13.280 辐射防护 标准查询与下载

KS A ISO 11933-4-2022 安全壳部件 第4部分：通风和气体净化系统 如过滤器、疏水阀、安全阀和调节阀、控制和保护装置

Components for containment enclosures－Part 4：Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices

KS C IEC 60861-2022 液体流出物和地表水中放射性核素监测设备

Equipment for monitoring of radionuclides in liquid effluents and surface waters

KS A ISO 14152-2022 中子辐射防护屏蔽 设计原则及选择合适材料的考虑

Neutron radiation protection shielding－Design principles and considerations for the choice of appropriate materials

KS A 4801-2022 放射性污染防护鞋

Protective footwear for radioactive contamination

KS C IEC 62022-2022 安装监测器 用于控制和检测车辆运输的可回收或不可回收材料中所含的伽马辐射

Installed monitors for the control and detection of gamma radiations contained in recyclable or non-recyclable materials transported by vehicles

KS C IEC 61582-2022 辐射防护仪器仪表 活体计数器 便携式、可运输和安装设备的分类、一般要求和测试程序

Radiation protection instrumentation－In vivo counters－Classification, general requirements and test procedures for portable, transportable and installed equipment

KS A 4025-2022 X射线防护装置铅当量测试方法

Testing method of lead equivalent for X-ray protective devices

KS C IEC 61526-2022 辐射防护仪器 X、γ、中子和β辐射的个人剂量当量Hp(10)和Hp(0.07)的测量 直读个人剂量当量计

Radiation protection instrumentation－Measurement of personal dose equivalents Hp(10) and Hp(0.07) for X, gamma, neutron and beta radiations－Direct reading personal dose equivalent meters

KS A ISO 8690-2022 放射性污染表面的去污 去污难易性的试验和评价方法

Decontamination of radioactively contaminated surfaces－Method for testing and assessing the ease of decontamination

KS A 4036-2022 X射线防护手套

X-ray protective gloves

KS A ISO 9978-2022 辐射防护 密封放射源 泄漏试验方法

Radiation protection－Sealed radioactive sources－Leakage test methods

KS A ISO 12790-1-2022 辐射防护 放射生物测定性能标准 第1部分：一般原则

Radiation protection－Performance criteria for radiobioassay－Part 1：General principles

ASTM C1831/C1831M-17(2022) γ辐射屏蔽性能试验的标准指南

1.1 This guide identifies appropriate test methods for determining the sufficiency of radiological shielding for hot cells and shielded enclosures. 1.2 After constructing or modifying radiological shielding, it is necessary to verify that shielding performance meets or exceeds the shielding performance requirements. This is typically accomplished using sealed test sources of much less activity than the design basis. This allows for modifications or correction of any discrepancies identified before the commissioning of the hot cell. 1.3 The guidance and practices recommended by this guide are applicable to both new and existing shielded facilities and enclosures for evaluating shielding suitability and locating the existence of shine paths or other shielding anomalies that result from design, manufacture, or construction. 1.4 Two types of testing may be performed. 1.4.1 Shielding performance verification testing provides evidence that the shielding configuration is sufficient for meeting established performance criteria and for identifying deficiencies in the shielding configuration or components that may not have been addressed during design. Test results are expected to demonstrate that shielding performance meets or exceeds design criteria, not match the dose rates predicted analytically. 1.4.2 Shielding performance verification testing identifies shielding deficiencies (hot spots) in the installed configuration relative to adjacent shielding but does not demonstrate compliance with any quantitative shielding performance requirement. 1.5 Performance testing should be specified and performed to assess shielding adequacy with sources in all critical locations. 1.6 Requirements for shielding performance testing should be clearly defined in design basis or procurement documentation. 1.7 This guide is not applicable to neutron radiation shielding performance evaluations. 1.8 Units—The values stated in either SI units or inchpound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in nonconformance with the standard. 1.8.1 Units for total activity should be given in Becquerel (Bq) or curies (Ci). 1.8.2 Units for dose rate as measured during testing should be given in Sieverts (Sv/h) or rad/h. 1.8.3 Distances and locations should be provided in centimetres or inches. 1.9 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. 1.10 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 Gamma Radiation Shielding Performance Testing

GSO ISO 20046:2022 放射防护 使用荧光原位杂交 (FISH) 易位测定评估电离辐射暴露的实验室的性能标准

The purpose of this document is to provide criteria for quality assurance (QA), quality control (QC) and evaluation of the performance of biological dosimetry by cytogenetic service laboratories. This document addresses: a) the responsibilities of both the customer and the laboratory; b) the confidentiality of personal information, for the customer and the laboratory; c) the laboratory safety requirements; d) sample processing; culturing, staining and scoring, including the criteria for scoring for translocation analysis by FISH; e) the calibration sources and calibration dose ranges useful for establishing the reference dose‑response curves that contribute to the dose estimation from chromosome aberration frequency and the detection limit; f) the scoring procedure for translocations stained by FISH used for evaluation of exposure; g) the criteria for converting a measured aberration frequency into an estimate of absorbed dose (also appears as "dose"); h) the reporting of results; i) the QA and QC; j) Annexes A to F containing sample instructions for the customer, sample questionnaire, sample datasheet for recording aberrations, sample of report and fitting of the low dose-response curve by the method of maximum likelihood and calculating the uncertainty of dose estimate.

Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation

BS EN IEC 63121:2021 辐射防护仪器仪表 用于检测放射性材料非法贩运的车载移动系统

Radiation protection instrumentation. Vehicle-mounted mobile systems for the detection of illicit trafficking of radioactive materials

BS EN IEC 62484:2021 辐射防护仪器仪表 用于检测和识别放射性材料非法贩运的光谱辐射入口监测器(SRPM)

What is BS EN IEC 62484 about?    BS EN IEC 62484 discusses defines the performance requirements of installed monitors used for the detection and identification of gamma emitters and the detection of neutron radiation emitters. These monitors are commonly known as spectrometric radiation portal monitors or SRPMs. They are used to monitor vehicles, cargo containers, people, or packages and are typically used at national and international border crossings and ports of entry. SRPMs may be used at any location where there is a need for this type of monitoring.   BS EN IEC 62484 establishes the general, radiological, climatic, mechanical, electric, and electromagnetic documentation requirements and associated test methods.   Note: BS EN IEC 62484 does not apply to the performance of non-spectroscopic portal monitors covered in IEC 62244 .   Who is BS EN IEC 62484 for?

Radiation protection instrumentation. Spectrometric radiation portal monitors (SRPMs) used for the detection and identification of illicit trafficking of radioactive material

BS ISO 21909-2:2021 被动中子剂量测定系统 工作场所个人剂量测定系统资格的方法和标准

1   Scope This document provides methodology and criteria to qualify the dosimetry system at workplaces where it is used. The criteria in this document apply to dosimetry systems which do not meet the criteria with regard to energy and direction dependent responses described in ISO 21909‑1. The qualification of the dosimetry system at workplace aims to demonstrate that: — either, the non-conformity of the dosimetry system to some of the requirements on the energy or direction dependent responses defined in ISO 21909‑1 does not lead to significant discrepancies in the dose determination for a certain workplace field; — or, that the correction factor or function used for this specific studied workplace enables the dosimetry system to accurately determine the conventional dose value with uncertainties similar to the ones given in ISO 21909‑1. NOTE This document is directed at all stakeholders who are involved: IMSs , accreditation or regulatory bodies, and users of the particular dosimetry (the user is meant as the entity which assigns the dosimetry system to the radiation worker and records the assigned dose.) The methodologies to characterize the work place field in order to perfo...

Passive neutron dosimetry systems - Methodology and criteria for the qualification of personal dosimetry systems in workplaces

DB3206/T 1022-2021 环境介质放射性污染监测规范

本文件规定了环境介质放射性污染监测的样品、测量、计算、结果表达和数据存档。 本文件适用于环境介质放射性污染监测。

Specifications for Monitoring Radioactive Pollution of Environmental Media

T/WHAEPI 005-2021 建筑材料检测专用NaI低本底多道γ能谱仪

本文件规定了建筑材料检测专用NaI低本底多道γ能谱仪的术语和定义、要求、试验方法、检验规则、标志、包装、贮存与运输。 本文件适用于测量建筑材料中弱γ放射性活度的NaI低本底多道γ能谱仪。

NaI low-background multi-channel gamma spectrometer for building materials testing

ISO 21909-2:2021 被动式中子剂量测定系统第2部分:工作场所个人剂量测定系统的鉴定方法和标准

This document provides methodology and criteria to qualify the dosimetry system at workplaces where it is used. The criteria in this document apply to dosimetry systems which do not meet the criteria with regard to energy and direction dependent responses described in ISO 21909-1. The qualification of the dosimetry system at workplace aims to demonstrate that: — either, the non-conformity of the dosimetry system to some of the requirements on the energy or direction dependent responses defined in ISO 21909-1 does not lead to significant discrepancies in the dose determination for a certain workplace field; — or, that the correction factor or function used for this specific studied workplace enables the dosimetry system to accurately determine the conventional dose value with uncertainties similar to the ones given in ISO 21909-1. NOTE This document is directed at all stakeholders who are involved: IMSs, accreditation or regulatory bodies, and users of the particular dosimetry (the user is meant as the entity which assigns the dosimetry system to the radiation worker and records the assigned dose.) The methodologies to characterize the work place field in order to perform the qualification of the dosimetry system are given in Annex A. Annex B is complementary as it gives the practical methods to follow, once one methodology is chosen. The provider of the dosimetry system shall provide the type test results corresponding to ISO 21909-1. However, when the dosimetry system to be qualified does not comply with all the criteria of ISO 21909-1 dealing with the energy and angle dependence of the response, some tests of the ISO 21909-1 can be not performed. The links between ISO 21909-1 and ISO 21909-2 are described in Annex E. This document only addresses neutron personal monitoring and not criticality accident conditions.

Passive neutron dosimetry systems — Part 2: Methodology and criteria for the qualification of personal dosimetry systems in workplaces