Method and system for measuring neutron, gamma energy spectrum and dosage in nuclear power station

Abstract

The invention discloses a method for measuring neutron, gamma energy spectrum and dosage in a nuclear power station. The method comprises the following steps: 1 ) the neutron and gamma rays are inputinto a neutron detection system to output a signal A, and the gamma rays are input into a gamma detection system to output a signal B; 2) the signal A and the signal B are input into a digital signalprocessing circuit to be subjected to operation processing to obtain the neutron, gamma energy spectrum and dosage, wherein the digital signal processing circuit takes a field-programmable gate arraychip as a core chip. Compared with the prior art, the method for measuring neutron, gamma energy spectrum and dosage in the nuclear power station disclosed by the invention has the advantages that thesimulations measurement of the neutron, gamma energy spectrum and dosage can be realized based on the field-programmable gate array technology. In addition, the invention further discloses a system for measuring the neutron, gamma energy spectrum and dosage in nuclear power station.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, more specifically, the invention relates to a method and system for measuring neutron, gamma energy spectrum and dose of nuclear power plants, which is suitable for the protection of personnel in mixed field areas such as nuclear islands of nuclear power plants and spent fuel pools , Environmental radiation monitoring. Background technique [0002] Neutron energy spectroscopy is mainly used in the analysis of neutron flux, which plays an important role in the study of neutron behavior and reactor power of reactors; the measurement of gamma energy spectroscopy is mainly used in nuclide identification, industrial flaw detection and other fields. The main purpose of gamma spectrum measurement is to understand the distribution and content of radionuclides in the environment. [0003] At present, the technology for gamma ray detection at home and abroad is very mature, not only a variety of per...

AI Technical Summary

Problems solved by technology

[0006] 1) The neutron and gamma counts are measured only through the cooperation of the discriminator and the counter, and then the dose is calculated according to the count, but the energy spectrum and dose of neutrons and gamma rays cannot be measured at the same time;

[0007] 2) Calculation of neutron and gamma doses based on the counting method has a large inherent erro

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