to the type;
if the medium and low-level waste is alpha waste, acquiring scale experimental data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model, and calculating a neutron counting relational expression between all the measuring points according to the scale experimental data, wherein the scale experimental data is neutron counting generated by the medium and low-level waste at the measuring points of the cylindrical measuring cavity;
if the medium and low-level waste is not alpha waste, obtaining basic parameters of the medium and low-level waste, determining position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression between all the position points according to the experimental data;
and processing the measured data of the neutron counting relation by utilizing a Monte Carlo principle to obtain a measurement scale curve of the medium and low-level waste, wherein the measurement scale curve is a regular curve of the neutron counting of the medium and low-level waste.
2. The method for measuring calibration of middle and low level waste according to claim 1, wherein the step of collecting calibration experiment data of the measurement points disposed on different sides in the cylindrical measurement chamber by using a preset cylindrical data collection model and calculating the neutron counting relation between all the measurement points according to the calibration experiment data comprises:
selecting an upper bottom surface, a lower bottom surface and a middle surface of the cylindrical measuring cavity, and respectively setting measuring points on the upper bottom surface, the lower bottom surface and the middle section, wherein the middle surface is the circular section of the cylindrical measuring cavity;
placing a radionuclide on the measuring points, collecting neutron counts generated by the radionuclide on the corresponding measuring points, and classifying the neutron counts according to the upper bottom surface, the lower bottom surface and the middle surface;
and carrying out data processing according to the classified neutron counts to obtain a neutron count relational expression between the measuring points on each surface.
3. The method for measuring calibration of middle or low level waste according to claim 2, wherein if said radionuclide is a radioactive source 240 Pu, said placing a radionuclide on said measurement point, collecting neutron counts produced by said radionuclide on corresponding measurement points, and classifying said neutron counts according to said top, bottom and middle planes comprises:
a radioactive source is arranged on the circle center of the upper bottom surface 240 Pu and recording first neutron counts of all measuring points on the upper bottom surface, wherein all measuring points on the upper bottom surface comprise four points symmetrically arranged on the circumference of the upper bottom surface and four points symmetrically arranged in the upper bottom surface;
placing radioactive sources at four symmetrical positions in the middle plane 240 Pu and recording second neutron counts of all the measuring points on the middle surface, wherein all the measuring points on the middle surface comprise four points symmetrically arranged on the circumference of the middle surface;
placing radioactive sources on the circle center of the lower bottom surface and four points based on the circle center symmetry 240 Pu and recording third neutron counts of all measurement points on the lower bottom surface, wherein all measurement points on the middle surface comprise four points symmetrically arranged on the circumference of the lower bottom surface.
4. The method for measuring graduation according to claim 3, wherein said placing a radionuclide on said measuring point, collecting neutron counts generated by said radionuclide on the corresponding measuring point, and classifying said neutron counts according to said upper bottom surface, lower bottom surface, and middle surface, further comprises:
respectively calculating the positions of the upper bottom surface, the lower bottom surface and the middle surface when no radioactive source is placed 240 Pu, background neutron count of four measurement points on the circumference of each face.
5. The method for measuring and calibrating low-level waste according to claim 4, wherein the step of processing data according to the sorted neutron counts to obtain the neutron count relation between the measurement points on each surface comprises:
analyzing a first neutron counting rule of four points on the circumference of the upper bottom surface relative to four points in the upper bottom surface according to the first neutron counting, and calculating a first neutron counting relational expression based on the first neutron counting rule;
analyzing the circle center of the middle surface and a second neutron counting rule of the circle center relative to the four measuring points according to the second neutron counting, and calculating a second neutron counting relational expression based on the second neutron counting rule;
and analyzing a third neutron counting rule of the circle center of the lower bottom surface relative to four measuring points on the circumference of the lower bottom surface according to the third neutron count and the background neutron count, and calculating a third neutron counting relational expression based on the third neutron counting rule.
6. The method for measuring and calibrating the low-and-medium-level waste, according to claim 5, wherein the step of processing the measurement data of the neutron counting relation by using the Monte Carlo principle to obtain the measurement and calibration curve of the low-and-medium-level waste comprises the following steps:
processing the waste by using a Monte Carlo method according to a neutron counting relational expression between the measuring points on each surface to obtain a neutron counting formula of the low-level and medium-level waste in the cylindrical measuring cavity;
and establishing a measurement scale curve of the medium and low level waste according to the neutron counting formula.
7. The method for measuring calibration of middle and low level waste according to claim 1 or 6, wherein the steps of obtaining basic parameters of the middle and low level waste, determining the position points of the measurement calibration of the cylindrical measurement chamber based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting method, and calculating the neutron counting relation between all the position points according to the experimental data comprise:
obtaining basic parameters of the low-level and medium-level waste according to a gamma measurement calibration principle, wherein the basic parameters comprise at least one of a base material, waste loading density, nuclide characteristic gamma ray energy to be detected and geometric dimensions;
simulating a neutron emission scene of the low-level and medium-level waste in the cylindrical measuring cavity according to the basic parameters, and calculating the overall efficiency of the low-level and medium-level waste in the cylindrical measuring cavity based on the neutron emission scene;
determining the position point according to the overall efficiency;
based on the position points, carrying out gamma ray counting measurement on the low-level and medium-level waste, and recording corresponding experimental data;
and analyzing the neutron emission rule of the medium and low-level waste according to the experimental data, and generating the neutron counting relational expression based on the neutron emission rule.
