Mixed nuclide gamma point source volume sample efficiency calibration method

An efficiency calibration and sample technology, applied in X / γ / cosmic radiation measurement, measuring devices, instruments, etc., can solve problems such as difficulty in ensuring accuracy, limited types of standard gas sources, and inability to guarantee traceability, avoiding manufacturing Sophisticated effects

Inactive Publication Date: 2013-06-05
CHINA INST FOR RADIATION PROTECTION
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Problems solved by technology

However, since the internal structure of the detector is not very clear (the thickness of the dead layer on the surface of the detector crystal, the sensitive volume of the detector, the inhomogeneity of the charge collection efficiency, etc.), it is difficult to guarantee its accuracy

Method used

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  • Mixed nuclide gamma point source volume sample efficiency calibration method
  • Mixed nuclide gamma point source volume sample efficiency calibration method
  • Mixed nuclide gamma point source volume sample efficiency calibration method

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Embodiment Construction

[0023] The present invention will be described in detail below in conjunction with the accompanying drawings and embodiments.

[0024] The invention is a new method for obtaining the detection efficiency curve of a detector by combining Monte Carlo simulation and experiment. Let the sample volume be V, the position of the detector in the sample The detection efficiency of γ-ray with isotropic emission and energy E is Then the detection efficiency of the detector to the whole sample ε t (E) as follows:

[0025] ϵ t ( E ) = N A = ∫ V ϵ ( r → , E ) · C ( ...

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Abstract

The invention belongs to the ionizing radiation measurement technology, in particular to a mixed nuclide gamma point source volume sample efficiency calibration method. Measurement results of solid mixed nuclide gamma point source around a detector are adopted and the monte carlo simulation calculation is combined to determine the detection efficiency of the detector to arbitrary axisymmetric shape volume samples. Through the measurement results of solid mixed nuclide gamma point source around the detector, a volume sample detection efficiency curve can be determined. Under the premise that the traceability of calibration result values is guaranteed, the problems that complex manufacturing process and occurrence of radioactive wastes which are brought by other calibration methods ( such as standard volume sample calibration) are avoided.

Description

technical field [0001] The invention belongs to ionizing radiation metering technology, in particular to a volume sample efficiency calibration method of a mixed nuclide gamma point source. Background technique [0002] In order to ensure the safety of residents around nuclear power plants and environmental protection, the activity concentrations of various radioactive noble gases in gaseous effluents should be measured and confirmed. At present, the inert gas online monitoring system commonly used in China is NGM-204. Since it does not have the function of nuclide identification, it cannot give the activity concentrations of different inert gases separately; and its detection lower limit is relatively high. For inland Its suitability for nuclear power plants has yet to be demonstrated. In order to determine the discharge of various nuclides in the effluent, some domestic nuclear power plants use HPGe spectrometers to measure the activities of various nuclides in the sample...

Claims

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Application Information

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IPC IPC(8): G01T1/178G01T1/167
Inventor 金成赫韦应靖张庆利黄亚文牛强
Owner CHINA INST FOR RADIATION PROTECTION
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