CN-121978736-A - Quick nondestructive measuring device and measuring method for activity of radioactive steel ingot

CN121978736ACN 121978736 ACN121978736 ACN 121978736ACN-121978736-A

Abstract

The invention discloses a rapid nondestructive measuring device and a measuring method for radioactivity steel ingot activity, comprising a control module, a transmission module, a quality measuring module, The control module is used for controlling the transmission module, the quality measurement module and the analysis calculation module The transmission module is used for driving the radioactive steel ingot to be measured to reach a preset quality measurement position and The quality measurement module is used for acquiring the quality data of the radioactive steel ingot to be measured The said The spectrum measuring module is used for collecting the radiation steel ingot to be measured under the shielding condition The analysis and calculation module is internally provided with Monte Carlo calculation software and is used for calculating the full-energy peak simulation detection efficiency based on passive efficiency scales And combine with the above Energy spectrum and quality data And outputting the nuclide activity analysis result of the radioactive steel ingot to be detected.

Inventors

LIU RUIWEN
WEI JIAFU
LIU LIYE
LI HUA
CAO QINJIAN
ZHAO YUAN
SONG PEITAO
NIU JINBO
CHEN KEWEI
LONG ZEYU

Assignees

中国辐射防护研究院

Dates

Publication Date: 20260505
Application Date: 20260130

Claims (8)

1. A rapid nondestructive measuring device for activity of a radioactive steel ingot is characterized by comprising a control module, a transmission module, a quality measuring module, The spectrum measurement module and the analysis and calculation module: Wherein the control module is used for controlling the transmission module, the quality measurement module and the transmission module The spectrum measurement module cooperates to realize the automation of the measurement flow; the transmission module is used for driving the radioactive steel ingot to be measured to reach a preset quality measurement position and a preset quality measurement position A spectrum measurement location; The quality measurement module is used for obtaining the quality data of the radioactive steel ingot to be measured The said The spectrum measuring module is used for collecting the radiation steel ingot to be measured under the shielding condition An energy spectrum; The analysis and calculation module is internally provided with Monte Carlo calculation software and is used for calculating the full-energy peak simulation detection efficiency based on passive efficiency scales And combine with the above Energy spectrum and quality data And outputting the nuclide activity analysis result of the radioactive steel ingot to be detected.
2. The apparatus of claim 1, wherein the drive module comprises a motor, a driving roller, a driven roller, a conveyor belt and a first support frame, the motor and the driving roller are linked to drive the conveyor belt to move so as to drive the radioactive steel ingot to be measured to sequentially reach the quality measuring position and the quality measuring position The position is measured by energy spectrum.
3. The apparatus of claim 1, wherein the The spectrum measurement module comprises a high-purity germanium detector, a shielding body and a multi-channel analyzer, wherein the shielding body is provided with an opening facing the radioactive steel ingot to be measured so as to inhibit environmental background radiation, and the multi-channel analyzer is connected with the high-purity germanium detector so as to realize the purpose of And (5) collecting and storing energy spectrum signals.
4. The apparatus according to claim 1, wherein the mass measurement module comprises a load cell for acquiring mass data when the radioactive ingot to be measured reaches the mass measurement position And sending the result to the analysis and calculation module.
5. A method for rapid non-destructive measurement of activity of a radioactive ingot, applied to the apparatus of any one of claims 1 to 4, comprising: Performing crystal size characterization on the high-purity germanium detector, and establishing and verifying an efficiency calculation model of the high-purity germanium detector; placing a non-radioactive steel ingot sample with the shape, density and geometric dimension consistent with those of the radioactive steel ingot to be detected right in front of the high-purity germanium detector, and collecting a background energy spectrum; the transmission module is used for moving the radioactive steel ingot to be detected to the fixed geometric measurement position which is the same as the non-radioactive steel ingot sample, and collecting the radioactive steel ingot to be detected An energy spectrum; The parameters required by the passive efficiency scale are obtained, and at least comprise the geometric position relation between the radioactive steel ingot to be detected and the high-purity germanium detector, the geometric size and the material parameters of the radioactive steel ingot to be detected and the quality of the radioactive steel ingot to be detected And calculating the density of the radioactive steel ingot to be measured according to the density ; Based on the parameters required by the high-purity germanium detector efficiency calculation model and the passive efficiency scale, establishing a geometric model comprising the high-purity germanium detector, a shielding body and a steel ingot, and obtaining different energies by adopting Monte Carlo simulation Corresponding full-energy peak simulation detection efficiency ; Based on the radioactive steel ingot to be measured Extracting the nuclide of interest from the energy spectrum and the background energy spectrum At characteristic energy The net peak area at the position is subtracted by background energy spectrum, and the combination is combined with the Quality of steel ingot Calculating nuclide activity concentration And total activity of 。
6. The method of claim 5, wherein the crystal size characterization of the high purity germanium detector, and wherein establishing and verifying the high purity germanium detector efficiency calculation model comprises: The gamma energy spectrum measurement is carried out by placing a preset point source at a preset distance in front of a high-purity germanium detector, and the full energy peak actual measurement detection efficiency of gamma rays of each energy is obtained by calculation, wherein the energy is A kind of electronic device Ray, full energy peak actual measurement detection efficiency The method meets the following conditions: Wherein, the At energy for a preset point source The net peak area of the all-round peak at the position, For the preset activity of the point source, At energy for a preset point source The branching ratio at which the branching occurs, Measuring time for a preset point source; establishing a high-purity germanium detector efficiency calculation model by using Monte Carlo simulation software, and calculating the full-energy peak simulation detection efficiency Monte Carlo simulation detection efficiency of gamma rays of each energy ; By adjusting parameters of high-purity germanium detector crystals in the high-purity germanium detector efficiency calculation model, the gamma rays with each energy are led to And (3) with The relative deviation of (2) is less than 2%. Thereby obtaining the verified high-purity germanium detector efficiency calculation model.
7. The method of claim 5, wherein the nuclide is a nuclear species At the energy Net count rate at Concentration and activity The method meets the following conditions: Wherein, the Is a radioactive steel ingot to be measured Nuclides in energy spectrum At the energy The net peak area of the all-round peak at the position, For nuclides in background energy spectrum At the energy The net peak area of the all-round peak at the position, Is a radioactive steel ingot to be measured The time of the energy spectrum measurement is determined, For the background measurement time, the time required for the measurement, Is nuclide At the energy The branching ratio at which the branching occurs, Is the quality of the steel ingot, Is nuclide Is used for the concentration of the activity of (a), Is nuclide Is a total activity of (1).
8. A computer readable storage medium, on which a computer program is stored, characterized in that the program, when being executed by a processor, implements the method of one of claims 5-7.

