F50 同位素与放射源综合 标准查询与下载

DB12/T 487-2013 放射性同位素与射线装置安全使用管理制度编制规范

本标准适用于天津市行政区域或管辖范围内放射性同位素与射线装置使用单位安全使用管理制度（以下简称管理制度）的编制。

Specifications for the preparation of the management system for the safe use of radioisotope and radiation devices

KS A ISO 2919:2012 辐射防护.密封放射源.通用要求和分类

이 표준은 밀봉 선원의 시험절차를 기초로 한 밀봉 선원의 분류체계를 설정하고 일반요건, 성

Radiation protection-Sealed radioactive sources-General requirements and classification

DIN 25466:2012 放射性材料烟雾排气管.施工和检验规则

Fume hoods for radioactive materials - Rules for construction and tests

ISO 2919:2012 辐射防护 密封放射源 一般要求和分级

This International Standard establishes a classification system for sealed radioactive sources that is based on test performance and specifies general requirements, performance tests, production tests, marking and certification. It provides a set of tests by which manufacturers of sealed radioactive sources can evaluate the safety of their products in use and users of such sources can select types which are suitable for the required application, especially where protection against the release of radioactive material, with consequent exposure to ionizing radiation, is concerned. This International Standard can also serve as guidance to regulating authorities. The tests fall into several groups, including, for example, exposure to abnormally high and low temperatures and a variety of mechanical tests. Each test can be applied in several degrees of severity. The criterion of pass or fail depends on leakage of the contents of the sealed radioactive source. NOTE Leakage test methods are given in ISO 9978. Although this International Standard classifies sealed sources by a variety of tests, it does not imply that a sealed source will maintain its integrity if used continuously at the rated classification. For example, a sealed source tested for 1 h at 600 °C might, or might not, maintain its integrity if used continuously at 600 °C. A list of the main typical applications of sealed radioactive sources, with a suggested test schedule for each application, is given in Table 3. The tests constitute minimum requirements corresponding to the applications in the broadest sense. Factors to be considered for applications in especially severe conditions are listed in 4.2. This International Standard makes no attempt to classify the design of sources, their method of construction or their calibration in terms of the radiation emitted. Radioactive materials inside a nuclear reactor, including sealed sources and fuel elements, are not covered by this International Standard.

Radiological protection - Sealed radioactive sources - General requirements and classification

DIN 25425-5:2011 放射性同位素实验室.第5部分:表面去污规则

Radioisotope laboratories - Part 5: Rules for the decontamination of surfaces

ASTM C1030-10 用γ射线光谱法测定钚同位素成分的标准试验方法

The determination of plutonium isotopic composition by gamma-ray spectrometry is a nondestructive technique and when used with other nondestructive techniques, such as calorimetry (Test Method C1458) or neutron counting (Test Methods C1207, C1316, C1493, and C1500), can provide a wholly nondestructive plutonium assay necessary for material accountancy and safeguards needs. Because gamma-ray spectrometry systems are typically automated, the routine use of the test method is fast, reliable, and is not labor intensive. The test method is nondestructive, requires no sample preparation, and does not create waste disposal problems. This test method assumes that all plutonium in the measured item has the same isotopic distribution, often called isotopic homogeneity (see 7.2.4 and 7.2.5). The 242Pu abundance is not measured by this test method and must be estimated from isotopic correlation techniques, stream averages, historical information, or other measurement techniques. Americium-241 is a daughter product of 241Pu. The 241Am/239Pu atom ratio can also be determined by means of this test method (assuming a homogeneous isotopic distribution of plutonium and 241Am). The determination of the 241Am/239Pu atom ratio is necessary for the correct interpretation of a calorimetric heat measurement. The isotopic composition of a given batch or item of plutonium is an attribute of that item and, once determined, can be used in subsequent inventory measurements to verify the identity of an item within the measurement uncertainties. The method can also measure the ratio of other gamma-emitting isotopes to plutonium assuming they have the same spatial distribution as the plutonium in the item. Some of these “other” gamma-emitting isotopes include isotopes of uranium, neptunium, curium, cesium, and other fission products. The same methods of this standard can be used to measure the isotopic composition of uranium in items containing only uranium (3, 4, 5, 6).1.1 This test method is applicable to the determination of isotopic abundances in isotopically homogeneous plutonium-bearing materials. This test method may be applicable to other plutonium-bearing materials, some of which may require modifications to the described test method. 1.2 The procedure is applicable to items containing plutonium masses ranging from a few tens of milligrams up to the maximum plutonium mass allowed by criticality limits. 1.3 Measurable gamma ray emissions from plutonium cover the energy range from approximately 30 keV to above 800 keV. K-X-ray emissions from plutonium and its daughters are found in the region around 100 keV. This test method has been applied to all portions of this broad spectrum of emissions. 1.4 The isotopic abundance of the 242Pu isotope is not directly determined because it has no useful gamma-ray signature. Isotopic correlation techniques may be used to estimate its relative abundance Refs (1) and (2). 1.5 This test method has been demonstrated in routine use for isotopic abundances ranging from 99 to <50 % 239Pu. This test method has also been employed for isotopic ab......

Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry

ASTM D7219-08 同位素和接近同位素核裂变物质标准规范

1.1 This specification covers the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designer’s requirements for fuel elements, moderator or reflector blocks, in a high temperature gas cooled reactor. The graphite classes specified here would be suitable for reactor core applications where neutron irradiation induced dimensional changes are a significant design consideration. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. (See IEEE/ASTM SI 10.) 1.3 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 Specification for Isotropic and Near-isotropic Nuclear Graphites

ASTM C1118-07 波长色散X射线荧光(XRF)系统的选择元件用标准指南

This guide describes typical prospective analytical X-ray fluorescence systems that may be used for qualitative and quantitative elemental analyses of materials related to the nuclear fuel cycle. Standard test methods for the determination of materials using wavelength-dispersive XRF4 usually employ apparatus with the components described in this guide.1.1 This guide describes the components for a wavelength-dispersive X-ray fluorescence system for materials analysis. This guide can be used as a reference in the apparatus section of test methods for wavelength-dispersive X-ray fluorescence (WDXRF) analyses of nuclear materials.1.2 The components recommended include X-ray detectors, signal processing electronics, excitation sources, and dispersing crystals.1.3 Detailed data analysis procedures are not described or recommended, as they may be unique to a particular analysis problem. Some applications may require the use of complex computer software during data reduction to correct for matrix effects.1.4 The values stated in SI units are to be regarded as the standard.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 Guide for Selecting Components for Wavelength-Dispersive X-Ray Fluorescence (XRF) Systems

ASTM D7219-05 同位素和接近同位素核裂变物质标准规范

1.1 This specification covers the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designers requirements for fuel elements, moderator or reflector blocks, in a high temperature gas cooled reactor. The graphite classes specified here would be suitable for reactor core applications where neutron irradiation induced dimensional changes are a significant design consideration.1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.3 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 Specification for Isotropic and Near-isotropic Nuclear Graphites

EJ/T 499-2004 压水堆核电厂一次中子源棒设计和制造技术条件

本标准规定了压水堆核电厂一次中子源棒的结构设计、材料、制造、试验和检验、包装、运输、操 作和贮存等技术要求。 本标准适用于压水堆核电厂一次中子源棒的设计、制造、包装和运输。

Specification for design and manufacture of primary neutron source rod for pressurized water reactor nuclear power plant

ASTM C1030-03 用γ射线光谱法测定钚同位素成分的标准试验方法

The determination of isotopic composition by gamma-ray spectrometry is a nondestructive technique and when used with other nondestructive techniques, such as calorimetry (Test Method C 1458) or neutron counting (Test Methods C 1207C 1493C 1500), can provide a totally nondestructive plutonium assay necessary for material accountancy and safeguards needs. Since gamma-ray spectrometry systems are typically automated, the routine use of the test method is fast, reliable, and is not labor intensive. Since the test method is nondestructive, requiring no sample preparation, it does not create waste disposal problems. This test method assumes that the isotopic composition of plutonium in the sample being measured is homogeneous (see see 7.2.4 and (5)). The 242Pu abundance is not measured by this test method and must be estimated from isotopic correlation techniques, stream averages, historical information, or other measurement techniques. A daughter product of 241Pu is 241Am. The 241Am/239Pu atom ratio can also be determined by means of this test method (assuming a homogeneous isotopic distribution of plutonium and 241Am) and is necessary for the correct interpretation of a calorimetric heat measurement. The isotopic composition of a given batch or sample of plutonium is an attribute of that sample and, once determined, can be used in subsequent inventory measurements to verify the identity of a sample within the measurement uncertainties. The method can also measure the ratio of other gamma emiting isotopes to plutonium assuming they have the same spatial distribution as the plutonium in the sample. Some of these “other” gamma-emitting isotopes include isotopes of uranium, neptium, curium, cesium, and other fission products. (The same methods of this standard can be used to measure the isotopic composition of uranium in samples containing only uranium (4–6)).1.1 This test method is applicable to the determination of isotopic abundances in isotopically homogeneous Pu-bearing materials. This test method may be applicable to other plutonium-bearing materials, some of which may require modifications to the described test method. 1.2 The procedure is applicable to sample sizes ranging from a few tenths of a gram up to the maximum sample weight allowed by criticality limits. 1.3 Because 242 Pu has no useful gamma-ray signature, its isotopic abundance is not determined. Isotopic correlation techniques may be used to estimate its relative abundance (Refs 1, 2). 1.4 This test method has been demonstrated in routine use for isotopic abundances ranging from 94 to 70% 239 Pu. This test method has also been employed for isotopic abundances outside this range. 1.5 The values stated in SI units are to be regarded as the standard. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry

NF M61-100:2000 核能.辐射防护.手足和眼睛用热致发光剂量计

Nuclear energy - Radiation protection - Individual thermoluminescence dosemeters for extremities and eyes.

DIN 25425-2:1997 放射性同位素实验室.内部射线防护规则

The document shall be used during handling with radioactive materials in radioisotope laboratories for nonmedical purposes. It should serve as basic information for setting up internal radiation protection rules by radiation protection officers.

Radioisotope laboratories - Part 2: Internal radiation protection rules

ASTM E798-96 对基于加速器的中子源进行辐照的标准实施规范

1.1 This practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on two types of sources, namely nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply to other types of accelerator-based sources, including spallation neutron sources (1). Interest in spallation sources has increased recently due to their proposed use for transmutation of fission reactor waste (2). 1.2 Many of the experiments conducted using such neutron sources are intended to simulate irradiation in another neutron spectrum, for example, that from a DT fusion reaction. The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. In general, the intent of these simulations is to establish the fundamental relationships between irradiation or material parameters and the material response. The extrapolation of data from such experiments requires that the differences in neutron spectra be considered. 1.3 The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample, and the neutron flux and spectrum, as well as procedures for recording and reporting irradiation data. 1.4 Other experimental problems, such as temperature control, are not included. 1.5 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 Conducting Irradiations at Accelerator-Based Neutron Sources

ASTM E798-96(2003) 对基于加速器的中子源进行辐照的标准实施规范

1.1 This practice covers procedures for irradiations at accelerator-based neutron sources. The discussion focuses on two types of sources, namely nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply to other types of accelerator-based sources, including spallation neutron sources (). Interest in spallation sources has increased recently due to their proposed use for transmutation of fission reactor waste ().1.2 Many of the experiments conducted using such neutron sources are intended to simulate irradiation in another neutron spectrum, for example, that from a DT fusion reaction. The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. In general, the intent of these simulations is to establish the fundamental relationships between irradiation or material parameters and the material response. The extrapolation of data from such experiments requires that the differences in neutron spectra be considered.1.3 The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample, and the neutron flux and spectrum, as well as procedures for recording and reporting irradiation data.1.4 Other experimental problems, such as temperature control, are not included.1.5 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 Conducting Irradiations at Accelerator-Based Neutron Sources

DIN 25466:1995 放射性材料烟雾排气管.建造和试验规定

The document deals with special requirements for fume hoods for radioactive materials. So far there are no special requirements, general requirements for fume hoods in conventional laboratories shall be used. The purpose of this document is to give rules for planning, inspection and operation of radioisotope laboratories with fume hoods. Planning constructing and operating authorities should be enabled to get a guiding paper for practical use.

Fume hoods for radioactive materials - Rules for construction and tests

DIN 25425-1 Bb.1:1995 放射性同位元素实验室.第1部分:设计规则.应用举例

Radioisotope laboratories - Part 1: Rules for design; examples for application

DIN 25425-1:1995 放射性同位元素实验室.第1部分:设计规则

The document is to be applied for the design of radioisotope laboratories where unsealed radioactive material is handled in a notifiable way or requiring an acceptance by the authorities. It is also to be applied in those cases, where if necessay, additional sealed sources are handled and for the design of function related special rooms. As far as the unrationed allowances take into account the sum formula for sealed radiactive materials this document is not to be applied.

Radioisotope laboratories - Part 1: Rules for design

EJ/T 921-1995 放射性核素活度直接测量4πβ（PC）-γ符合法

4πβ(PC)-γ coincidence method for direct measurement of radionuclide activity

EJ/T 973-1995 二氧化铀粉末和芯块中铀同位素丰度的热电离质谱法测定

Determination of Uranium Isotope Abundance in Uranium Dioxide Powder and Pellets by Thermal Ionization Mass Spectrometry