17.240 辐射测量 标准查询与下载

ASTM 51275-21 辐射铬膜剂量测定系统的使用标准实施规程

Standard Practice for Use of a Radiochromic Film Dosimetry System

DIN EN ISO 4037-1 Berichtigung 1:2021 辐射防护 用于校准剂量计和剂量率计并确定它们作为光子能量函数的响应的 X 和伽马参考辐射 第1部分：辐射特性和生产方法（ISO 4037-1:2019）；德语

The corrigendum to DIN EN ISO 4037-1 (VDE 0412-4037-1):2021-07 changes a value in 4.5.1, 4th paragraph.

Radiological protection - X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 1: Radiation characteristics and production methods (ISO 4037-1:2019); German

UNI EN ISO 10703:2021 水质 发射伽马射线的放射性核素 使用高分辨率伽马射线光谱仪的测试方法

Water quality - Gamma-ray emitting radionuclides - Test method using high resolution gamma-ray spectrometry.

UNI EN ISO 13160:2021 水质 锶 90 和锶 89 使用液体闪烁计数或比例计数的测试方法

Water quality - Strontium 90 and strontium 89 - Test methods using liquid scintillation counting or proportional counting

KS A 4314-2021 放射光致发光玻璃剂量计系统

Radiophotoluminescent glass dosimeter systems

KS A 4724-2021 室内环境监测薄膜徽章

Film badge for in－door environmental monitoring

KS A ISO 6980-2-2021 核能 参考 β 粒子辐射 第2部分：与表征辐射场的基本量相关的校准原理

Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field

KS A ISO 6980-3-2021 核能 参考 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确定

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

KS A 4321-2021 辐射探测用铊激活碘化钠闪烁体

Thallium－activated sodium iodide scintillator for radiation detection

KS A ISO 8769-2021 参考源 表面污染监测仪的校准 α、β和光子发射器

Reference sources－Calibration of surface contamination monitors－Alpha-, beta- and photon emitters

KS A 4610-2021 用于辐射防护的便携式光子环境剂量当量率计

Portable photon ambient dose equivalent ratemeters for radiation protection

UNI EN ISO 18589-1:2021 环境中放射性的测量 土壤 第1部分：一般准则和定义

Measurement of radioactivity in the environment - Soil - Part 1: General guidelines and definitions

LST EN ISO 10703:2021 水质 发射伽马射线的放射性核素 使用高分辨率伽马射线光谱仪的测试方法（ISO 10703:2021）

Water quality - Gamma-ray emitting radionuclides - Test method using high resolution gamma-ray spectrometry (ISO 10703:2021)

NF C42-020-2-061*NF EN IEC 61010-2-061:2021 测量、控制和实验室用电气设备的安全要求. 第2-061部分: 具有热雾化和电离的实验室原子光谱仪的特殊要求

Safety requirements for electrical equipment for measurement, control and laboratory use - Part 2-061 : particular requirements for laboratory atomic spectrometers with thermal atomization and ionization

ASTM E1005-21 反应堆容器监测用辐射监测器的应用和分析的标准试验方法

1.1 This test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5).2 The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29). 1.1.1 The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26). 1.1.2 Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (2-5, 28-30). 1.1.3 Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs (2-5, 28-30). 1.1.4 The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (2-5, 28-30). 1.2 This test method is intended to be used in conjunction with ASTM Guide E844 and existing or proposed ASTM practices, guides, and test methods that are also directly involved in the physics-dosimetry evaluation of reactor vessel and support structure surveillance measurements. 1.3 The procedures in this test method are applicable to the measurement of radioactivity in RMs that satisfy the specific constraints and conditions imposed for their analysis. More detailed procedures for individual RM monitors are identified in 2.1 and in Refs 1-5 (see Table 1). 1.4 This test method, along with the individual RM monitor standard methods, are intended for use by knowledgeable persons who are intimately familiar with the procedures, equipment, and techniques necessary to achieve high precision and accuracy in radioactivity measurements. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard, except for the energy units based on the electron volt, keV and MeV, and the time units: minute (min), hour (h), day (d), and year (a). 1.6 This 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. 1.7 This 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. 1 This test method is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05 on Nuclear Radiation Metrology. Current edition approved Sept. 1, 2021. Published November 2021. Originally approved in 1997. Last previous edition approved in 2016 as E1005 – 16. DOI: 10.1520/E1005-21. 2 The boldface numbers in parentheses refer to the list of references appended to this method. Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States This 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. 1 TABLE 1 Radiometric Monitors Proposed for Reactor Vessel Surveillance Dosimetry Reactions Residual Nucleus Target Atom Natural AbundanceA Ref (31) Detector ResponseB ASTM Standard or Ref Half-lifeC,A,D Eγ D (keV) YieldD (%) γ/Reaction 23 Na(n,γ)24 Na 14.958 (2) h 1368.630 (5) 99.9934 (5) 1.00 NTR (2-5, 28-32) 2754.049 (13) 99.862 (3) 27 Al(n,α)24 Na 14.958 (2) h 1368.630 (5) 99.9934 (5) 1.00 TR (32) E266 2754.049 (13) 99.862 (3) 32 S(n,p)32 P 14.284 (36) d =695.5 (3) 100.0 0.9499 (26) TR E265 45 Sc(n,γ)46 Sc 83.787 (16) d 889.271 (2) 99.98374 (25) 1.00 NTR (2-5, 28-32) 1120.537 (3) 99.97 (2) 46 Ti(n,p)46 Sc 83.787 (16) d 889.271 (2) 99.98374 (25) 0.0825 (3) NTR (32) E526 1120.537 (3) 99.97 (2) 47 Ti(n,p)47 Sc 3.3485 (9) d 159.373 (12) 68.1 (5) 0.0744 (2) TR E526 48 Ti(n,p)48 Sc 43.67 (9) h 983.526 (12) 100.0 (3) 0.7372 (3) TR E526 1037.522 (12) 97.5 (5) 1312.120 (12) 100.0 (5) 55 Mn(n,2n)54 Mn 312.19 (3) d 834.848 (3) 99.752 (5) 1.00 TR E261, E263 (2-5, 28-30) 54 Fe(n,p)54 Mn 312.19 (3) d 834.848 (3) 99.752 (3) 0.05845 (35) TR E263 54 Fe(n,γ)55 Fe 2.747 (8) a 5.88765 8.45 (14) 0.05845 (35) NTR (2-5, 28-30) 5.89875 16.57 (27) 6.49045 3.40 (7) 56 Fe(n,p)56 Mn 2.57878 (46) h 846.7638 (19) 98.85 (3) 0.91754 (36) TR (2-5, 28-30) 1810.726 (4) 26.9 (4) 2113.092 (6) 14.2 (3) 58 Fe(n,γ)59 Fe 44.494 (12) d 1099.245 (3) 56.51 (31) 0.00282 (4) NTR (2-5, 28-30) 1291.590 (6) 43.23 (33) 1481.70 (12) 0.059 (6) 59 Co(n,γ)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 1.00 NTR E262, E481 