F46 核材料、核燃料及其分析试验方法 标准查询与下载

DB34/T 1563.2.2-2011 ITER馈线系统（FEEDER）故障模式及影响分析（FMEA）指南 第2部分：功能及硬件

DB34/T 1563 的本部分规定了国际热核聚变实验堆（ITER）馈线系统(FEEDER) 故障模式及影响分析(FMEA)的内容和方法，FEEDER功能及硬件FMEA的方法。 本部分适用于ITER馈线系统(FEEDER) 功能及硬件的故障模式及影响分析(FMEA)。

ITER Feeder System (FEEDER) Failure Mode and Effects Analysis (FMEA) Guide Part 2: Function and Hardware

DB34/T 1563.1-2011 ITER馈线系统(FEEDER)故障模式及影响分析(FMEA)指南 第1部分:术语和基本要求

本部分适用于产品在论证、方案、工程研制与定型、生产和使用等寿命周期各阶段开展的FMEA工作。

Guide to failure mode and effects analysis of ITER Feeder system Part 1: terms and basic requirements

DB34/T 1563.3-2011 ITER馈线系统(FEEDER)故障模式及影响分析(FMEA)指南 第3部分：功能及硬件分析报告

本部分适用于以纵向场（TF）磁体馈线系统为对象进行的FMEA分析，其他类型馈线系统也可参考本部分。

Guide to failure mode and effects analysis of ITER Feeder system Part 3: Analysis reports of function and hardware

DB34/T 1564-2011 超导电缆固体绝缘层帕邢条件直流高电压试验方法

本标准适用于超导电缆以及相关配套设备固体绝缘材料（多为树脂、浸渍纤维、薄膜、复合材料等）在帕邢（Paschen）条件下直流耐电压测试，同样适用于固体绝缘材料的击穿电压、介电强度的测试。对于其它使用橡胶、陶瓷等材料的绝缘体亦可参考本标准测试上述性能。

The DC High Voltage Experimental Method for the Solid Insualtion on Superconducting Cable under Paschen Condition

NF M60-441*NF ISO 27468:2011 用极限燃耗效益法对含有压水反应堆二氧化铀燃料的系统进行评估,并判定核临界安全性.

Nuclear criticality safety - Evaluation of systems containing PWR UOX fuels - Bounding burnup credit approach.

NF M60-443*NF ISO 11311:2011 核临界安全:反应堆外匀质钚铀氧化物燃料混合物的临界值.

Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors.

NF M60-333:2011 核能.燃料循环技术.废物.废水和废物中碘129活性的测定

Énergie nucléaire - Technologie du cycle du combustible - Déchets - Détermination de l'activité de l'iode 129 dans des effluents et déchets

BS ISO 27468:2011 核临界安全.含PWR UOX燃料系统的评估.边界燃烧信用法

Nuclear criticality safety. Evaluation of systems containing PWR UOX fuels. Bounding burnup credit approach

EJ/T 1035-2011 土壤中锶-90的分析方法

本标准规定了用磷酸二(2-乙基已基)酯(P204)萃淋树脂色层分析土壤中锶-90的快速法和放置法。本标准适用于土壤中锶-90的分析,方法检出限为:0.23Bq/kg。快速法分析步骤适用于锶-90-钇-90处于平衡状态和不含钇-91的土壤样品。

Analytical method for strontium-90 in soil

ISO 27468:2011 核临界安全.包含PWR UOX燃料的系统评估.临界燃耗效益方法

Nuclear criticality safety - Evaluation of systems containing PWR UOX fuels - Bounding burnup credit approach

ISO 11311:2011 核临界安全.反应堆外部钚铀混合燃料的临界值

Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors

ANSI/ASTM D7301:2011 适用于受低中子Irr Adiation剂量影响元件的核石墨用规范

Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose

ASTM D7301-11 适用于受低中子辐照剂量元件的核石墨标准规范

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 reflector blocks and core support structures, 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 not a significant design consideration. 1.2 The purpose of this specification is to document the minimum acceptable properties and levels of quality assurance and traceability for nuclear grade graphite suitable for components subjected to low irradiation dose. Nuclear graphites meeting the requirements of Specification D7219 are also suitable for components subjected to low neutron irradiation dose. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose

ASTM C696-11 对核级二氧化铀粉末和球粒进行化学分析,质谱分析及光谱分析的标准试验方法

Uranium dioxide is used as a nuclear-reactor fuel. In order to be suitable for this purpose, the material must meet certain criteria for uranium content, stoichiometry, isotopic composition, and impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C753 and C776. An assay is performed to determine whether the material has the minimum uranium content specified on a dry weight basis. The stoichiometry of the oxide is useful for predicting its sintering behavior in the pellet production process. Determination of the isotopic content of the uranium in the uranium dioxide powder is made to establish whether the effective fissile content is in compliance with the purchaser''s specifications. Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. Determination of impurities is also required for calculation of the equivalent boron content (EBC).1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Uranium by Ferrous Sulfate Reduction in Phosphoric Acid and Dichromate Titration Method C1267 Test Method for Uranium By Iron (II) Reduction In Phosphoric Acid Followed By Chromium (VI) Titration In The Presence of Vanadium Uranium and Oxygen Uranium Atomic Ratio by the Ignition (Gravimetric) Impurity Correction Method C1453 Standard Test Method for the Determination of Uranium by Ignition and Oxygen to Uranium Ratio (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets Carbon (Total) by Direct Combustion-Thermal Conductivity Method C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Total Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method C1502 Standard Test Method for the Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide nbsp;nbsp;nbsp; Moisture by the Coulometric, Electrolytic Moisture Analyzer Method7-14 Nitrogen by the Kjeldahl Method15-22

