辐射测量_国内外标准网文献检索下载

1.[标准] 紫外辐射源的辐射测量方法

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 43817-2024

发布时间：
2024-03-15

中标分类：
K70 电气照明综合

国标分类：
17.240 辐射测量

实施时间：
2024-10-01

摘要：本文件描述了紫外辐射源在200 nm～400 nm波段范围内的光谱分布、（有效)辐通量、（有效)辐射剂量、（有效)辐强度和（有效)辐照度及其空间分布等辐射度量的测量方法。本文件适用于实验室条件下的紫外辐射源的辐射测量。生产线和应用现场的紫外辐射量测量，以及光辐射源在400 nm～450 nm波段范围内的辐射量测量参照使用。本文件不适用于相干辐射源（如紫外激光器)和自然辐射源（如太阳光)的测量，也不适用于旨在发射200 nm以下真空紫外辐射以产生臭氧的紫外辐射源的测量。

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2.[标准] 电磁屏蔽材料高功率微波屏蔽效能测量方法

发布单位：
中国-国家标准(CN-GB)

标准状态：
即将实施

标准号：
GB/T 44645-2024

发布时间：
2024-09-29

中标分类：
F74 幅射防护监测与评价

国标分类：
17.240 辐射测量

实施时间：
2026-10-01

摘要：本文件描述了100 MHz~40 GHz频率范围内电磁屏蔽材料高功率微波屏蔽效能测量方法、安全与防护以及测试报告内容。本文件适用于平面型电磁屏蔽材料的高功率微波屏蔽效能测量。

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3.[标准] Water quality — Radium 226 — Test method using ICP-MS

水质镭226 ICP-MS试验方法

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 4685:2024

发布时间：
2024-01-09

中标分类：
-

国标分类：
13.060.60 水质 - 水的物理特性检验

17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： This document specifies methods to determine 226Ra concentration by inductively coupled plasma mass spectrometry (ICP-MS). The mass concentrations obtained can be converted into activity concentrations.The method is applicable to test samples of drinking water, rainwater, surface and ground water, after proper sampling and handling, and test sample preparation.The detection limit depends on the sample volume, the instrument used, the background count rate, the detection efficiency, the counting time and the chemical yield. The detection limit of the method described in this document, using currently available equipment, is approximately 10？mBq·l-1, which is better than the WHO criteria for safe consumption of drinking water (1？Bq·l-1).This method covers the measurement of 226Ra in water at activity concentrations between 0,001？Bq·l？1 and 100？Bq·l？1. Samples with concentrations higher than 1？Bq·l？1 can be measured if a dilution is performed.The method described in this document is applicable in the event of an emergency situation.In this method, filtration of the test sample is necessary. The analysis of 226Ra adsorbed to suspended matter is not covered by this method. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document. In this case, the measurement is made on the different phases obtained.It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
4.[标准] 核技术利用单位自行监测技术规范

发布单位：
中国-安徽省地方标准(CN-DB34)

标准状态：
现行

标准号：
DB34/T 4571-2023

发布时间：
2023-10-07

中标分类：
F73 能源、核技术 - 辐射防护与监测 - 环境辐射防护与核医学防护

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：
2023-11-07
5.[标准] 固体材料使用自由空间法的电磁参数测量方法

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 42741-2023

发布时间：
2023-05-23

中标分类：
K04 电工 - 电工综合 - 基础标准和通用方法

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：
2023-12-01

摘要：本文件描述了在2 GHz～110 GHz频率范围使用自由空间法测量固体材料电磁参数的一般要求及测量方法。本文件适用于使用自由空间法对均匀、各向同性的固体材料的复相对介电常数、复相对磁导率等参数的测量。

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6.[标准] 高纯锗γ谱仪

发布单位：
中国-国家标准(CN-GB)

标准状态：
现行

标准号：
GB/T 43535-2023

发布时间：
2023-12-28

中标分类：
F81 能源、核技术 - 核仪器与核探测器 - 通用核仪器

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：
2024-07-01

摘要：本文件规定了高纯锗γ谱仪（以下简称“谱仪”)的分类、技术要求,描述了试验方法，同时对检验规则、标志、随行文件、运输及贮存进行了规定。
本文件适用于具有同轴型半导体探测器（以下简称“同轴型”)的高纯锗γ谱仪的生产、销售、管理和检测等。用于特殊或定制场景的其他类型高纯锗γ谱仪参考使用。

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7.[标准] Radiation protection instrumentation - Installed personnel surface contamination monitors

