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WS/T 184-2017 English PDF

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WS/T 184-2017: Determination of radionuclides in air by gamma spectrometry
Status: Valid

WS/T 184: Evolution and historical versions

Standard ID	Contents [version]	USD	STEP2	[PDF] delivered in	Standard Title (Description)	Status	PDF
WS/T 184-2017	English	229	Add to Cart	3 days [Need to translate]	Determination of radionuclides in air by gamma spectrometry	Valid	WS/T 184-2017
WS/T 184-2017	English	229	Add to Cart	3 days [Need to translate]	Determination of radionuclides in air by gamma spectrometry	Valid	WS/T 184-2017
WS/T 184-1999	English	559	Add to Cart	3 days [Need to translate]	Gamma spectrometry method of analysing radionuclides in air	Obsolete	WS/T 184-1999

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Basic data

Standard ID	WS/T 184-2017 (WS/T184-2017)
Description (Translated English)	Determination of radionuclides in air by gamma spectrometry
Sector / Industry	Health Industry Standard (Recommended)
Classification of Chinese Standard	C57
Word Count Estimation	9,979
Date of Issue	2017-10-27
Date of Implementation	2018-05-01
Older Standard (superseded by this standard)	WS/T 184-1999
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 184-2017: Determination of radionuclides in air by gamma spectrometry

---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
Determination of radionuclides in air by gamma spectrometry ICS 13.280 C 57 WS People's Republic of China Health Industry Standard Replace WS/T 184-1999 Analytical Method of Radionuclides in Air by γ Energy Spectrum 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. This standard replaces WS/T 184-1999 "Analysis Method of Radionuclides in Air by γ Energy Spectrum". Compared with WS/T 184-1999, except The main technical changes besides editorial changes are as follows. -Modified the "scope" of the standard (see Chapter 1, Chapter 1 of the.1999 edition); - "Citation Standard" is revised to "Normative Reference Documents" (see Chapter 2, Chapter 2 of the.1999 edition); - "Definitions" was revised to "Terms and Definitions" (see Chapter 3, Chapter 3 of the.1999 edition), and "Workplace and Environment “Air monitoring” and “breathing belt sampling” (3.1 and 3.4 of the.1999 edition), revised “aerosol”, “air sampler”, "Breathing belt" and "personal air sampler" (see 3.1, 3.2, 3.3 and 3.4, 3.6, 3.2, 3.3 and 3.5 of the.1999 edition); -Deleted "Method Overview" (see Chapter 4 of the.1999 edition); -Deleted the "Schematic Diagram of Air Sampling System Composition", "Schematic Diagram of Combined Sampler" and filter media in "Instruments and Equipment" Content (see 5.1 of the.1999 edition), "Instruments and equipment" is revised to "materials and equipment" (see Chapter 4,.1999 edition of the Chapter 5); - "Filter material" is changed to "filter medium" (see 4.2, 5.1.2 of the.1999 edition); - "Sampling method" is changed to "sampling", which is divided into "ambient air sampling", "workplace air sampling" and "individual Human air sampling" (see Chapter 5, Chapter 6 of the.1999 edition); -Revised the "minimum gas recovery" (see 5.6, 6.7 of the.1999 edition); -Deleted the "determination of sampling efficiency" (see 6.9 in the.1999 edition); -Modified "Spectrometer Calibration" (see Chapter 6, Chapter 7 of the.1999 Edition), and added "Passive Efficiency Calibration" (see Chapter 6); - "Measurement and Nuclide Analysis" is revised to "Measurement and Analysis" (see Chapter 7, Chapter 8 of the.1999 edition); -Modified "Calculation of Air Activity Concentration" and "Decay Correction" (see Chapter 7,.1999 edition of 8.4 and 8.5); -Revised the "Result Report" (see Chapter 8, Chapter 9 of the.1999 edition), and added Type A and Type B uncertainty And expanded uncertainty (see Chapter 8); -Deleted Appendix A, Appendix B, Appendix C and Appendix D (see Appendix A, Appendix B, Appendix C and Appendix D in the.1999 edition). Drafting organizations of this standard. Nuclear Accident Medical Emergency Center of National Health and Family Planning Commission, Radiation Protection and Nuclear Safety of China Center for Disease Control and Prevention Medical Institute, Heilongjiang Provincial Center for Disease Control and Prevention, Shandong Academy of Medical Sciences Institute of Radiation Medicine, Xinjiang Uyghur Center for Disease Control and Prevention Heart, Beijing Center for Disease Control and Prevention, Jiangsu Provincial Center for Disease Control and Prevention. The main drafters of this standard. Zhang Qing, Liu Changan, Xu Cuihua, Tuofei, Zhou Qiang, Zhang Jing, Li Wenhong, Ding Yanqiu, Yuan Long, Zhao Yu, Li Huijuan, Meng Qinghua, Hu Pengchao, Xu Jiaang, Yang Xiaoyong, Yu Ningle, Wang Yuwen, Hao Jianmei. Analytical Method of Radionuclides in Air by γ Energy Spectrum

