MODELING OF HARDWARE SPECTRUMS OF CdZnTe- DETECTORS

  • V.A. Mokritskij
  • O.V. Maslov
  • O.V. Banzak
  • O.I. Leshchenko
Ключові слова: parametric reliability, photodetectors, performance criterion, ionizing radiation, crystal structure

Анотація

This article has developed a technique for modeling the instrumental spectrum obtained by measuring the intrinsic gamma radiation of spent nuclear fuel with different burnup depths and the degree of leakage fuel cladding. The spectrum model of the studied fuel assembly made it possible to determine the sensitivity of measurements and choose the optimal algorithm for processing the spectra. Due to this, costs of developing hardware and software components of the nuclear fuel condition monitoring system have been reduced. The difference between this technique and the known ones is that they did not use the simulation of the distribution of electric field strength in the volume of the sensor crystal and did not use the Monte Carlo method to simulate electric charge induced during the initial interaction of gamma radiation with the crystal. An experimental verification of the technique using the example of modeling the radiation spectrum of 137Cs source confirmed the effectiveness of the use of the spectrometer based on the CdZnTe detector created in this work: compliance with the requirements for monitoring the state of nuclear fuel in real time; identification of fuel assemblies containing fuel elements with an unpressurized cladding; determination of fuel burnup based on the activity of fission products. For the first time, a method has been proposed for processing large packets of the spectra of the own gamma radiation of spent nuclear fuel. A distinctive feature of the method is the two-stage processing of the spectra: at the first stage, parameters are determined that describe the measured spectra and are necessary for the operation of the algorithms for their processing by methods of numerical differentiation; at the second stage, using these methods, large arrays of spectra are automatically processed in real time.This method increases the accuracy of measurements and the completeness of the distribution pattern of burnup over the fuel assembly volume. This is the technological basis of the tomography method created in this work.
Опубліковано
2019-11-04
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ВІЙСЬКОВА ТЕХНІКА І ТЕХНОЛОГІЇ ПОДВІЙНОГО ПРИЗНАЧЕННЯ