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 58 Ni(n,p)58 Co 70.85 (3) d 810.7602 (20) 99.44 (2) 0.68077 (9) TR E264 863.958 (6) 0.700 (22) 1674.705 (6) 0.528 (13) 9.10 (9) h (meta) 24.889 (21) 0.0397 (6) 60 Ni(n,p)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 0.26223 (8) TR (2-5, 28-30) 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 63 Cu(n,γ)64 Cu 12.7004 (20) h 1345.77 (6) 0.4748 (34) 0.6915 (15) NTR (2-5, 28-30) 63 Cu(n,α)60 Co 5.2711 (8) a 1173.228 (3) 99.85 (3) 0.6915 (15) TR E523 1332.492 (4) 99.9826 (6) 10.467 (6) min 58.603 (7) 2.07 (3) (meta) 826.10 (3) 0.00775 (3) 1332.492 (4) 0.25 (3) 2158.57 (3) 0.00075 (3) 93 Nb(n,n')93m Nb 16.12 (15) a 30.77 (2) 0.000591 (9) 1.00 TR (1-5, 28-30) 16.52 (Kα1,2) 9.25 103 Rh(n,n')103m Rh 56.114 (20) min 39.755 (12) 0.0684 (35) 1.00 TR (2-5, 28-30) 109 Ag(n,γ)110m Ag 249.78 (2) d 116.48 (5) 0.0080 (3) 0.48161 (8) NTR E481 884.6781 (13) 74.0 (12) E1005 − 21 2 TABLE 1 Continued Dosimetry Reactions Residual Nucleus Target Atom Natural AbundanceA Ref (31) Detector ResponseB ASTM Standard or Ref Half-lifeC,A,D Eγ D (keV) YieldD (%) γ/Reaction 937.485 (3) 34.51 (27) 1384.2931 (20) 24.7 (5) 1475.7792 (23) 4.03 (5) 1505.028 (2) 13.16 (16) 115 ln(n,γ)116m ln 54.29 (17) min 1293.56 (2) 84.8 0.9571 (5) NTR E261, E262 1097.28 (2) 58.512 818.68 (2) 12.126 2112.29 (2) 15.094 115 ln(n,n')115m ln 4.486 (4) h 336.241 (25) 45.9 (1) 0.9571 (5) TR (2-5, 28-30) 497.370 (29) 0.047 (1) 181 Ta(n,γ)182 Ta 114.61 (13) d 1121.290 (3) 35.17 (33) 0.9998799 (32) NTR E262 1189.040 (3) 16.58 (16) 1221.395 (3) 27.27 (27) 197 Au(n,γ)198 Au 2.6943 (3) d 1087.6842 (7) 0.1591 (21) 1.00 NTR E261, E262 675.8836 (7) 0.804 (5) (2-5, 28-30) 411.80205 (17) 95.62 (6) 232 Th(n,γ)233 Th 22.15 (8) min 890.1 (5) 0.1052 (14) 1.00 NTR (2-5, 28-30) 490.80 (6) 0.1078 (16) 499.02 (4) 0.1576 (21) 699.901 0.68 764.55 (6) 0.0891 (13) 233 Th⇒233 Pa 26.98 (2) d 311.904 (5) 38.3 (5) FM(n,f)144 Ce 284.89 (6) d 133.5152 (20) 10.83 (12) —E NTR, TR E704, E705 80.120 (4) 1.40 (5) (2-5, 28-30) (see Table 2) FM(n,f)140 Ba 12.753 (5) d 537.261 (25) 24.6 (5) —E NTR, TR E393, E704, (see Table 2) E705 140 Ba⇒140 La 1.67858 (21) d 1596.203 (13) 95.40 (5) (2-5, 28-30) 815.784 (6) 23.72 (20) 487.022 (6) 46.1 (5) (see Table 2) FM(n,f)137 Cs 30.05 (8) a 661.657 (3) 84.99 (20) —E NTR, TR E704, (see Table 2) E705 137 Cs⇒137m Ba 2.552 (1) min 661.657 (3) 90.07 (20) (2-5, 28-30) (see Table 2) FM(n,f)106 Ru 371.5 (21) d — — —E NTR, TR E704, E705 (see Table 2) (2-5, 28-30) 106 Ru⇒106 Rh 30.1 (3) s 511.8534 (23) 20.52 (23) (see Table 2) FM(n,f)103 Ru 39.247 (13) d 497.085 (10) 91.0 —E NTR, TR E704, E705 (see Table 2) (2-5, 28-30) FM(n,f)95 Zr 64.032 (6) d 756.729 (12) 54.38 (22) —E NTR, TR E704, E705 724.193 (3) 44.27 (22) (2-5, 28-30) (see Table 2) 95 Zr⇒95 Nb 34.991 (6) d 765.803 (6) 99.808 (7) (see Table 2) A The numbers in parentheses following some given values is 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 NTR = Non-Threshold Response, TR = Threshold Response. C The time units listed for half-life are years (a), days (d), hours (h), minutes (min), and seconds (s). Note that a “year” herein is considered to be tropical and equivalent to 365.242 days and thus equivalent to 31.556.926 s per Ref (32). D The nuclear data has been drawn from several primary sources including Refs (32-35). Reference (36) summarizes the source of the selected nuclear constants, last checked for consistency on March 19, 2014. E FM = Fission Monitor: 235 U and 239 Pu (NTR) and 238 U, 237 Np, and 232 Th (TR) target isotope or weight fraction varies with material batch. E1005 − 21 3 2. Referenced Documents

Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

ASTM E261-16(2021) 用放射性技术测定中子注量、注量率和光谱的标准实施规程

1.1 This practice describes procedures for the determination of neutron fluence rate, fluence, and energy spectra from the radioactivity that is induced in a detector specimen. 1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials. 1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E1005. 1.4 This 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. NOTE 1—Detailed methods for individual detectors are given in the following ASTM test methods: E262, E263, E264, E265, E266, E343, E393, E481, E523, E526, E704, E705, and E854. 1.5 This 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.

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

LST EN ISO 13162:2021 水质 碳 14 使用液体闪烁计数的测试方法（ISO 13162:2021）

Water quality - Carbon 14 - Test method using liquid scintillation counting (ISO 13162:2021)

LST EN ISO 22515:2021 水质 Iron-55 使用液体闪烁计数的测试方法（ISO 22515:2021）

Water quality - Iron-55 - Test method using liquid scintillation counting (ISO 22515:2021)

ASTM E3270-21 γ辐照器操作鉴定的标准指南

1.1 This document provides guidance on operational qualification (OQ) tests to meet the OQ requirements defined in ISO 11137-1, ISO 14470, ISO/ASTM 51702, and ISO/ASTM 52303 for gamma irradiators. 1.1.1 The types of OQ tests are discussed to help the user gain an increased understanding of operational aspects of their irradiator and determine which OQ tests are appropriate for the assessment of irradiator change. 1.1.2 The facility should assess the rationale for the OQ tests chosen and for the ones that have been deemed to be unnecessary. 1.2 Specific requirements for OQ are dependent on the application of the irradiation process and are not within the scope of this guide. For example, requirements for OQ when sterilizing healthcare products can be found in ISO 11137-1. 1.3 A change to the irradiator is a component of the change control process. The OQ testing following the irradiator change is determined as part of the change control documentation and should include rationale to support decision(s) on which tests are required to be completed. 1.4 For an OQ study following an irradiator change, the required OQ tests are defined procedurally with established acceptance criteria. (The OQ tests in the appendixes have examples of defined acceptance criteria with a rationale for the acceptance.) When multiple tests are used in the assessment of change, no individual OQ test should be solely relied upon; rather, the composite of OQ test results should be used to help provide a clear justification for the conclusion regarding irradiator change. 1.5 Many calculations in this guide were completed using Microsoft Excel (for example, ANOVA, t-test, p-value), but numerous other software tools are commercially available. 1.6 This 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. 1.7 This 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.

Standard Guide for Operational Qualification of Gamma Irradiators

OENORM EN ISO 4037-1:2021 放射防护 用于校准剂量计和剂量率计并确定它们作为光子能量函数的响应的 X 和伽马参考辐射 第1部分：辐射特性和生产方法（ISO 4037-1:2019）

Radiological protection - X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 1: Radiation characteristics and production methods (ISO 4037-1:2019)