辐射防护仪表.安装的人员表面污染监测器

发布单位：
国际组织-国际电工委员会(IX-IEC)

标准状态：
现行

标准号：
IEC 61098:2023

发布时间：
2023-02-24

中标分类：
-

国标分类：
13.280 环保、保健和安全 - 辐射防护

17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： IEC 61098:2023 applies to contamination monitors that include warning assembles and meters used for the monitoring of radioactive contamination on the surface of personnel whether they be clothed or not. The document is applicable only to that type of equipment where the user stays at the monitor. This document is applicable to the monitoring of the whole body (including the head), hands and feet, but parts of this document can be used for monitors designed for the monitoring of radioactive contamination on the hands and/or feet only. This document does not include tritium measurement.This third edition cancels and replaces the second edition published in 2003. This edition includes the following significant technical changes with respect to the previous edition:a. Title is modified.b. As an alternative of small area sources, area sources are added to be used for methods of test with respect to the variation of response with source position, effective instrument efficiency, detection limit (DL), and variation of response with energy.c. Detection limit (DL) complies with the ISO 11929 series.d. Descriptions of influence quantities of type F and type S are added.e. Consistency with IEC 62706 is promoted for environmental requirements, mechanical requirements, electromagnetic compatibility and methods of test.f. Descriptions of overhead detectors are added.g. Descriptions of friskers are added with respect to the hand and foot monitoring.h. Figures are made easier to understand the relation between the detector position and the response, and the positional relation between the detector surface and the source.
8.[标准] Standard Practice for Application of CaFinf2/inf(Mn) Thermoluminescence Dosimeters in Mixed Neutron-Photon Environments

混合中子光子环境中CaF＜inf＞2/inf＞（Mn）热释光剂量计的应用标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E2450-23

发布时间：
2023-01-01

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This practice describes a procedure for correcting a CaF2(Mn) thermoluminescence dosimeter (TLD) reading for its response to neutrons during the irradiation. The neutron response may be subtracted from the total TLD response to give the gamma-ray response. In fields with a large neutron contribution to the total response, this procedure may result in large uncertainties.1.2More precise experimental techniques may be applied if the uncertainty derived from this practice is larger than the level that the user can accept. These more precise techniques are not discussed here. The references in Section8describe some of these techniques.1.3This practice does not discuss effects on the TLD reading from neutron interactions with the material surrounding the TLD and used to ensure a charged particle equilibrium. These effects will depend on the isotopic composition of the surrounding material and its thickness, and on the incident neutron spectrum(1).21.4The values stated in SI units are to be regarded as standard.1.5This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======4.1Electronic devices are typically tested for device response to gamma radiation in pure gamma-ray fields. Testing electronic device response against neutrons is more complex since there is invariably a gamma-ray component in addition to the neutron field. The gamma-ray response of the electronic device is typically subtracted from the overall response to find the device response to neutrons. This approach to the testing requires a determination of the gamma-ray exposure in the mixed field. To enhance the neutron effects, the radiation field is sometimes selected to have as large a neutron component as possible.4.2CaF2(Mn) TLDs are often used to monitor the gamma-ray dose in mixed neutron/gamma radiation fields. Since the dosimeters are exposed along with the device under test to the mixed field, their response must be corrected for neutrons. In a field rich in neutrons, the uncertainty in the interpretation of the TLD response grows. In fields with relatively few neutrons, the total TLD response may be used to make a correction for gamma response of the device under test. Under this condition, the relative uncertainty in the TLD neutron response is not likely to drive the overall uncertainty in the correction to the electronic device response.4.3This practice gives a means of estimating the response of CaF2(Mn) TLDs to neutrons. This neutron response is then subtracted from the measured response to determine the TLD response due to gamma rays. The procedure has relatively high uncertainty because the neutron response of CaF2(Mn) TLDs may vary depending on the source of the material, and this procedure is a generic calculation applicable to CaF2(Mn) TLDs independent of their manufacturer/source. The neutron response given in this practice is a summary of CaF2(Mn) TLD responses reported in the literature. The associated uncertainty envelops the range of results reported and includes the variety of CaF2(Mn) TLDs used as well as the uncertainties in the determination of the neutron response as reported by various authors.4.4Should the user find the resulting uncertainties too large for his purposes, the neutron response of the CaF2(Mn) TLDs in use during the irradiations must be determined. This practice does not supply guidance on how to determine the neutron response of a specific batch of TLDs.4.5Neutron effects on electronics under test are usually reported in terms of 1-MeV(Si) equivalent fluence (PracticeE722). Neutron effects of TLDs, as discussed here, are reported in units of absorbed dose, since they are corrections to the gamma-ray dose.
9.[标准] Standard Terminology Relating to Radiation Measurements and Dosimetry

