17.240 辐射测量 标准查询与下载

ASTM 51707-22 辐射处理用剂量测定中测量不确定度估计的标准指南

Standard Guide for Estimation of Measurement Uncertainty in Dosimetry for Radiation Processing

ASTM ISO/ASTM51608-15(2022) 能量在50keV和7.5MeV之间的辐射处理用X射线（轫致辐射）设施中剂量测定的标准实施规程

Standard Practice for Dosimetry in an X-Ray (Bremsstrahlung) Facility for Radiation Processing at Energies between 50 keV and 7.5 MeV

ASTM ISO/ASTM 51608-15(2022) 能量在50keV和7.5MeV之间的辐射处理用X射线（轫致辐射）设施中剂量测定的标准实施规程

1.1 This practice outlines the dosimetric procedures to be followed during installation qualification, operational qualification, performance qualification and routine processing at an X-ray (bremsstrahlung) irradiator. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed. NOTE 1—Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications. NOTE 2—ISO/ASTM Practices 51649, 51818 and 51702 describe dosimetric procedures for electron beam and gamma facilities for radiation processing. 1.2 For radiation sterilization of health care products, see ISO 11137-1, Sterilization of health care products – Radiation – Part 1: Requirements for development, validation and routine control of a sterilization process for medical devices. In those areas covered by ISO 11137-1, that standard takes precedence. 1.3 For irradiation of food, see ISO 14470, Food irradiation – Requirements for development, validation and routine control of the process of irradiation using ionizing radiation for the treatment of food. In those areas covered by ISO 14470, that standard takes precedence. 1.4 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628, “Practice for Dosimetry in Radiation Processing”. 1.5 In contrast to monoenergetic gamma radiation, the X-ray energy spectrum extends from low values (about 35 keV) up to the maximum energy of the electrons incident on the X-ray target (see Section 5 and Annex A1). 1.6 Information about effective or regulatory dose limits and energy limits for X-ray applications is not within the scope of this practice. 1.7 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Dosimetry in an X-Ray (Bremsstrahlung) Facility for Radiation Processing at Energies between 50 keV and 7.5 MeV

22/30394888 DC BS ISO 20956 辐射防护 环境和区域监测仪器的低剂量率校准

BS ISO 20956. Radiological protection. Low dose rate calibration of instruments for environmental and area monitoring

BS ISO 6980-3:2022 核能 参考 β 粒子辐射 区域和个人剂量计的校准以及确定其响应随 β 辐射能量和入射角的变化

1   Scope This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the International Commission on Radiation Units and Measurements (ICRU) operational quantities for radiation protection purposes. However, as noted in ICRU 56 [ 2 ] , the ambient dose equivalent, H *(10), used for area monitoring, and the personal dose equivalent, H p (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 ( E max  > 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.

Nuclear energy. Reference beta-particle radiation - Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

BS ISO 6980-2:2022 核能 参考 β 粒子辐射 与表征辐射场的基本量相关的校准基础

1   Scope This document specifies methods for the measurement of the absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,22 MeV to 3,6 MeV maximum beta energy corresponding to 0,06 MeV to 1,1 MeV mean beta energy . Radiation energies outside this range are beyond the scope of this document. While measurements in a reference geometry (depth of 0,07 mm or 3 mm at perpendicular incidence in a tissue‑equivalent slab phantom ) with an extrapolation chamber used as primary standard are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. However, as noted in ICRU 56 [ 5 ] , the ambient dose equivalent, H *(10), used for area monitoring, and the personal dose equivalent, H p (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 ( E max  > 2 MeV). This document is intended for those organizations wishing to establish primary dosimetry capabilities for beta particles and serves as a guide to the performance of dosimetry with an extrapolation chamber used as primary standard for beta‑particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.

