27.120.30 裂变物质 标准查询与下载

KS A ISO 18315:2019 核能 - 通过线性回归分析评估铀溶液中杂质的测量不确定性的指南

Nuclear energy — Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis

KS A ISO 18315-2019 核能 - 通过线性回归分析评估铀溶液中杂质的测量不确定性的指南

Nuclear energy — Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis

ISO 10276:2019 核能.燃料技术.运输放射性物质用包装的耳轴系统

This document covers trunnion systems used for tie-down, tilting and/or lifting of a package of radioactive material during transport operations. Aspects included are the design, manufacture, maintenance, inspection and management system. Regulations which can apply during handling operation in nuclear facilities are not addressed in document. This document does not supersede any of the requirements of international or national regulations, concerning trunnions used for lifting and tie-down.

Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material

KS A ISO 9278-2019 核能 二氧化铀丸粒 密度和开孔和闭孔体积分数的测定

Nuclear energy — Uranium dioxide pellets — Determination of density and volume fraction of open and closed porosity

KS A ISO 9005-2019 核能 二氧化铀粉末和烧结球团 电流法测定氧/铀原子比

Nuclear energy — Uranium dioxide power and sintered pellets — Determination of oxygen/uranium atomic ratio by the amperometric method

KS A ISO 9161-2019 二氧化铀粉表观密度和振实密度的测定

Uranium dioxide powder－Determination of apparent density and tap density

KS A ISO 11320-2019 核临界安全 应急准备和响应

Nuclear criticality safety — Emergency preparedness and response

ASTM D7219-19 各向同性和近各向同性核石墨的标准规范

1.1 This specification covers the classification, processing, and typical properties of as-manufactured nuclear grade graphite billets with dimensions sufficient to meet the designer’s requirements for fuel elements, moderator or reflector blocks, in a high temperature reactor. The graphite classes specified here may be suitable for reactor core applications where dimensional change due to fast neutron irradiation has a significant impact on design, provided they meet the requirements of the ASME code. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 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 Specification for Isotropic and Near-isotropic Nuclear Graphites

ASTM C1477-19 通过多集电极 电感耦合等离子体质谱法对六氟化铀和硝酸铀溶液进行同位素丰度分析的标准测试方法

1.1 This test method covers the isotopic abundance analysis of 234 U, 235 U, 236 U, and 238 U in samples of hydrolysed uranium hexafluoride (UF6) by inductively coupled plasma source, multicollector, mass spectrometry (ICP-MC-MS). The method applies to material with 235 U abundance in the range of 0.2 to 6 % mass. This test method is also described in ASTM STP 1344. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 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 Test Method for Isotopic Abundance Analysis of Uranium Hexafluoride and Uranyl Nitrate Solutions by Multi-Collector, Inductively Coupled Plasma-Mass Spectrometry

ASTM C1001-19 用α光谱法对土壤中钚进行放射化学测定的标准试验方法

1.1 This test method covers the determination of plutonium in soils at levels of detection dependent on count time, sample size, detector, background, and tracer yield. This test method describes one acceptable approach to the determination of plutonium in soil. 1.2 This test method is designed for 10 g of soil, previously collected and treated as described in Practices C998 and C999, but sample sizes up to 50 g may be analyzed by this test method. This test method may not be able to completely dissolve all forms of plutonium in the soil matrix. 1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 10. 1.5 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 Test Method for Radiochemical Determination of Plutonium in Soil by Alpha Spectroscopy