Description

Quick nondestructive measuring device and measuring method for activity of radioactive steel ingot Technical Field The invention relates to the field of nuclear radioactive waste treatment, in particular to a rapid nondestructive measuring device and a measuring method for activity of a radioactive steel ingot. Background During the operation and maintenance of nuclear facilities, a large amount of radioactive metal waste is generated. In the field of radioactive waste treatment, a smelting treatment technology is often adopted to cast the radioactive steel ingot into a radioactive steel ingot, so that the volume of waste can be reduced, the subsequent final treatment is convenient, and the steel ingot can be further manufactured into a waste container through rolling, so that the secondary utilization is realized. The accurate radioactivity measurement of the steel ingots is a key link for judging the radioactivity level or carrying out classified treatment, and has great economic value and environmental safety significance. Current methods of measuring the activity of nuclides in solid waste are classified into destructive and non-destructive methods. The activity measurement of large-volume and high-density objects such as radioactive steel ingots lacks mature and effective nondestructive measurement schemes in industry, and destructive laboratory analysis measurement methods are generally adopted. The method needs to cut or grind a representative sample from a steel ingot, then sends the sample to a professional radiochemistry laboratory for a series of treatment and measurement analysis, and the analysis method of the sampling laboratory has the advantages of complex flow, long time consumption and high cost. And because the distribution of nuclides in the steel ingot may have non-uniformity, the local sampling result is difficult to completely represent the total activity of the whole steel ingot with a weight of several tons, and the risk of large measurement uncertainty exists. In the field of radioactive waste treatment, non-destructive measurement (non-destructive measurement) techniques, in particular measurement systems based on gamma spectroscopy, have been widely used for activity measurement in 200 liter standard waste drums. These systems are usually equipped with shields, mechanical transfer means and a fixed array of high purity germanium detectors, with non-destructive measuring devices and techniques mainly applied to activity measurements in standard waste drums, and no non-destructive measuring device is currently on the market specifically designed for the specific measuring object, radiosteel ingot. When facing non-standard and large-volume samples, the existing nondestructive measurement technology generally adopts an active efficiency scale method, namely, an experimental scale is carried out by using a scale source with known activity and similar to the shape and the matrix of the sample to be measured, and an analog scale source which is completely consistent with the actual radioactive steel ingot in size, density and element composition is needed to be manufactured by using the active efficiency scale method, so that the cost is high and the process is complex. Disclosure of Invention To achieve the above and other related objects, the present invention discloses a rapid nondestructive measuring device for activity of a radioactive steel ingot, which comprises a control module, a transmission module, a quality measuring module,The spectrum measurement module and the analysis and calculation module: Wherein the control module is used for controlling the transmission module, the quality measurement module and the transmission module The spectrum measurement module cooperates to realize the automation of the measurement flow; the transmission module is used for driving the radioactive steel ingot to be measured to reach a preset quality measurement position and a preset quality measurement position A spectrum measurement location; The quality measurement module is used for obtaining the quality data of the radioactive steel ingot to be measured The saidThe spectrum measuring module is used for collecting the radiation steel ingot to be measured under the shielding conditionAn energy spectrum; The analysis and calculation module is internally provided with Monte Carlo calculation software and is used for calculating the full-energy peak simulation detection efficiency based on passive efficiency scales And combine with the aboveEnergy spectrum and quality dataAnd outputting the nuclide activity analysis result of the radioactive steel ingot to be detected. Preferably, the transmission module comprises a motor, a driving roller, a driven roller, a conveyor belt and a first supporting frame, wherein the motor is linked with the driving roller to drive the conveyor belt to move, so as to drive the radioactive steel ingot to be measured to sequentially reach the quality measurement pos