辐射测量和剂量测定相关的标准术语

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E170-23

发布时间：
2023-02-01

中标分类：
-

国标分类：
01.040.17 词汇 - 计量学和测量、物理现象 (词汇)

17.240 计量学和测量、物理现象 - 辐射测量

实施时间：
10.[标准] Standard Practice for Using the Fricke Dosimetry System

弗里克剂量测定系统的使用标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM 51026-23

发布时间：
2023-12-01

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This practice covers the procedures for preparation, testing, and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system.1.2This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice52628for the Fricke dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice52628.1.3The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system.1.4This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons.1.5This practice applies provided the following are satisfied:1.5.1The absorbed dose range shall be from 20 Gy to 400 Gy(1).21.5.2The absorbed dose rate does not exceed 106Gy·s−1(2).1.5.3For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV.Note 1:The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams(3). The Fricke dosimetry system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).1.5.4The irradiation temperature of the dosimeter should be within the range of 10 °C to 60 °C.1.6This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.7This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======4.1The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (ICRU 80, PIRS-0815,(4)). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (seeAppendix X3).4.2The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance.
11.[标准] Standard Practice for Field Use of Pyranometers, Pyrheliometers and UV Radiometers

日射强度计、日射强度仪和紫外线辐射计现场使用的标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM G183-15(2023)

发布时间：
2023-03-15

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This practice describes deployment conditions, maintenance requirements, verification procedures and calibration frequencies for use of pyranometers, pyrheliometers and UV radiometers in outdoor testing environments. This practice also discusses the conditions that dictate the level of accuracy required for instruments of different types.1.2While both pyranometers and UV radiometers may be employed indoors to measure light radiation sources, the measurement of ultraviolet and light radiation in accelerated weathering enclosures using manufactured light sources generally requires specialized radiometric instruments. Use of radiometric instrumentation to measure laboratory light sources is covered in ISO 9370.Note 1:An ASTM standard that is similar to ISO 9370 is under development and deals with the instrumental determination of irradiance and radiant exposure in weathering tests.1.3The characterization of radiometers is outside the scope of the activities required of users of radiometers, as contemplated by this standard.1.4This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
12.[标准] Standard Practice for Calibration and Usage of Germanium Detectors in Radiation Metrology for Reactor Dosimetry

反应堆剂量测定用辐射计量中锗探测器的校准和使用的标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E3376-23

发布时间：
2023-02-15

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This standard establishes techniques for calibration, usage, and performance testing of germanium detectors for the measurement of gamma-ray emission rates of radionuclides in radiation metrology for reactor dosimetry. The practice is applicable only to samples of small size, approximating to point sources. It covers the energy and full-energy peak efficiency calibration as well as the determination of gamma-ray energies in the 0.06 MeV to 2 MeV energy region and is designed to yield gamma-ray emission rates with an uncertainty of ±3 % (seeNote 1). This technique applies to measurements that do not involve overlapping peaks, and in which peak-to-continuum considerations are not important.Note 1:UncertaintyUis given at the 68 % confidence level; that is,where δiare the estimated maximum systematic uncertainties, and σiare the random uncertainties at the 68 % confidence level. Other techniques of error analysis are in use(1,2).21.2Additional information on the setup, calibration, and quality control for radiometric detectors and measurements is given in IEEE/ANSI N42.14 and in GuideC1402and PracticeD7282.1.3The values stated in SI units are generally to be regarded as standard. The rad is an exception.1.4This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.5This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======5.1High-purity germanium detectors are used for precise gamma-ray spectroscopy for the purpose of determining radioactivity in materials. Typical applications include monitoring, mapping, and characterization of neutron energy spectra in nuclear reactors or isotopic fission sources.
13.[标准] Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry

反应堆剂量测定用辐射计量中放射性核素的探测器校准和分析的标准指南

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E181-23

发布时间：
2023-02-15

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This guide covers general procedures for the calibration of radiation detectors and measurement for radiation metrology for reactor dosimetry. For any particular radionuclide, one or more of these methods may apply.1.2These techniques are concerned only with specific radionuclide measurements. The chemical and physical properties of the radionuclides are not within the scope of this standard.1.3E3376, Standard Practice for Calibration and Usage of Germanium Detectors in Radiation Metrology for Reactor Dosimetry, was previously in Guide E181 and is now found in Volume 12.02 of theAnnual Book of ASTM Standards. The discussion herein is not a sufficient substitute for the full standard. This guide is specifically NOT to be used as a direct reference to PracticeE3376. Only the standard listed provides sufficient information to serve as a reference.1.4Additional information on the setup, calibration, and quality control for radiometric detectors and measurements is given in GuideC1402and PracticeD7282.1.5The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.6This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.7This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
14.[标准] Standard Practice for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

用钴和银的放射性测定中子通量率的标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E481-23

发布时间：
2023-06-01

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

27.120.30 核能工程 - 裂变物质

实施时间：

摘要： 1.1This practice covers a suitable means of obtaining the thermal neutron fluence rate, or fluence, in nuclear reactor environments where the use of cadmium, as a thermal neutron shield as described in Test MethodE262, is undesirable for reasons such as potential spectrum perturbations or due to temperatures above the melting point of cadmium.1.2The reaction59Co(n,γ)60Co results in a well-defined gamma emitter having a half-life of 5.2711 years2(8)3(1).4The reaction109Ag(n,γ)110mAg results in a nuclide with a well-known, complex decay scheme with a half-life of 249.78 (2) days(1). Both cobalt and silver are available either in very pure form or alloyed with other metals such as aluminum. A reference source of cobalt in aluminum alloy to serve as a neutron fluence rate monitor wire standard is available from the National Institute of Standards and Technology (NIST) as Standard Reference Material (SRM) 953.5The competing activities from neutron activation of other isotopes are eliminated, for the most part, by waiting for the short-lived products to die out before counting. With suitable techniques, thermal neutron fluence rate in the range from 108cm−2·s−1to 3 × 1015cm−2·s−1can be measured. Two calculational practices are described in Section9for the determination of neutron fluence rates. The practice described in9.3may be used in all cases. This practice describes a means of measuring a Westcott neutron fluence rate in9.2(Note 1) by activation of cobalt- and silver-foil monitors (see TerminologyE170). For the Wescott Neutron Fluence Convention method to be applicable, the measurement location must be well moderated and be well represented by a Maxwellian low-energy distribution and an (1/E) epithermal distribution. These conditions are usually only met in positions surrounded by hydrogenous moderator without nearby strongly multiplying or absorbing materials.Note 1:Westcott fluence rate1.3The values stated in SI units are to be regarded as the standard, except in the case of nuclear data where the source referenced units are retained in order to preserve the integrity of the referenced uncertainty values.1.4This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.5This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======3.1This practice uses one monitor (cobalt) with a nearly 1/vabsorption cross-section curve and a second monitor (silver) with a large resonance peak so that its resonance integral is large compared to its thermal cross section. The pertinent data for these two reactions are given inTable 1. The equations are based on the Westcott formalism ((2,3)and PracticeE261) and determine a Westcott 2200 m/s neutron fluence ratenv0and the Westcott epithermal index parameter. References(4-6)contain a general discussion of the two-reaction test method. In this practice, the absolute activities of both cobalt and silver monitors are determined. This differs from the test method in the references wherein only one absolute activity is determined.(A)The numbers in parentheses following given values are the uncertainty in the last digit(s) of the value; 0.729 (8) means 0.729 ± 0.008, 70.8(1) means 70.8 ± 0.1.(B)The decay constant, λ, is defined as ln(2) / t1/2with units of sec–1, where t1/2is the nuclide half-life in seconds.(C)Calculated usingEq 10.(D)InFig. 1, Θ = 4ErkT/AΓ2= 0.2 corresponds to the value for109Ag forT= 293 K,∑r= N0σr,max,T=0Kσr,max,T=0K= 31138.03 barn at 5.19 eV(13). The value of σr,max,T=0K= 31138.03 barns is calculated using the Breit-Wigner single-level resonance formulawhere the109Ag atomic mass is A = 108.9047558 amu(14), the ENDF/B-VIII.0 (MAT = 4731)(13)resonance parameters are: resonance total width Γ = 0.1427333 eV, formation neutron width Γn= 0.0127333 eV, and radiative/decay width Γγ= 0.13 eV, with a resonance spin J=1, and the statistical spin factorwhere s1=1/2and s2=1/2are the spins of the two particles (neutron and109Ag ground state(15)) forming resonance.3.2The advantages of this approach are the elimination of four difficulties associated with the use of cadmium: (1) the perturbation of the field by the cadmium; (2) the inexact cadmium cut-off energy; (3) the low melting temperature of cadmium; and (4) the potential for high dose-rate encountered when handling activated cadmium. In addition, the reactivity changes accompanying the rapid insertion and removal of cadmium may prohibit the use of the cadmium-ratio method. Self-shielding corrections are only important if the concentrations of cobalt and silver are large, but may be neglected for diluted alloys (<1 %). Studies indicate that the accuracy of the two-reaction method for determination of thermal neutron fluence is comparable to the cadmium-ratio method(16).3.3The long half-lives of the two monitors permit the determination of fluence for long-term monitoring.
15.[标准] Standard Practices for the Measurement of Radioactivity

