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WS/T 584-2017 English PDF

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WS/T 584-2017: Methods for measuring radionuclides in the human body with whole body counts
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Standard ID	Contents [version]	USD	STEP2	[PDF] delivered in	Standard Title (Description)	Status	PDF
WS/T 584-2017	English	379	Add to Cart	4 days [Need to translate]	Methods for measuring radionuclides in the human body with whole body counts	Valid	WS/T 584-2017

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Basic data

Standard ID	WS/T 584-2017 (WS/T584-2017)
Description (Translated English)	Methods for measuring radionuclides in the human body with whole body counts
Sector / Industry	Health Industry Standard (Recommended)
Classification of Chinese Standard	C57
Word Count Estimation	15,146
Date of Issue	2017-10-27
Date of Implementation	2018-05-01
Regulation (derived from)	State-Health-Communication (2017) 22
Issuing agency(ies)	National Health and Family Planning Commission of the People's Republic of China

WS/T 584-2017: Methods for measuring radionuclides in the human body with whole body counts

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Methods for measuring radionuclides in the human body with whole body counts ICS 13.280 C 57 WS People's Republic of China Health Industry Standard Measurement method for whole body count of radionuclides in human body 2017-10-27 released 2018-05-01 Implementation Issued by the National Health and Family Planning Commission of the People's Republic of China

Foreword

This standard was drafted in accordance with the rules given in GB/T 1.1-2009. Drafting organizations of this standard. Chinese Center for Disease Control and Prevention, Institute of Radiation Protection and Nuclear Safety Medicine, Jiangsu Provincial Center for Disease Control and Prevention, China Institute of Radiation Medicine, Chinese Academy of Medical Sciences, Institute of Radiation and Radiation Medicine, Academy of Military Medical Sciences, Chinese Institute of Metrology, Suzhou Thermal Institute of Engineering. The main drafters of this standard. Zhang Jianfeng, Ma Jiayi, Zhou Qiang, Zhang Wenyi, Tuofei, Pan Jie, Li Wenhong, Liang Juncheng, Zhang Qing, Yang Xiao Yong, Yu Enjian, Zhang Jing. Measurement method of whole body count of radionuclides in human body

1 Scope

This standard specifies the method for measuring the type and activity of radionuclides in the human body by a whole body counter. This standard is applicable to the qualitative and quantitative analysis of radionuclides in the human body by whole body counters.

2 Normative references

The following documents are indispensable for the application of this document. For dated reference documents, only the dated version applies to this document. For undated references, the latest version (including all amendments) applies to this document. GB/T 11713 High purity germanium  energy spectrum analysis general method

3 Terms and definitions

The following terms and definitions apply to this document. 3.1 Whole body counter Directly measure X-rays or -rays emitted by radioactive substances in the human body from outside the human body to perform qualitative and quantitative analysis of radionuclides Analysis of the device. 3.2 Lower detection limit The lowest activity that the spectrometer can detect under a given confidence level. 3.3 Motif An object whose absorption or scattering effect on ionizing radiation is basically the same as that of human tissue. Note. It can be used to simulate actual measurement conditions in various measurements.

4 Equipment

4.1 Whole body counter. It consists of detectors, shielded lead chambers, electronic components, data processing systems, etc. Among them, electronic components include Preamplifier, main amplifier, analog-to-digital converter (ADC), high-voltage power supply (HPS) and multi-channel analyzer. 4.2 Types of whole body counters. There are two commonly used ones. high-purity germanium (HPGe) has high energy resolution and relatively low detection efficiency; sodium iodide (thallium) (NaI(Tl)) has high detection efficiency and relatively low energy resolution. According to the purpose and requirements of the measurement, select the type and group of extracorporeal detectors Together. 4.3 High voltage power supply. The detector has a stable working high-voltage power supply, its steady-wave voltage is not more than 0.01%, and the high-voltage semiconductor detector should be connected The continuation is adjustable without any discontinuities. 4.4 Spectrum amplifier. Should have waveform adjustment and match with preamplifier and multi-channel pulse amplitude analyzer. 4.5 Multi-channel pulse amplitude analyzer. It should be selected according to the complexity of the energy spectrum, the ray energy distribution range and the energy resolution of the detector, etc. The track width and number of the multi-channel analyzer. 4.6 Data processing system. Receive and process the spectrum data from the multi-channel analyzer. The data processing system consists of computer hardware and software equipment to make. 4.7 Data processing system hardware. It mainly includes a computer and its supporting read-in device. 4.8 Data processing system software. Various routine procedures for analyzing  spectrum should be included, such as energy calibration, efficiency calibration, spectrum smoothing, peak finding, Basic procedures such as peak area calculation and heavy peak analysis.

5 Calibration source and system calibration

5.1 Calibration source and its requirements 5.1.1 Calibration source The calibration source is a prerequisite for the normal energy calibration and efficiency calibration of the whole body counter. Single and multi-energy nuclei suitable for energy calibration See Appendix A for elements and their main parameters. 5.1.2 Traceability of scale source The calibration source should have accuracy and traceability, and have an inspection certificate. In addition to the given activity (or specific activity) and uncertainty on the certificate, The calibration date, standard source purity, mass or volume, chemical composition, nuclide half-life,  ray branch ratio and standard source calibration should also be marked method. In addition, the total uncertainty of the radionuclide standard source should be less than 5%. 5.2 Energy scale 5.2.1 Scale range The energy of the scale source  ray should be evenly distributed in the energy range of the required scale (usually 40keV～2000keV), and at least 4 energy points are required. The calibration source should be a mixed source emitting multiple energy  rays. 5.2.2 Scale curve Use spectroscopic software to do a straight line fitting between the ray energy and the peak position of the total absorption peak. Energy of high-resolution  energy spectrum system in good working condition The scale curve should be a straight line, and its nonlinearity should be less than 0.5%. If it deviates from linearity, the energy calibration should be done again. Specific requirements according to GB/T The 11713 regulations are implemented. 5.2.3 Verification of the calibration curve During the measurement, the whole body counter should be checked with at least two energy points  rays every day. The energy of the used  rays should depend on The low energy end and high energy end of the near-scale energy zone. If the peak position remains substantially unchanged, the scale data remains applicable. For HPGe detectors greater than 1keV, when the NaI detector is greater than 0.5FWHM, the energy calibration should be redone. 5.3 Efficiency scale 5.3.1 Efficiency scale When measuring the radionuclide content in the human body, the efficiency of the whole body counter should be scaled. 5.3.2 Efficiency calibration source The activity of the radionuclide of the efficiency calibration source should be less than 1000kBq, and the energy distribution should be appropriate for the energy used in the calibration of the efficiency curve It should be distributed in the energy range of 40keV～2000keV, and at least 7 energy gamma rays should be selected. There should be 2 low energy ranges (40keV～200keV)～ 3 gamma rays. The efficiency calibration is carried out by the phantom. 5.4 Scale phantom 5.4.1 Select the scale mode according to the measured radionuclide, the distribution of the radionuclide in the body, the measurement method and the measured photon energy. Body, see Appendix B for details. 5.4.2 When measuring evenly distributed radionuclides in the body, a simple calibration phantom should be used. 5.4.3 When measuring low-energy photons (40 keV ~.200 keV), use the simulation scale phantom. 5.5 Muscle equivalent chest wall thickness 5.6 Tissue thickness correction To measure low-energy photons (100 keV) in an organ, the thickness of the tissue covering the organ must be corrected. Tissue thickness correction is By using the calibration phantom to simulate the human tissue between the measured organ and the detector, through more than three calibration experiments, the phase It should be corrected according to the counting efficiency scale curve.

6 measurement

6.1 Before the measurement, the examinee should remove the accessories, watches, glasses and other metal objects worn on the body. 6.2 After measuring with a radioactive surface contamination meter, it is determined that the subject has no surface radioactive contamination. If it shows that the subject has radioactive surface contamination, Radioactive contamination should be decontaminated first, and measurement can only be performed after confirming that there is no radioactive surface contamination. 6.3 According to the distribution characteristics of radionuclides in the body, the measurement types are divided into whole body measurement and organ measurement. 6.4 Whole body measurement is used to measure the uniform distribution of radionuclides in the body. 6.5 Organ measurement is used to measure the concentration of radionuclides in organs. Common organ measurements include lung measurement and thyroid measurement. 6.6 Lung measurement is used to quantify the radioactivity deposited by the respiratory system. The measurement of radioactivity in the lung should be corrected for muscle equivalent chest wall thickness. 6.7 Thyroid measurement. Under normal thyroid function, about 20% of radioactive iodine is absorbed by the thyroid. The detector is 10cm on the surface of the neck Place. Counting time is 600s.

7 Data analysis methods

7.1 Whole body counter  energy spectrum analysis method 7.1.1 The path location of the total absorption peak (also called the all-power peak or photoelectric peak) is proportional to the energy of the incident -ray, which is the whole-body counter  energy spectrum Qualitative basis. 7.1.2 The net peak area under the total absorption peak is proportional to the number of  rays of the energy interacting with the detector, which is the whole-body counter  energy The basis of spectral quantification. In the analysis of the net peak area of the total absorption peak, the counting of Compton continuum and background should be deducted. 7.2 Radioactivity calculation The radioactivity A can be calculated by formula (2).

8 reports

8.1 Report format 8.1.1 The analysis report should include personal information, such as name, gender, age, exposure history of radioactive contamination, etc. 8.1.2 The analysis report should have the unique number of the examinee, inspection type, inspection staff and inspection time. 8.1.3 The analysis report should include radionuclide activity data and appropriate uncertainty. For uncertainty, this standard recommends 2 times the standard deviation or The inclusion factor is 2, which is the uncertainty in the case of 95% confidence. When reporting uncertainty with confidence, it should be stated in the text or footnotes Marked out to avoid confusion, see Appendix C for details. 8.2 Reports below the detection limit of the whole body counter In the report analysis result, when the result of human count rate minus background (or base) is negative, the common method is to use the leading "≤" Report the DLA value of the human body under actual measurement conditions. See Appendix D for the calculation method of detection limit.

Appendix B

(Normative appendix) Scale phantom B.1 Requirements for scale phantom B.1.1 The main components of the phantom material should have similar radiation attenuation characteristics to the human body. B.1.2 The degree of similarity between the phantom and the human body is related to the purpose of the study. B.1.3 The radioactive substances added to the phantom and their solutions have stable physical and chemical properties and should not react with the phantom materials. B.2 Requirements for standard radioactive materials B.2.1 It shall be a measurement basis recognized by the national legal metrology department or traceable to the national legal metrology department. Standard radioactivity imported from abroad The substance should be approved by the national metrology department. B.2.2 For standard radioactive materials, the original or copy of the inspection certificate and other relevant materials should be provided to ensure the traceability of the delivery process. B.2.3 Standard radioactive materials should be used within the specified validity period. B.3 General requirements for calibration sources B.3.1 Uniformity. whether it is a phantom or a standard radioactive material, its distribution in the scale phantom is uniform and does not produce significant content. The wall specifically adsorbs and changes its distribution. B.3.2 Simulation. Except for the known radioactivity, other properties, such as density, shape, composition, etc., are similar to those of the human body. B.3.3 Stability. During the period of storage and use, there will be no precipitation, deliquescent or crystallization, no foreign matter or mildew. B.3.4 High purity. Except for the added radioactive standard materials, there should be no or as few other radioactive impurities as possible. B.3.5 Accuracy. Under the premise of a confidence level of 99.7%, the uncertainty of radioactivity should be less than 5%. B.3.6 Airtightness. It should be sealed in the phantom without leakage.

Appendix C

(Normative appendix) Extended uncertainty C.1 Expanded uncertainty The expanded uncertainty (C) of the measurement results includes. Type A uncertainty (A) and Type B uncertainty (B). Class A uncertain Degree is to evaluate the uncertainty by statistical analysis of the observation column, such as the uncertainty introduced by statistical counting. Type B uncertainty It uses a method different from the statistical analysis of the observation column to evaluate the standard uncertainty, such as detection efficiency, self-absorption correction factor, volume The uncertainty introduced by the correction factor, emission probability correction factor, nuclide decay correction factor and coincidence addition correction factor. For the measurement junction Therefore, when there are several sources of uncertainty, it is necessary to synthesize various uncertainties.

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