Mixed radiation field dose measurement system based on liquid scintillator detector

Abstract

The invention discloses a mixed radiation field dose measurement system based on a liquid scintillator detector. The mixed radiation field dose measurement system comprises a liquid scintillator detector, a digital pulse waveform collector and a signal processing system, wherein the liquid scintillator detector is connected with the digital pulse waveform collector, and the digital pulse waveform collector is connected with the signal processing system. The neutron dose rate and the gamma dose rate in a mixed radiation field are measured at the same time, errors are reduced, full-digital collection and storage of pulse signals are achieved, data support is provided for follow-up processing, and the mixed radiation field dose measurement system has wide application prospects in the aspects of actual dose monitoring and scientific research.

Description

technical field [0001] The invention relates to the technical field of nuclear technology application, and more specifically, relates to a mixed radiation field dose measurement system based on a liquid scintillator detector. Background technique [0002] In nuclear power plants and other nuclear-related workplaces, due to the complex types of radiation produced by the decay of nuclear materials, the energy distribution is wide, and it has the characteristics of a typical mixed radiation field. The strong penetrating radiation is mainly n-γ. How to accurately and effectively evaluate it, It is of great significance to the evaluation of external exposure of personnel and the monitoring of the radiation safety situation of the site. [0003] At present, the mainstream detectors for neutron and gamma measurement on the market include He-3 tubes for neutron measurement, NaI and halogen tube detectors for gamma measurement, all of which can realize the measurement of a single ray...

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Problems solved by technology

[0003] At present, the mainstream detectors for neutron and gamma measurement on the market include He-3 tubes for measuring neutrons, NaI and halogen tube detectors for measuring gamma, all of which can realize the measurement of a single ray, but only a single ray. Simultaneous monitoring of n-γ-rays in a mixed radiation field cannot be realized. At the same time, the dose assessment is mostly calculated by multiplying the detector count by the particle fluence-dose conversion factor. Document ICRP39 clearly gives different energy fluence-dose The relationship between conversion factor and quality factor, especially for neutrons, is nonlinear, and the difference between different energies is very obvious, so the neutron-gamma dose assessment method not based on spectral analysis will inevitably lead to very large errors

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