Nuclear energy. Reference beta-particle radiation - Calibration fundamentals related to basic quantities characterizing the radiation field

BS ISO 6980-1:2022 核能 参考β粒子辐射 生产方法

1   Scope 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 H p (0,07), H' (0,07; Ω ), H p (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 and 3,6 MeV maximum beta energy corresponding to 0,06 MeV to 1,1 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 Report 56 [ 3 ] , the ambient dose equivalent, H *(10), used for area monitoring, and the personal dose equivalent, H p (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 ( E max  > 2 MeV).

Nuclear energy. Reference beta-particle radiation. Methods of production

DB33/T 2553-2022 电磁辐射环境自动监测技术规范

Electromagnetic radiation environment automatic monitoring technical specification

ISO 6980-3:2022 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测定

This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the International Commission on Radiation Units and Measurements (ICRU ) operational quantities for radiation protection purposes . However, as noted in ICRU 56 [2], 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 (Ema x > 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 fi xed, ins talled 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 .

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 inc

ISO 6980-2:2022 核能.参考β粒子辐射.第2部分:与表征辐射场的基本量有关的校准基本原理

This document specifies methods for the measurement of the absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta- particle-emitting isotopes covered by these reference radiations is 0,22 MeV to 3,6 MeV maximum beta energy corresponding to 0,06 MeV to 1,1 MeV mean beta energy. Radiation energies outside this range are beyond the scope of this document. While measurements in a reference geometry (depth of 0,07 mm or 3 mm at perpendicular incidence in a tissue-equivalent slab phantom) with an extrapolation chamber used as primary standard are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. 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 foranybeta radiation, even thatwhich penetrates 10 mm oftissue (Emax > 2 MeV). This document is intended for those organizations wishing to establish primary dosimetry capabilities for beta particles and serves as a guide to the performance of dosimetry with an extrapolation chamber used as primary standard for beta-particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.

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

ISO 6980-1:2022 核能.参考β粒子辐射.第1部分:生产方法

Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production

ISO/FDIS 20045 环境中放射性的测量“空气：氚”使用鼓泡取样的测试方法

Measurement of the radioactivity in the environment – Air: tritium – Test Method using bubbler sampling

BS ISO 11929-4:2022 电离辐射测量特征限值（决策阈值、检测限值和覆盖区间限值）的确定 基础知识和应用 第4部分：应用指南

1   Scope This document specifies a procedure, in the field of ionizing radiation metrology, for the calculation of the “decision threshold”, the “detection limit” and the “limits of the coverage interval” for a non‑negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. The measurand results from a gross count rate and a background count rate as well as from further quantities on the basis of a model of the evaluation. In particular, the measurand can be the net count rate as the difference of the gross count rate and the background count rate, or the net activity of a sample. It can also be influenced by calibration of the measuring system, by sample treatment and by other factors. ISO 11929 has been divided into four parts covering elementary applications in ISO 11929‑1, advanced applications on the basis of the ISO/IEC Guide 98‑3:2008/Suppl.1 in ISO 11929‑2, applications to unfolding methods in ISO 11929‑3, and guidance to the application in ISO 11929‑4. ISO 11929‑1 covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98‑3 (JCGM 2008). In ISO 11929‑1:2019, Annex A the special case of repeated counting measurements with random influences and in ISO 11929‑1:2019, Annex B, measurements with linear analogous ratemeters are covered. ISO 11929‑2 extends ISO 11929‑1 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98‑3:2008/Suppl.1. ISO 11929‑2 also presents some explan...