8. A measurement calibration device for low and medium level wastes, which is characterized by comprising:
a detection module for detecting the types of the low-level and medium-level waste placed in the cylindrical measurement cavity, wherein the types comprise alpha waste and gamma waste;
the judging module is used for judging whether the medium-low level waste is alpha waste or not according to the type;
the first measurement module is used for acquiring scale experimental data of measurement points arranged on different sides in the cylindrical measurement cavity by using a preset cylindrical data acquisition model when the medium and low level waste is alpha waste, and calculating a neutron counting relational expression among all the measurement points according to the scale experimental data, wherein the scale experimental data is neutron counting generated by the medium and low level waste at the measurement points of the cylindrical measurement cavity;
the second measurement module is used for acquiring basic parameters of the low-and-medium-level waste when the low-and-medium-level waste is not alpha waste, determining position points of measurement scales of the cylindrical measurement cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression among all the position points according to the experimental data;
and the scale processing module is used for processing the measured data of the neutron counting relation by utilizing a Monte Carlo principle to obtain a measured scale curve of the medium and low-level waste, and the measured scale curve is a regular curve of the neutron counting of the medium and low-level waste.
9. A measurement calibration system for low and medium level waste, said system comprising:
a detection device for detecting the types of the low-level and medium-level wastes placed in the cylindrical measurement cavity, wherein the types comprise alpha wastes and gamma wastes; judging whether the low-level waste is alpha waste or not according to the type;
the alpha neutron measuring device is used for acquiring scale experimental data of measuring points arranged on different sides in the cylindrical measuring cavity by using a preset cylindrical data acquisition model when the medium and low-level waste is alpha waste, and calculating a neutron counting relational expression among all the measuring points according to the scale experimental data, wherein the scale experimental data is neutron counting generated by the medium and low-level waste at the measuring points of the cylindrical measuring cavity;
the gamma measuring device is used for acquiring basic parameters of the low-and-medium-level waste when the low-and-medium-level waste is not alpha waste, determining position points of measuring scales of the cylindrical measuring cavity based on the basic parameters, acquiring experimental data of the position points according to a gamma ray counting mode, and calculating a neutron counting relational expression among all the position points according to the experimental data;
and the scale processing device is used for processing the measured data of the neutron counting relation by utilizing the Monte Carlo principle to obtain a measured scale curve of the medium and low-level radioactive waste, and the measured scale curve is a regular curve of the neutron counting of the medium and low-level radioactive waste.
10. A computer readable storage medium, characterized in that the computer readable storage medium has stored thereon a measurement calibration program for low-and-medium waste, which when executed by a processor implements the steps of the measurement calibration method for low-and-medium waste according to any one of claims 1 to 7.
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1295256A (en) * | 1999-08-18 | 2001-05-16 | 上海伽玛射线技术有限公司 | Specific radioactivity measuring method and equipment |
| CN103454669A (en) * | 2012-05-28 | 2013-12-18 | 中国原子能科学研究院 | Method for graduating barreled nuclear waste neutron measuring device |
| CN105665310A (en) * | 2016-03-11 | 2016-06-15 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detecting and classifying method and system |
| JP2017198535A (en) * | 2016-04-27 | 2017-11-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Waste measuring device and waste measuring method |
| CN107462914A (en) * | 2017-09-12 | 2017-12-12 | 西南科技大学 | The method that point source radial position is determined in nuclear waste bucket layering γ scanning |
| CN108919331A (en) * | 2018-07-03 | 2018-11-30 | 上海交通大学 | A kind of double detector spiral gamma scanning survey method of pair of radioactive waste bucket |
| CN109557575A (en) * | 2018-12-17 | 2019-04-02 | 中国原子能科学研究院 | A kind of neutron multiplicity measuring device and its application method |
-
2019
- 2019-10-11 CN CN201910962760.3A patent/CN110727020B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1295256A (en) * | 1999-08-18 | 2001-05-16 | 上海伽玛射线技术有限公司 | Specific radioactivity measuring method and equipment |
| CN103454669A (en) * | 2012-05-28 | 2013-12-18 | 中国原子能科学研究院 | Method for graduating barreled nuclear waste neutron measuring device |
| CN105665310A (en) * | 2016-03-11 | 2016-06-15 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detecting and classifying method and system |
| JP2017198535A (en) * | 2016-04-27 | 2017-11-02 | 日立Ｇｅニュークリア・エナジー株式会社 | Waste measuring device and waste measuring method |
| CN107462914A (en) * | 2017-09-12 | 2017-12-12 | 西南科技大学 | The method that point source radial position is determined in nuclear waste bucket layering γ scanning |
| CN108919331A (en) * | 2018-07-03 | 2018-11-30 | 上海交通大学 | A kind of double detector spiral gamma scanning survey method of pair of radioactive waste bucket |
| CN109557575A (en) * | 2018-12-17 | 2019-04-02 | 中国原子能科学研究院 | A kind of neutron multiplicity measuring device and its application method |
Non-Patent Citations (1)
| Title |
|---|
| 核废物桶检测中探测效率的数值方法;钱雅兰等;《上海交通大学学报》;20170128(第01期);全文 * |
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