放射性测量的标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM D3648-23

发布时间：
2023-06-01

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1These practices cover a review of the accepted counting practices currently used in radiochemical analyses. The practices are divided into four sections:SectionGeneral Information6 –11Alpha Counting12 –22Beta Counting23 –33Gamma Counting34 –411.2The general information sections contain information applicable to all types of radioactive measurements, while each of the other sections is specific for a particular type of radiation.1.3The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.4This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.5This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======5.1This practice was developed for the purpose of summarizing the various generic radiometric techniques, equipment, and practices that are used for the measurement of radioactivity.
16.[标准] Standard Practice for Screening of Waste for Radioactivity

放射性废物筛选的标准实施规程

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM D5928-23

发布时间：
2023-11-01

中标分类：
-

国标分类：
13.030.30 废物 - 特殊废物

17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： 1.1This practice covers the screening for α–, β–, and γ radiation above ambient background levels or user-defined criteria, or both, in liquid, sludge, or solid waste materials.1.2This practice is intended to be a gross screening method for determining the presence or absence of radioactive materials in liquid, sludge, or solid waste materials. It is not intended to replace more sophisticated quantitative analytical techniques, but to provide a method for rapidly screening samples for radioactivity above ambient background levels or user-defined criteria, or both, for facilities prohibited from handling radioactive waste.1.3This practice may or may not be suitable for applications such as site assessments and remediation activities, depending on the data quality objectives or intended use.1.4The values stated in SI units are to be regarded as the standard.1.5This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.6This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======5.1Most facilities disposing or using waste materials are prohibited from handling wastes that contain radioactive materials. This practice provides the user a rapid method for screening waste material for the presence or absence of radioactivity at user-established levels that consider background radiation and the intended use of the screening method. It is important to these facilities to be able to verify generator-supplied information in regard to radiation and to meet worker health and safety needs.
17.[标准] Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

用铝的放射性测定快中子反应率的标准试验方法

发布单位：
美国-美国材料与试验协会(US-ASTM)

标准状态：
现行

标准号：
ASTM E266-23

发布时间：
2023-06-01

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

27.120.30 核能工程 - 裂变物质

实施时间：

摘要： 1.1This test method covers procedures measuring reaction rates by the activation reaction27Al(n,α)24Na.1.2This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times up to about two days (for longer irradiations, or when there are significant variations in reactor power during the irradiation, see PracticeE261).1.3With suitable techniques, fission-neutron fluence rates above 106cm−2·s−1can be determined.1.4Detailed procedures for other fast neutron detectors are referenced in PracticeE261.1.5This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.6This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ======5.1Refer to GuideE844for the selection, irradiation, and quality control of neutron dosimeters.5.2Refer to PracticeE261for a general discussion of the determination of fast-neutron fluence rate with threshold detectors.5.3Pure aluminum in the form of foil or wire is readily available and easily handled.27Al has an abundance of 100 %(1).35.424Na has a half-life of 14.958 (2)4h(2)and emits gamma rays with energies of 1.368630 (5) and 2.754049 (13) MeV(2).5.5Fig. 1shows a plot of the International Reactor Dosimetry and Fusion File (IRDFF-II) cross section(3,4)versus neutron energy for the fast-neutron reaction27Al(n,α)24Na(3)along with a comparison to the current experimental database(5,6). While the RRDF-2008 and IRDFF-1.05 cross sections extend from threshold up to 60 MeV, due to considerations of the available validation data, the energy region over which this standard recommends use of this cross section for reactor dosimetry applications only extends from threshold at ~4.25 MeV up to 20 MeV. This figure is for illustrative purposes and is used to indicate the range of response of the27Al(n,α) reaction. Refer to GuideE1018for recommended sources for the tabulated dosimetry cross sections.FIG. 127Al(n,α)24Na Cross Section, from IRDFF-II Library, with EXFOR Experimental Data5.6Two competing activities,28Al (2.25 (2) minute half-life) and27Mg (9.458 (12) minute half-life), are formed in the reactions27Al(n,γ)28Al and27Al(n,p)27Mg, respectively, but these can be eliminated by waiting 2 h before counting.
18.[标准] Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

核能基准β粒子辐射第3部分:面积和个人剂量计的校准及其作为β辐射能量和入射角函数的响应的测定

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 6980-3:2023

发布时间：
2023-11-22

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10？mm of tissue (Emax？？2？MeV).This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters with beta-reference radiation and determine their response as a function of beta-particle energy and angle of incidence. Such measurements can represent part of a type test during the course of which the effect of other influence quantities on the response is examined. This document does not cover the in-situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description of calibration procedures, this document includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.
19.[标准] Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production

核能基准β粒子辐射第1部分:生产方法

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 6980-1:2023

发布时间：
2023-11-17

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

实施时间：

摘要： This document specifies the requirements for reference beta radiation fields produced by radioactive sources to be used for the calibration of personal and area dosemeters and dose-rate meters to be used for the determination of the quantities Hp(0,07), H'(0,07;Ω), Hp(3) and H'(3;Ω), and for the determination of their response as a function of beta particle energy and angle of incidence. The basic quantity in beta dosimetry is the absorbed-dose rate in a tissue-equivalent slab phantom. This document gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07？mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 0,22？MeV and 3,6？MeV maximum beta energy corresponding to 0,07？MeV to 1,2？MeV mean beta energy and the dose equivalent rates are in the range from about？10？μSv·h-1 to at least 10？Sv·h-1.. In addition, for some sources, variations of the dose equivalent rate as a function of the angle of incidence are given. However, as noted in ICRU？56[5], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10？mm of tissue (Emax？？2？MeV).This document is applicable to two series of reference beta radiation fields, from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.Series？1 reference radiation fields are produced by radioactive sources used with beam-flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 106Ru/106Rh, 90Sr/90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately？200？mSv·h–1.Series？2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this series has the advantage of extending the energy and dose rate ranges beyond those of series？1. The series also include radiation fields using polymethylmethacrylate (PMMA) absorbers to reduce the maximum beta particle energy. The radionuclides used are those of series？1; these sources produce dose equivalent rates of up to？10？Sv·h–1.
20.[标准] Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation

环境中放射性的测量.使用环境监测数据进行有效剂量评估的指南.第2部分:紧急暴露情况

发布单位：
国际组织-国际标准化组织(IX-ISO)

标准状态：
现行

标准号：
ISO 20043-2:2023

发布时间：
2023-07-07

中标分类：
-

国标分类：
17.240 计量学和测量、物理现象 - 辐射测量

13.280 环保、保健和安全 - 辐射防护

实施时间：

摘要： These international guidelines are based on the assumption that monitoring of environmental components (atmosphere, water, soil and biota) as well as food quality is performed to ensure the protection of human health[5][7][8][9][10][11][12]. The guidelines constitute a basis for the setting of national regulations, standards, and inter alia, for monitoring air, water and food in support of public health, specifically to protect the public from ionizing radiation.This document provides:—？guidance to collect data needed for the assessment of human exposure to radionuclides naturally present or discharged by anthropogenic activities in the different environmental compartments (atmosphere, waters, soils, biota) and food;—？guidance on the environmental characterization needed for the prospective and/or retrospective dose assessment methods of public exposure;—？guidance that addresses actions appropriate for an event involving uncontrolled releases of gamma-emitters (e.g. nuclear power reactor emergencies) and also events that would involve beta- or alpha-emitters would require additional consideration of the pathways, instrumentation, laboratory analysis, operational intervention levels, protective actions, etc., appropriate to their release;—？guidance for staff in nuclear installations responsible for the preparation of radiological assessments in support of permit or authorization applications and National Authorities’ officers in charge of the assessment of doses to the public for the purposes of determining gaseous or liquid effluent radioactive discharge authorizations;—？information to the public on the parameters used to conduct a dose assessment for any exposure situations to a representative person/population. It is important that the dose assessment process be transparent, and that assumptions are clearly understood by stakeholders who can participate in, for example, the selection of habits of the representative person to be considered.This document refers to various published ISO documents. When appropriate, this document also refers to national standards or other publicly available documents.