1 Scope

This standard specifies the method for determining the composition and activity concentration of gamma radionuclides in the air by a high purity germanium (HPGe) gamma spectrometer, Ge (Li) The detector and sodium iodide detector can be implemented with reference to this standard. This standard is applicable to the gamma spectrum analysis of radionuclides in the air.

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 11713-2015 High-purity germanium γ energy spectrum analysis general method GB/T 11743-2013 γ-spectrum analysis method for radionuclides in soil

3 Terms and definitions

The following terms and definitions apply to this document. 3.1 Aerosol A gas dispersion system formed by solid or liquid particulate matter in air or other gaseous media. Aerosols containing radionuclides are called Radioactive aerosol. 3.2 Air sampler A device that uses suction to collect or trap aerosol particles or gaseous iodine on the filter medium. 3.3 Breathing zone The area near the operator’s mouth and nostrils. When the operator completes the specified task, the air there is inhaled through the mouth and nose Into the human body. 3.4 Personal air sampler An air sampler worn by the staff to obtain a representative air sample of the breathing belt.

4 Materials and equipment

4.1 Air sampling system The air sampling system mainly includes an air sampler, a flow measurement and control device and a suction power. 4.2 Filter media Appropriate filter media should be selected according to the sampling purpose and collection object. The effective sampling area of the filter medium should be the same as that of the air sampler. The window area matches. This document recommends three commonly used filter media. a) Superfine glass fiber filter paper. used to collect aerosol particles; b) Activated carbon filter paper. used to collect gaseous elemental iodine and aerosol particles; c) Activated carbon filter cartridge. used to collect gaseous organic iodide. 4.3 Flow measurement and control device The flow measurement and control device should have the functions of real-time flow display, flow adjustment and collection volume accumulation. The flow measurement device should be Calibration accuracy should be better than 5%. 4.4 Pumping power The pumping power should be linked with the flow control device to realize the function of flow adjustment and maintaining a constant flow. 4.5 Sample box It is used to install filter media samples for direct measurement by gamma spectrometer, and the material of the sample box should be polyethylene. 4.6 Energy spectrometer Energy spectrometer is an instrument for measuring the energy of γ-rays of radioactive materials. It consists of shielded room, detector, electronic system, computer and For output and printing equipment, please refer to Chapter 3 of GB/T 11713-2015 for related performance indicators. γ spectrometer should be Verification by the legal metrology department.