ASTM C696-19 核级二氧化铀粉末和芯块的化学、质谱和光谱化学分析的标准试验方法

1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nucleargrade uranium dioxide powders and pellets to determine compliance with specifications. 1.2 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only. 1.3 The analytical procedures appear in the following order: Sections Uranium by Ferrous Sulfate Reduction in Phosphoric Acid and Dichromate Titration Method 2 Uranium and Oxygen Uranium Atomic Ratio by the Ignition (Gravimetric) Impurity Correction Method 3 Carbon (Total) by Direct Combustion-Thermal Conductivity Method 2 Total Chlorine and Fluorine by Pyrohydrolysis IonSelective Electrode Method 3 Moisture by the Coulometric, Electrolytic Moisture Analyzer Method 8 – 15 Nitrogen by the Kjeldahl Method 16 – 23 Isotopic Uranium Composition by Multiple-Filament Surface Ionization Mass Spectrometric Method 4 Spectrochemical Determination of Trace Elements in High-Purity Uranium Dioxide 5 Silver, Spectrochemical Determination of, by Gallium Oxide Carrier D-C Arc Technique 5 Rare Earths by Copper Spark-Spectrochemical Method 2 Impurity Elements by a Spark-Source Mass Spectrographic Method 2 Surface Area by Nitrogen Absorption Method 24 – 30 Total Gas in Reactor-Grade Uranium Dioxide Pellets 2 Thorium and Rare Earth Elements by Spectroscopy 2 Hydrogen by Inert Gas Fusion 3 Uranium Isotopic Analysis by Mass Spectrometry 2 1.4 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 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets

ASTM C1771-19 用电感耦合等离子体测定水解六氟化铀中硼、硅和锝的标准试验方法&x2014；固相萃取除铀后的质谱仪

1.1 This test method covers the determination of boron, silicon, and technetium in hydrolyzed uranium hexafluoride (UF6) by Inductively Coupled Plasma Mass Spectrometry (ICP-MS) after separation of the uranium by solid phase extraction. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. Some specific hazards statements are given in Section 7 on Hazards. 1.4 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 Test Method for Determination of Boron, Silicon, and Technetium in Hydrolyzed Uranium Hexafluoride by Inductively Coupled Plasma—Mass Spectrometer After Removal of Uranium by Solid Pha

ASTM C1625-19 通过热离子化质谱法测定铀和钚浓度和同位素丰度的标准测试方法

1.1 This test method covers the determination of the concentration and isotopic composition of uranium and plutonium in solutions. The purified uranium or plutonium from samples ranging from nuclear materials to environmental or bioassay matrices is loaded onto a mass spectrometric filament. The isotopic ratio is determined by thermal ionization mass spectrometry, the concentration is determined by isotope dilution. 1.2 The values stated in SI units are to be regarded as the standard. Values in parentheses are for information only. 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 safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 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 Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry

ASTM C968-19 用于分析烧结钆氧化物 - 二氧化铀丸的标准测试方法

1.1 These test methods cover procedures for the analysis of sintered gadolinium oxide-uranium dioxide pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Section Carbon (Total) by Direct Combustion—Thermal Conductivity Method 2 C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method 3 Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method 4 C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide 3 Gadolinia Content by Energy-Dispersive X-Ray Spectrometry 4 C1456 Test Method for Determination of Uranium or Gadolinium (or both) in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray Fluorescence (XRF) 3 Hydrogen by Inert Gas Fusion 4 C1457 Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction 3 Isotopic Uranium Composition by Multiple-Filament SurfaceIonization Mass Spectrometric Method 2 C1413 Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride And Uranyl Nitrate Solutions By Thermal Ionization Mass Spectrometry 3 C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis 3 Nitrogen by Distillation—Nessler Reagent (Photometric) Method 7 to 17 Oxygen-to-Metal Ratio of Sintered Gadolinium Oxide-Uranium Dioxide Pellets 4 C1430 Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration 3 Spectrochemical Determination of Trace Impurity Elements 4 C1517 Test Method for Determination of Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy 3 Total Gas by Hot Vacuum Extraction 2 Ceramographic Determination of Free Gd2O3 and Free UO2 to Estimate the Homogeneity of (U,Gd)O2 Pellets 18 to 25 Section Ceramographic Determination of Average Grain Size by Linear Intercept after Chemical Etching 26 to 33 1.3 The values stated in SI units are to be regarded as the 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 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 Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

BS ISO 21391:2019 核临界安全 次临界控制的几何尺寸 设备及布局

What is ISO 21391- Geometrical dimensions for subcriticality control about?   ISO 21391 is an International Standard on nuclear criticality safety.    ISO 21391 provides guidance, requirements and recommendations related to determination of   limits on subcriticality dimensions and ensuring compliance with:   Geometrical dimensions specified in the design (design dimensions)   Actual dimensions   ISO 21391 is applicable to nuclear facilities containing fissile materials, except nuclear power reactor cores. ISO 21391 can also be applied to the tran...

Nuclear criticality safety. Geometrical dimensions for subcriticality control. Equipment and layout

ISO 21391:2019 核临界性 - 安全尺度 - 核建筑尺寸与核临界安全尺寸限制的合规验证

This document provides guidance, requirements and recommendations related to determination of limits on subcriticality dimensions and to their compliance with: — geometrical dimensions specified in the design (design dimensions), or, — actual dimensions. This document is applicable to nuclear facilities containing fissile materials, except nuclear power reactor cores. This document can also be applied to the transport of fissile materials outside the boundaries of nuclear establishments. Subcriticality dimension control based on dimensions and layout of fuel assembly, fuel rods and fuel pellets are not covered by this document. This document does not specify requirements related to the control of fissile and non-fissile material compositions. The Quality Assurance associated with the fabrication and layout of the unit based on specifications (e.g. drawings elaborated during design) is a prerequisite of this document. The Quality Assurance is important to ensure the consistency between the unit geometry, its general purpose and its intended function.

Nuclear criticality safety — Geometrical dimensions for subcriticality control — Equipment and layout

ASTM C1453-19 核能级二氧化铀粉末和颗粒的点火和铀氧（O/U）原子比测定铀的标准测试方法

1.1 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear grade uranium dioxide powder and pellets. 1.2 This test method does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this test method does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. 1.3 This test method also is applicable to UO3 and U3O8 powder. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 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 Test Method for the Determination of Uranium by Ignition and the Oxygen to Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets

ASTM C799-19 核级硝酸铀溶液的化学 质谱 光谱 核和放射化学分析的标准测试方法

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 8 Specific Gravity by Pycnometry 16 – 21 Free Acid by Oxalate Complexation 22 – 28 Determination of Thorium 29 Determination of Chromium 30 Determination of Molybdenum 31 Halogens Separation by Steam Distillation 32 – 36 Fluoride by Specific Ion Electrode 37 – 43 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 44 Determination of Chloride and Bromide 45 Determination of Sulfur by X-Ray Fluorescence 46 Sulfate Sulfur by (Photometric) Turbidimetry 47 Phosphorus by the Molybdenum Blue (Photometric) Method 55 – 62 Silicon by the Molybdenum Blue (Photometric) Method 63 – 70 Carbon by Persulfate Oxidation-Acid Titrimetry 71 Conversion to U3O8 72 – 75 Boron by Emission Spectrography A Impurity Elements by Spark Source Mass Spectrography 77 Isotopic Composition by Thermal Ionization Mass Spectrometry 78 Uranium-232 by Alpha Spectrometry 79 – 85 Total Alpha Activity by Direct Alpha Counting 86 – 92 Fission Product Activity by Beta Counting 93 – 99 Entrained Organic Matter by Infrared Spectrophotometry 100 Fission Product Activity by Gamma Counting 101 Determination of Arsenic 102 Determination of Impurities for the EBC Calculation 103 Determination of Technetium 99 104 Determination of Plutonium and Neptunium 105 A Discontinued July 2019. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 6. 1.5 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 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions

BS EN ISO 12800:2019 核燃料技术 BET法测量氧化铀粉末比表面积的指南

What is ISO 12800 - Specific surface area of uranium oxide powders about?   ISO 12800 is an International Standard on nuclear fuel technology.   ISO 12800 specifies guidelines on the determination of the specific surface area of as-fabricated uranium dioxide powder by volumetric or gravimetric determination of the amount of nitrogen adsorbed on the powder. It can be applied to other similar materials, e.g. U3O8, UO2-PuO2 powders, and other bodies with similar surface areas, e.g. powder granules or green pellets, provided that the conditions described are fulfilled. Modifications using other adsorbing gases are included.   The method in ISO 12800 ...

Nuclear fuel technology. Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method

ASTM C1883-19 气体浓缩六氟化铀取样的标准实施规程

1.1 This practice covers the methods for withdrawing samples of enriched uranium hexafluoride (UF6) during and after a transfer occurring in the gas phase in order to determine compliance with Specification C996. It is applicable to the filling of a transport UF6 container (30B cylinder or 1 m3 vertical container) at a centrifuge enrichment facility that has been fed with UF6 that complies with Specification C787. 1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent, for example, contamination with irradiated material). 1.3 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. 1.4 The scope of this practice does not include provisions for preventing criticality incidents. 1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 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 Practice for Sampling of Gaseous Enriched Uranium Hexafluoride