System and method for detecting radioactive characteristics of nuclear facility waste packages

Abstract

The invention provides a system and method for detecting radioactive characteristics of nuclear facility waste packages, wherein the system comprises a perspective imaging module, a scanning measurement module and a calculation control module; the perspective imaging module and the scanning measurement module are in communication connection with the calculation control module. The invention further provides the method for detecting the radioactive characteristics of the nuclear facility waste packages. Compared with the prior art, the system and method for detecting the radioactive characteristics of the nuclear facility waste packages are closer to the field actual situation, field implementation is facilitated, and the evaluation result is more credible.

Description

【Technical field】 [0001] The invention relates to the technical field of nuclear facility radioactive waste management, in particular to a detection system and method for radioactive characteristics of nuclear facility waste packages. 【Background technique】 [0002] In recent decades, the construction of the national nuclear industry and the development of nuclear energy have continued to carry out a large number of scientific research and production activities, and a large number of nuclear facilities have been established. With the rapid development of construction and operation, various radioactive wastes continue to be generated. After a large number of nuclear facilities built in the early stage have successfully completed various national tasks, in order to protect the environment and public safety, various nuclear facilities have been closed down and entered the decommissioning stage. In the future, more nuclear facilities will be decommissioned. The decommissioning p...

AI Technical Summary

Problems solved by technology

For larger waste packages, usually non-barrel waste packages, the waste package is large in size and weight, and it is difficult to rotate during measurement, making high-efficiency measurement difficult; the distribution of source items and matrix materials in the waste package is uneven, and the waste package contains The density of the matrix and waste after the waste is high, the traditional radioactive source transmission measurement method is difficult to apply, and the self-absorption correction is difficult

The radioactive solid waste package can be measured with a portable gamma spectrometer, but the problem is that the waste package is large in size (1m 3 Above), the measurement error of a single gamma spectrometer is relatively large; the density of the matrix and radioactive waste in the waste package is high and uneven, and the measurement error will be very large without self-absorption correction; the distribution of source items in the solid waste package is uneven, portable The gamma spectrometer cannot accurately measure the distribution of source items in the waste package, and the final measurement error will be very large; for solid waste packages with small radioactive source items, the detection efficiency of the portable gamma spectrometer is low, and it will take a long time to measure large-volume waste packages. time, cannot be applied in engineering

[0013] The main features of the correlation γ non-destructive measurement technology in the detection system shown in Table 1 are as follows: a high-resolution HPGe detector is used for continuous scanning measurement of the box, which is suitable for complex nuclide types and energy spectra in waste inclusions , improves the measurement accuracy to a certain extent, but the detection efficiency of the HPGe detector is low, when the waste package is scanned and measured, when the waste source item in the waste package is small, the measurement takes a long time (especially for large-volume , medium and high density waste packages); the waste body is divided into many voxels, and the activity of each voxel is measured separately, so as to obtain the spatial distribution of the radioactive activity of the waste body, and the sum is the total activity. The activity of each voxel must be calculated, so the detection efficiency calibration must be carried out for each voxel. The calibration test has a large workload and a long measurement time; considering the inhomogeneity of the matrix, transmission measurement is used for self-absorption correction, and the measurement system requires an additional transmission source. The device increases the transmission measurement and emission measurement links, resulting in a long time for waste measurement and analysis, and the density of the matrix and waste in the waste bag is high and uneven, and ordinary transmission measurement cannot accurately measure the large-volume transmission. For the transmission source item of the waste package, only a few high-intensity and high-energy rays can pass through and make the measurement results stable and acceptable. Even if high-energy rays can pass through high-density and large-volume waste bins, a very high linear attenuation coefficient is required to obtain accurate linear attenuation coefficients. source strength, which imposes very stringent requirements on radioactive source management for waste bin transmission measurements

Therefore, traditional radioactive source transmission measurement methods are difficult to apply

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