13.280 辐射防护 标准查询与下载

GB 11930-1989 操作开放型放射性物质的辐射防护规定

本标准规定了操作开放型放射性物质所应遵循的辐射防护原则与要求。 本标准适用于放射性同位素生产和应用中，操作开放型放射性物质的一切实践活动；对核工业中操作开放型放射性物质的实践活动亦可参照使用。

Regulation of radiation protection for handling nonsealed radioactive material

GB/T 11713-1989 用半导体γ谱仪分析低比活度γ放射性样品的标准方法

本标准规定了使用高能量分辨能力的半导体γ射线能谱仪分析低比活度γ放射性核素的固态、液态或可以转化为这两种物态的均匀样品的常规方法。 本标准适用于分析活度大于谱仪的探测限L〔附录A（补充件）〕，并且各核素的Y特征谱线能够分辨开的样品。因此，一般对样品只作诸如烘干、粉碎、搅匀等简单的物理处理，而不作化学分离。当必须对样品作化学分离时，其回收率等参数应按相应规程测定。

Standard methods of analyzing low specific gamma radioactivity samples by semiconductor gamma spectrometers

GB/T 11712-1989 用于χ、γ线外照射放射防护的剂量转换因子

放射防护的基本限值量（有效剂量当量和器官剂量当量）不能直接测量，因此在监测中要使用可测量的“运用量”。本标准提供的转换因子可用于估计放射工作人员的器官剂量当量和有效剂量当量。 本标准只适用于成人受X、γ线外照射，不适用于局部照射和大剂量的事故照射。

Dose conversion factors for use in protection against χ、γ-ray external radiation

GB 8922-1988 油(气)田测井用密封型放射源放射卫生防护标准

本标准适用于在油田使用密封型（中子、γ）放射源（以下简称放射源或源）进行测井及测井研究单位。

Radiological health protection standard for using sealed radioactive sources in oil and gas-fild logging

GB 8921-1988 磷肥放射性镭-226限量卫生标准(已废止)

本标准适用于农业（包括蔬菜、果树）用磷肥及用来生产磷肥的磷矿石（包括磷精矿）。

Limit standard of radioactive Ra-226 in phosphate fertilizer

GB/T 7161-1987 非密封放射性物质 识别和证书

本标准规定了生产部门在出售非密封放射性物质时应提供的识别标志和证书的内容。以便用户对该产品作进一步物理或化学的加工处理。

Unsealed radio active substances--Identification and certification

GB 5172-1985 粒子加速器辐射防护规定

本规定适用于加速粒子的单核能量低于100MeV的粒子加速器（不包括医疗用加速器和象密封型中子管之类的可移动加速器）设施。

The rule for radiation protection of particle accelerators

T/BSRS 109-2024 高水平放射性废物粘土岩地质处置设施选址准则

本文件用于指导选择合适的高水平放射性废物粘土岩地质处置设施场址。本文件提出了高水平放射性废物粘土岩处置设施的选址阶段和选址准则。选址阶段分为：规划选址阶段、区域调查阶段、场址特性评价阶段和场址确认4个阶段。选址准则分为：地质条件、未来自然变化、水文地质、地球化学、人类活动、建造和工程条件、废物运输、环境保护、土地利用、社会影响等10个方面。 本文件适用于高水平放射性废物粘土岩地质处置设施的选址，其他类型的放射性废物粘土岩地质处置设施的选址可参照执行。 本文件是指导性文件。在实际工作中可以采用不同于本导则的方法和方案，但必须证明所采用的方法和方案至少具有与本导则相同的安全水平。

Site Selection Criteria for Claystone Geological Disposal Facilities of High-Level Radioactive Waste

T/BSRS 111-2024 高完整性容器内容物树脂辐解释氢试验方法

本文件用于指导低、中水平放射性废物处置库所处置的贮树脂高完整性容器释氢对处置库安全评价中内容物树脂释放的辐解气体（氢气）数据的获得。本文件规定了高完整性容器内容物树脂辐解释氢试验方法，即通过加速辐照的方法获得研究用树脂在规定的处置年限和树脂所含放射性核素数据计算得到的累积剂量下的辐解气体产量以及辐解气体组分。 本文件适用于低、中水平放射性废物处置库处置的贮树脂高完整性容器释放的辐解气体（氢气）对处置库安全的评价所需的树脂辐解气体（氢气）释放速率的获得，其他材料的辐解实验方法和辐解气体获得方法可参照执行。