5 sampling

5.1 Sampling principle According to the monitoring type, it is divided into ambient air sampling, workplace air sampling and personal air sampling. The sampling location and time of the air sample And the number of samples should be representative. 5.2 Ambient air sampling Ambient air sampling refers to air sampling in environments outside the boundaries of nuclear facilities, radiation sources, or non-sealed source radiation workplaces. To be used for monitoring and control of ambient air radiation levels. Ambient air sampling should be carried out in accordance with the specific radiation ambient air monitoring plan. Air The sampling point should be selected in an open area with no surrounding trees or buildings, or an uncovered building without the influence of tall buildings. on the platform. When monitoring accident air pollution, special attention should be paid to the timeliness and geographical distribution of sampling. 5.3 Air sampling in the workplace Workplace air sampling refers to air sampling within the boundaries of nuclear facilities, radiation sources or non-sealed source radiation workplaces, and is mainly used Monitoring of air radiation levels in the workplace. In the absence of a personal air sampler, it can be used for inhaled air internal radiation personal dose Of estimates. At this time, the sampling point should be set at a key location where radioactive pollution of the air may occur, and fixed point sampling is usually adopted, and the sampling is high. 1.5 m from the ground. 5.4 Personal air sampling Personal air samplers should be used to monitor radioactive workers inhaling radioactive contaminated air in the workplace. personal The air sampler should be worn on the corresponding human body part of the breathing belt for sampling. The air sampling rate should be similar to the human breathing rate. The time depends on the type of polluting nuclide and the concentration level of radionuclide activity in the air. 5.5 Sampling information record Sampling information includes but is not limited to sampling start time, end time, sampling flow rate, sampling site temperature and air pressure, sampling location and Information about surrounding environment characteristics, sampler, sample number, etc. 5.6 Minimum sampling volume The minimum sampling volume depends on the purpose of sampling, the estimated air activity concentration and the lower detection limit of the analysis method. 5.7 Air sampling volume The sampling volume Vr in the sampling state can be obtained by formula (1). 5.8 Air sampling volume correction Air pressure and temperature will affect the volume of gas sampling. When the temperature at the sampling location is lower than 5℃ or higher than 35℃, the atmospheric pressure is lower than 98.8kPa Or when it is higher than 103.4 kPa, use formula (2) to correct the volume of collected air to the volume V0 in the standard state. 6 γ spectrometer scale 6.1 Energy scale The energy calibration of the energy spectrometer requires a calibration source with known γ-ray energy, and its energy range should cover the γ-ray energy of the sample to be tested. Generally, 40 keV～2 000 keV are used. For single-energy and multi-energy nuclides suitable for energy calibration, see Appendix A of GB/T 11713-2015.Scale method See 4.2 of GB/T 11713-2015. 6.2 Active efficiency scale The active efficiency calibration of the energy spectrometer requires a standard source of known radionuclide activity concentration. The matrix of the source should be consistent with the material and The characteristics such as density are the same or similar. The γ-ray energy emitted by the radionuclide contained in the standard source should be in the range of 40 keV to 2 000 keV, The single-energy and multi-energy nuclides suitable for efficiency calibration are shown in Appendix A of GB/T 11713-2015, and natural radionuclides can be added. Scale square See 4.3 of GB/T 11713-2015. 6.3 Passive efficiency scale The passive efficiency calibration of the energy spectrometer is only for detectors that have completed the passive efficiency calibration characterization. Use passive efficiency calibration software to input the measured The density, material, size, distance from the detector and other parameters of the sample and sample box, the passive efficiency calibration software automatically completes the efficiency of the γ spectrometer Scale.

7 Measurement and analysis

7.1 Background measurement of filter media Take the same batch of clean filter media, put it in the sample box with a lid and seal, and measure under the same conditions as the efficiency scale. The measurement time is generally not Less than 24 hours or statistical fluctuation of all-powerful peak count ≤5%. 7.2 Measurement of samples Put the sampled filter medium in the sample box and measure under the same conditions as the efficiency scale. The measurement time should meet the requirements of the nuclides to be tested. The statistical fluctuation of the minimum almighty peak count is ≤5%. 7.3 Qualitative identification of nuclides Accurate energy calibration is the basis for qualitative identification of nuclides, based on the energy of the central channel of the γ universal peak to compare the energy identification of the nuclides in the nuclide library Nuclide. When identifying nuclides, care should be taken to eliminate interference with similar γ-ray energies, see 7.4 of GB/T 11743-2013. 7.4 Relative comparison method for quantitative calculation of nuclide The relative comparison method is suitable for the calculation of the activity concentration of the radionuclide in the sample when the standard source of the nuclides to be tested is available. Use the computer to decode the spectrum to obtain the net area of all-power peaks in the standard source and sample spectra. The moment of the i-th almighty peak of the j-th nuclide in the standard source The degree coefficient Cji is shown in formula (3). 7.5 Nuclide quantitative calculation efficiency curve method The efficiency curve method is suitable for the calculation of the activity concentration of the radionuclide in the sample when the existing efficiency calibration curve is available. Obtain the efficiency value ηji corresponding to a specific energy γ-ray according to the efficiency curve after the efficiency scale or the fitting function of the efficiency curve, The activity concentration jQ of the j-th nuclide in the tested sample is shown in formula (5). 7.6 Decay correction When the sampling time, storage time, and measurement time are greater than the half-life of the nuclides to be measured, the decay of the nuclides in each time interval shall be carried out. Correction. The calibration from sample collection to sample measurement is shown in equation (6), and the calibration during sample measurement is shown in equation (7).

8 Results report

8.1 Report format The content of the result report should include the result of the quantitative calculation of the nuclide and the corresponding expanded uncertainty. 8.2 Evaluation method of uncertainty 8.2.1 Type A uncertainty Based on the measurement series, statistical analysis is used to evaluate the uncertainty of type A, and the uncertainty of type A in γ energy spectrum analysis is evaluated by formula (8). 8.3 Reports below the lower detection limit of instrument measurement When the nuclide quantitative calculation result is lower than the lower detection limit of the instrument, the result is expressed as "less than the lower detection limit". For the calculation method of the lower detection limit, see Appendix C of GB/T 11713-2015.

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