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets

ASTM E385-11 使用14 MeV中子活化法和直接计算技术测定含氧量的标准试验方法

The conventional determination of oxygen content in liquid or solid samples is a relatively difficult chemical procedure. It is slow and usually of limited sensitivity. The 14-MeV neutron activation and direct counting technique provides a rapid, highly sensitive, nondestructive procedure for oxygen determination in a wide range of matrices. This test method is independent of the chemical form of the oxygen. This test method can be used for quality and process control in the metals, coal, and petroleum industries, and for research purposes in a broad spectrum of applications.1.1 This test method covers the measurement of oxygen concentration in almost any matrix by using a 14-MeV neutron activation and direct-counting technique. Essentially, the same system may be used to determine oxygen concentrations ranging from under 10 μg/g to over 500 mg/g, depending on the sample size and available 14-MeV neutron fluence rates. Note 18212;The range of analysis may be extended by using higher neutron fluence rates, larger samples, and higher counting efficiency detectors. 1.2 This test method may be used on either solid or liquid samples, provided that they can be made to conform in size, shape, and macroscopic density during irradiation and counting to a standard sample of known oxygen content. Several variants of this method have been described in the technical literature. A monograph is available which provides a comprehensive description of the principles of activation analysis using a neutron generator (1). 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 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 and health practices and determine the applicability of regulatory limitations prior to use. Specific precautions are given in Section 8.

Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique

ASTM C889-11 核纯级的氧化钆(Gd2O3)粉末的化学和质谱分析标准试验方法

Gadolinium oxide powder is used, with subsequent processing, in nuclear fuel applications, such as an addition to uranium dioxide. These test methods are designed to determine whether the material meets the requirements described in Specification C888. The material is analyzed to determine whether it contains the minimum gadolinium oxide content specified. The loss on ignition and impurity content are determined to ensure that the weight loss and the maximum concentration limit of specified impurity elements are not exceeded.1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Carbon by Direct CombustionThermal Conductivity C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Total Chlorine and Fluorine by Pyrohydrolysis Ion Selective Electrode C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Loss of Weight on Ignition7-13 Sulfur by CombustionIodometric Titration Impurity Elements by a Spark-Source Mass Spectrographic C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Uranium Hexafluoride C1287 Test Method for Determination of Impurities In Uranium Dioxide By Inductively Coupled Plasma Mass Spectrometry Gadolinium Content in Gadolinium Oxide by Impurity Correction14-17 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 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 and health practices and determine the applicability of regulatory limitations prior to use. For specific hazard statements, see Section 5. 7.1 This test method covers the loss-on-ignition of volatile constituents from nuclear-grade gadolinium oxide (Gd2O3) powder. 14.1 The percent gadolinium oxide content of powders, exclusive of volatiles, is determined by calculation after the material......

Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd₂O₃) Powder

ASTM D2685-11 用气体色层分离法对六氟化硫中空气和四氟化碳含量的标准试验方法

Air and carbon tetrafluoride (CF4) are two contaminants of interest in sulfur hexafluoride (SF6). Both of these contaminants adversely affect the performance of SF6 when used as an electrical insulating gas. Specification for maximum levels of these contaminants are given in Specification D2472. Gas chromatography is used to separate these contaminants from a sample of SF6 and to determine their concentration.1.1 This test method covers the determination of air (Note 1) and carbon tetrafluoride as impurities in sulfur hexafluoride. Note 18212;Nitrogen, oxygen, or any of their mixtures is considered to be air. Commercial grade air or nitrogen is used for standardization. 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 Test Method for Air and Carbon Tetrafluoride in Sulfur Hexafluoride by Gas Chromatography

ASTM C1428-11 用单支标准气体源多收集器质谱仪法进行六氟化铀的同位素分析的标准试验方法

Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C787 and C996.1.1 This test method is applicable to the isotopic analysis of uranium hexafluoride (UF6) with 235U concentrations less than or equal to 5 % and 234U, 236U concentrations of 0.0002 to 0.1 %. 1.2 This test method may be applicable to the analysis of the entire range of 235U isotopic compositions providing that adequate Certified Reference Materials (CRMs or traceable standards) are available. 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 health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single-Standard Gas Source Multiple Collector Mass Spectrometer Method