Radiolysis experiment method of hydrogen release from resin containing in the High Integrity Container

T/BSRS 108-2024 高水平放射性废物粘土岩地质处置设施安全要求

本文件用于指导选择合适的高水平放射性废物粘土岩地质处置设施场址并提出了高水平放射性废物粘土岩处置设施的粘土岩安全要求、处置设施场址调查安全要求、处置设施设计安全要求、处置设施建造安全要求、处置设施运行安全要求、处置设施关闭安全要求和处置设施关闭后安全要求。 本文件适用于高水平放射性废物粘土岩地质处置设施，其他类型的放射性废物粘土岩地质处置设施的安全要求可参照执行。 本文件是指导性文件。在实际工作中可以采用不同于本导则的方法和方案，但必须证明所采用的方法和方案至少具有与本导则相同的安全水平。

Safety Requirements for Claystone Geological Disposal Facilities of High-Level Radioactive Waste

BS EN IEC 62618:2024 辐射防护仪器仪表 用于检测放射性物质非法贩运的基于光谱的报警个人辐射探测器（SPRD）

Radiation protection instrumentation. Spectroscopy-based alarming personal radiation detectors (SPRD) for the detection of illicit trafficking of radioactive material

T/BSRS 110-2024 贮树脂高完整性容器释氢对处置安全影响评价

本文件用于指导处置库场内所处置的贮树脂高完整性容器释氢对处置库安全的计算和评价。本文件给出了贮树脂高完整性容器在处置库氢气释放对处置库安全影响评价的主要内容和评价方法。 本文件适用于低、中水平放射性固体废物处置库场内所处置的贮树脂高完整性容器释放的氢气对处置库安全的计算和评价，其他设施的评价可参照执行。

Evaluation of the Impact of hydrogen release from resin containing in the High Integrity Container on disposal safety

T/BSRS 107-2024 放射性金属材料在高温高压水环境中应力腐蚀裂纹萌生评价试验方法

本标准规定了放射性金属材料高温高压水中应力腐蚀裂纹萌生评价试验方法的适用范围、引用标准、试样的制备和要求、试验仪器和设备、试验溶液、试验条件和步骤、试验结果的观察及评定、试验报告。 本标准适用于放射性材料高温高压水中恒载荷拉伸试验，适用材料为具有放射性的铁基、镍基合金等核用水堆材料。 本试验方法的优点是能够使用小型片状试样进行应力腐蚀实验，节省辐照后材料、减轻实验人员所受辐照剂量。

Test Method for Evaluation to Stress Corrosion Crack Initiation of Radioactive Metal Materials in High-temperature and High-pressure Water Environments

GSO ISO 8690:2024 放射性测量 发射γ射线和β射线的放射性核素 评估表面材料去污难易程度的试验方法

This document applies to the testing of surfaces that may become contaminated by radioactive materials. The ease of decontamination is a property of a surface and an important criterion for selecting surface materials used in the nuclear industry, interim storage or disposal facilities from which contamination can be removed easily and rapidly without damaging the surface. The test described in this document is a rapid laboratory-based method to compare the ease of decontamination of different surface materials. The results from the test can be one parameter to take into account when selecting surface coatings such as varnish or impervious layers such as ceramics and other surfaces. The radionuclides used in this test are those commonly found in the nuclear industry (137Cs, 134Cs and 60Co) in aqueous form. The test can also be adopted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not corrode the test specimen. The test does not measure the ease of decontamination of the surface materials in practical use, as this depends on the radionuclide(s) present, their chemical form, the duration of exposure to the contaminant and the environmental conditions amongst other factors. The test method is not intended to describe general decontamination procedures or to assess the efficiency of decontamination procedures (see ISO 7503 series). The test method is not suitable for use of radiochemicals if the radionuclide emit low energy gamma rays or beta particles that are readily attenuated in the surface.

Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials

GSO ASTM C637:2024 辐射屏蔽混凝土骨料的标准规范

This specification covers special aggregates for use in radiation-shielding concretes in which composition or high specific gravity, or both, are of prime consideration. Aggregates covered by specification include the natural mineral aggregates of either high density or high fixed water content, or both. These include aggregates that contain or consist predominately of materials such as barite, magnetite, hematite, ilmenite, and serpentine. Also included are synthetic aggregates such as iron, steel, ferrophosphorus and boron frit or other boron compounds. Fine aggregate consisting of natural or manufactured sand including high-density minerals. Coarse aggregate may consist of crushed ore, crushed stone, or synthetic products, or combinations or mixture thereof. Aggregates shall meet the required uniformity of specific gravity and fixed water content. The materials shall also meet the required chemical composition for serpentine, limonite, goethite, barite, ilmenite, hematite, magnetite, iron, ferrophosphorus, boron frit, boron carbide, calcium carbide.

Standard Specification for Aggregates for Radiation-Shielding Concrete

GSO ISO 20042:2024 放射性测量 发射伽马射线的放射性核素 采用伽马射线光谱法的通用试验方法

This document describes the methods for determining the activity in becquerel (Bq) of gamma‑ray emitting radionuclides in test samples by gamma-ray spectrometry. The measurements are carried out in a testing laboratory following proper sample preparation. The test samples can be solid, liquid or gaseous. Applications include: — routine surveillance of radioactivity released from nuclear installations or from sites discharging enhanced levels of naturally occurring radioactive materials; — contributing to determining the evolution of radioactivity in the environment; — investigating accident and incident situations, in order to plan remedial actions and monitor their effectiveness; — assessment of potentially contaminated waste materials from nuclear decommissioning activities; — surveillance of radioactive contamination in media such as soils, foodstuffs, potable water, groundwaters, seawater or sewage sludge; — measurements for estimating the intake (inhalation, ingestion or injection) of activity of gamma-ray emitting radionuclides in the body. It is assumed that the user of this document has been given information on the composition of the test sample or the site. In some cases, the radionuclides for analysis have also been specified if characteristic limits are needed. It is also assumed that the test sample has been homogenised and is representative of the material under test. General guidance is included for preparing the samples for measurement. However, some types of sample are to be prepared following the requirements of specific standards referred to in this document. The generic recommendations can also be useful for the measurement of gamma-ray emitters in situ. This document includes generic advice on equipment selection (see Annex A), detectors (more detailed information is included in Annex D), and commissioning of instrumentation and method validation. Annex F summarises the influence of different measurement parameters on results for a typical gamma-ray spectrometry system. Quality control and routine maintenance are also covered, but electrical testing of the detector and pulse processing electronics is excluded. It is assumed that any data collection and analysis software used has been written and tested in accordance with relevant software standards such as ISO/IEC/IEEE 12207. Calibration using reference sources and/or numerical methods is covered, including verification of the results. It also covers the procedure to estimate the activity content of the sample (Bq) from the spectrum. The principles set out in this document are applicable to measurements by gamma-ray spectrometry in testing laboratories and in situ. However, the detailed requirements for in situ measurement are given in ISO 18589-7 and are outside the scope of this document. This document covers, but is not restricted to, gamma-ray emitters which emit photons in the energy range of 5 keV to 3 000 keV. However, most of the measurements fall into the range 40 keV to 2 000 keV. The activity (Bq) ranges from the low levels (sub-Bq) found in environmental samples to activities found in accident conditions and high level radioactive wastes.

Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry

BS EN IEC 62694:2024 辐射防护仪器仪表 用于检测放射性物质非法贩运的背包式辐射探测器（BRD）

Radiation protection instrumentation. Backpack-type radiation detector (BRD) for the detection of illicit trafficking of radioactive material

T/ACEF 135-2024 移动式医用CT设备辐射防护与安全要求

本文件规定了移动式医用CT设备诊断过程应用中的辐射防护与安全要求。

Requirements on radiation protection and safety for mobile medical computed tomography equipment

T/ACEF 137-2024 辐射屏蔽用铅砖

本文件规定了辐射屏蔽用铅砖的分类与命名、技术要求、试验方法、检验规则以及标志、包装、运输和贮存。

Lead bricks for radiation shielding

T/ACEF 136-2024 核医学钇-90微球辐射防护与安全要求

本文件适用于医疗机构核医学钇-90微球使用过程中的辐射防护与安全管理。 本文件不适用于非医疗机构中开展钇-90微球的生产、运输、科研等相关实践活动。

Requirements on radiation protection and safety for yttrium-90 microspheres in nuclear medicine