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application - Part 4: Guidelines to applications

22/30456241 DC BS ISO 8529-3 中子参考辐射场 第 3 部分：面积和个人剂量计的校准及其作为中子能量和入射角函数的响应的确定

BS ISO 8529-3. Neutron reference radiation fields - Part 3. Calibration of area and personal dosemeters and determination of their response as a function of neutron energy and angle of incidence

IEC 62232:2022 为评估人体暴露而确定基站附近的射频场强、功率密度和 SAR

Determination of RF field strength, power density and SAR in the vicinity of base stations for the purpose of evaluating human exposure

T/CAB 0181-2022 硅酸镥和硅酸钇镥闪烁单晶特性参数测量方法

本文件规定了硅酸镥（LSO）和硅酸钇镥（LYSO）闪烁单晶的中子灵敏度测量、固有幅度分辨率测量、闪烁衰减时间测量、伽马灵敏度测量和温度效应等晶体特性参数的测量方法。

The methods of measuring on characteristic parameters of both LYSO and LSO scintillators

T/CAB 0180-2022 GAGG晶体及晶片阵列性能测量方法

本文件规定了掺铈钆铝镓石榴石（Cerium-doped Gadolinium Aluminum Gallium Garnet，Gd3Al2Ga3O12，英文缩写GAGG）晶体及晶片阵列外观及几何特性（外观、尺寸、翘曲度、总厚度偏差、表面粗糙度、垂直度、平行度等）的检测方法，以及辐射特性（光输出、相对能量转换效率、闪烁光衰减长度、发射光谱、闪烁余辉时间、晶体阵列的心角比等）的测量方法。

Measurement method for characteristic parameters of GAGG crystal and crystal array

T/SXQCA 002-2022 利用医用数字X射线摄影(DR)设备实施热释光探测器分散度筛选操作方法

本文件规定了利用医用数字X射线摄影(DR)设备作为辐射源，实施热释光探测器分散度筛选的术语和定义、测量设备、筛选方法等内容和要求。 本文件适用于测量X、γ射线的圆片状热释光探测器使用过程中的分散度筛选。本文件不适用于热释光探测器出厂前进行的分组筛选。

Using digital photography (DR) equipment to implement the dispersion screening method of thermoluminescencedetectors

T/SXQCA 003-2022 工业脉冲X射线发生装置放射防护检测与评价方法

本文件规定了利用热释光法对工业脉冲X射线发生装置工作场所实施放射防护检测与评价的术语和定义、检测流程、检测仪器以及检测方法等内容和要求。 本文件适用于工业领域曝光时间在10-7秒～10-8秒的脉冲X射线发生装置的检测。

Radiation protection detection and evaluation method of industrial pulsed X-ray generator

EN ISO 16638-2:2022 放射防护 - 特定材料的监测和内部剂量测定 - 第2部分:摄入铀化合物

This document specifies the minimum requirements for the design of professional programmes to monitor workers exposed to a risk of ingestion to uranium compounds. This document establishes principles for the development of compatible goals and requirements for monitoring programmes and dose assessment for workers occupationally exposed to internal contamination. It establishes procedures and assumptions for risk analysis, monitoring programmes and the standardized interpretation of monitoring data in order to achieve acceptable levels of reliability for uranium and its compounds. It sets limits for the applicability of the procedures in respect to dose levels above which more sophisticated methods need to be applied. This document addresses those circumstances when exposure could be constrained by either radiological or chemical toxicity concerns. This document addresses, for ingestion of uranium and its compounds, the following items: a) purposes of monitoring and monitoring programmes; b) description of the different categories of monitoring programmes; c) suitable methods for monitoring and criteria for their selection; d) information that is collected for the design of a monitoring programme; e) procedures for dose assessment based on reference levels for special monitoring programmes; f) criteria for determining the significance of monitoring results; g) uncertainties arising from dose assessment and interpretation of bioassays data; h) reporting/documentation; i) quality assurance; j) record keeping requirements. It is not applicable to the following items: a) detailed descriptions of measuring methods and techniques for uranium; b) modelling for the improvement of internal dosimetry; c) potential influence of counter-measures (e.g. administration of chelating agents); d) investigation of the causes or implications of an exposure; e) dosimetry for inhalation exposures and for contaminated wounds.

Radiological protection - Monitoring and internal dosimetry for specific materials - Part 2: Ingestion of uranium compounds (ISO 16638-2:2019)