ASTM C1234-11 痕量元素测定用高压,高温分解法制备油及含油废物样品的标准操作规程

This practice is useful for preparation of difficult-to-digest, primarily oils and oily wastes, specimens for trace element determinations of up to 28 elements by atomic absorption or plasma emission techniques. Specimen preparation by high-pressure ashing is primarily applicable to specimens whose preparation by EPA SW-846 protocols is either not applicable or not defined. This sample preparation practice is applicable for the trace element characterization of mixed oily wastes for use by waste treatment facilities such as incinerators or waste stabilization facilities.1.1 This practice covers a high-pressure, high-temperature digestion technique using the high-pressure asher (HPA) for preparation of oils and oily waste specimens for determination of up to 28 different elements by inductively coupled plasma-atomic emission plasma spectroscopy (ICP-AES), cold-vapor atomic absorption spectroscopy (CVAAS), and graphite furnace atomic absorption spectroscopy (GFAAS), inductively coupled plasma-mass spectrometry (ICPMS), and radiochemical methods. Oily and high-percentage organic waste streams from nuclear and non-nuclear manufacturing processes can be successfully prepared for trace element determinations by ICP-AES, CVAAS, and GFAAS. This practice is applicable to the determination of total trace elements in these mixed wastes. Specimens prepared by this practice can be used to characterize organic mixed waste streams received by hazardous waste treatment incinerators and for total element characterization of the waste streams. 1.2 This practice is applicable only to organic waste streams that contain radioactivity levels that do not require special personnel or environmental protection from radioactivity or other acute hazards. 1.3 A list of elements determined in oily waste streams is found in Table 1. 1.4 This practice has been used successfully to completely digest a large variety of oils and oily mixed waste streams from nuclear processing facilities. While the practice has been used to report data on up to 28 trace elements, its success should not be expected for all analytes in every specimen. The overall nature of these oily wastes tends to be heterogeneous that can affect the results. Homogeneity of the prepared sample is critical to the precision and quality of the results. 1.5 This practice is designed to be applicable to samples whose preparation practices are not defined, or not suitable, by other regulatory procedures or requirements, such as the U.S. Environmental Protection Agency (EPA) SW-846 and EPA-600/4-79-020 documents. This digestion practice is designed to provide a high level of accuracy and precision, but does not replace or override any regulatory requirements for sample preparation. 1.6 This practice uses hazardous materials, operations, and equipment at high pressure (90–110 bars, 89–108 atm, or 1305–1595 lb/in.2) and high temperatures, up to 320°C, and therefore poses significant hazards if not operated properly. 1.7 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.7.1 Exception8212;Pressure measurements are given in lb/in. units. 1.8 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. Specific warning statements are given in Sections 10. TABLE 1 List of......

Standard Practice for Preparation of Oils and Oily Waste Samples by High-Pressure, High-Temperature Digestion for Trace Element Determinations

ASTM C761-11 六氟化铀的化学,质谱,光谱化学,核(放射性)及放射化学分析的标准试验方法

1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities.1.2 The analytical procedures in this document appear in the following order:Note 18212;Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications.SectionsSubsampling of Uranium Hexafluoride7 - 10Gravimetric Determination of Uranium11 - 19Titrimetric Determination of Uranium20 Preparation of High-Purity U3O 821Isotopic Analysis22Isotopic Analysis by Double-Standard Mass-Spectrometer Method23 - 29Determination of Hydrocarbons, Chlorocarbons, and Partially Substituted Halohydrocarbons29-36Atomic Absorption Determination of Antimony36Spectrophotometric Determination of Bromine37Titrimetric Determination of Chlorine38-44Determination of Silicon and Phosphorus45-51Determination of Boron and Silicon52-59 Determination of Ruthenium60 Determination of Titanium and Vanadium61Spectrographic Determination of Metallic Impurities 62Determination of Tungsten63Determination of Thorium and Rare Earths64-69Determination of Molybdenum70Atomic Absorption Determination of Metallic Impurities71-76Impurity Determination by Spark-Source Mass Spectrography77Determination of Boron-Equivalent Neutron Cross Section78Determination of Uranium-233 Abundance by Thermal Ionization Mass Spectrometry79Determination of Uranium-232 by Alpha Spectrometry80-86Determination of Fission Product Activity87Determination of Plutonium by Ion Exchange and Alpha Counting88-92Determination of Plutonium by Extraction and Alpha Counting93-100Determination of Neptunium by Extraction and Alpha Counting101-108Atomic Absorption Determination of Chromium Soluble In Uranium Hexafluoride109-115Atomic Absorption Determination of Chromium Insoluble In Uranium Hexafluoride116-122Determination of Technetium-99 In Uranium Hexafluoride123-131Method for the Determiation of Gamma-Energy Emission Rate from Fission Products in Uranium Hexafluoride132Determination of Metallic Impurities by ICP-AES133-142Determination of Molybdenum, Niobium, Tantalum, Titanium, and Tungsten by ICP-AES143-1521.3 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. (For specific safeguard and safety consideration statements, see Section 6.)

Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride