27.120.30 (Fissile materials and nuclear fuel tech 标准查询与下载

ASTM C1254-99(2005) 用X射线荧光法测定无机酸中铀的标准试验法

This test method is applicable to aqueous solutions of uranium containing 0.05 to 20 g uranium per litre of solution presented to the spectrometer. Either wavelength-dispersive or energy-dispersive X-ray fluorescence systems may be used provided the software accompanying the system is able to accommodate the use of internal standards.1.1 This test method covers the steps necessary for the preparation and analysis by X-ray fluorescence (XRF) of mineral acid solutions containing uranium. 1.2 This test method is valid for those solutions containing 2 to 20 g uranium/L as presented to the spectrometer. Higher concentrations may be covered by appropriate dilutions. 1.3 This test method requires the use of an appropriate internal standard. Care must be taken to ascertain that samples analyzed by this test method do not contain the internal standard element or that this contamination has been corrected for mathematically whenever present. Such corrections are not addressed in this test method. Care must also be taken that the choice of internal standard and sample medium are compatible; that is, do not use yttrium with solutions containing HF or strontium with those having H 2 SO 4 . Alternatively a scatter line may be used as internal standard. 1.4 The values stated in SI units are to be regarded as the standard. 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. Specific precautionary statements are given in Section 8 and Note 1.

Standard Test Method for Determination of Uranium in Mineral Acids by X-Ray Fluorescence

ASTM C1432-99 测定钚中杂质的标准试验方法:酸溶解、离子交换矩阵分离和感应耦合等离子体-原子发射光谱法(ICP/AES)分析

1.1 This test method covers the determination of 25 elements in plutonium (Pu) materials. The Pu is dissolved in acid, the Pu matrix is separated from the target impurities by an ion exchange separation, and the concentrations of the impurities are determined by inductively coupled plasma-atomic emission spectroscopy (ICP-AES). The elements determined are listed in Table 2. 1.2 This test method is specific for the determination of impurities in Pu in 8 M nitric acid (HNO3) solutions. Impurities in other plutonium materials, including plutonium oxide samples, may be determined if they are appropriately dissolved (see Practice C 1168) and converted to 8 M HNO3 solutions. 1.3 Plutonium bearing materials are radioactive and toxic. Adequate laboratory facilities, glove boxes, and fume hoods, along with safe techniques, must be used in handling samples containing these materials. A detailed discussion of all the precautions necessary is beyond the scope of this test method; however, personnel who handle these materials should be familiar with such safe handling practices. 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.

Standard Test Method for Determination of Impurities in Plutonium: Acid Dissolution, Ion Exchange Matrix Separation, and Inductively Coupled Plasma-Atomic Emission Spectroscopic (ICP/AES) Analysis

ASTM C968-99 烧结氧化钆及二氧化铀丸粒的分析方法

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: Sections Carbon (Total) by Direct Combustion-Thermal Conductivity Method 6 to 15 Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method 16 to 22 Gadolinis Content by Energy-Dispersive X-Ray Spectrometry 23 to 32 Hydrogen by Inert Gas Fusion 33 to 40 Isotopic Uranium Composition by Multiple-Filament Surface- Ionization Mass Spectrometric Method 41 to 49 Nitrogen by Distillation-Nessler Reagent (Photometric) Method 50 to 60 Oxygen-to-Metal Ratio of Sinterod Gadolinium Oxide-Uranium Dioxide Pellets 61 to 70 Spectrochemical Determination of Trace Impurity Elements 71 to 77 Total Gas by Hot Vacuum Extraction 78 to 85 Ceramographic Determination of Free Gd2O3 and Free UO2 to Estimate the Homogeneity of (U,Gd)O2 Pellets 86 to 93 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

ASTM C753-99 核纯级的可烧结的二氧化铀粉末标准规范

1.1 This specification covers nuclear-grade, sinterable uranium dioxide powder. It applies to uranium dioxide powder containing uranium of any 235 U concentration for use in nuclear reactors. 1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for commercial grade UO 2 . Such commercial grade UO 2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium. UO 2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design. 1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification 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. 1.4 Special tests and procedures are given in Annex A1. 1.5 This specification refers expressly to UO 2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions, sampling procedures or allowable impurity contents, or both, may need to be modified by agreement between the buyer and the seller. 1.6 The following safety hazards caveat pertains to the test methods portion in the annexes of this specification: 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 Nuclear-Grade, Sinterable Uranium Dioxide Powder

ASTM C1441-99 用傅里叶转换红外(FTIR)光谱分析六氟化铀中制冷剂114加上其它含碳和含氟化合物的标准试验方法

1.1 This test method covers determining the concentrations of refrigerant-114, other carbon-containing and fluorine-containing compounds, hydrocarbons, and partially or completely substituted halohydrocarbons that may be impurities in uranium hexafluoride. The two options are outlined for this test method. They are designated as Part A and Part B. 1.1.1 To provide instructions for performing Fourier-Transform Infrared (FTIR) spectroscopic analysis for the possible presence of Refrigerant-114 impurity in a gaseous sample of uranium hexafluoride, collected in a "2S" container or equivalent at room temperature. The all gas procedure applies to the analysis of possible Refrigerant-114 impurity in uranium hexafluoride, and to the gas manifold system used for FTIR applications. The pressure and temperatures must be controlled to maintain a gaseous sample. The concentration units are in mole percent. This is Part A. 1.2 Part B involves a high pressure liquid sample of uranium hexafluoride. This method can be applied to the limits of detection for hydrocarbons, chlorocarbons, and partially or completely substituted halohydrocarbons as specified in Method C 996. The limits of detection are in units of mole percent concentration. 1.3 Part A pertains to Sections 7-10 and Part B pertains to sections 12-16. 1.4 These test options are applicable to the determination of hydrocarbons, chlorocarbons, and partially or completely substituted halohydrocarbons contained as impurities in uranium hexafluoride (UF6). Gases such as carbon tetrafluoride (CF4), which absorb infrared radiation in a region where uranium hexafluoride also absorbs infrared radiation, cannot be analyzed via these methods due to spectral overlap/interference. 1.5 These test options are quantitative and applicable in the concentration ranges from 0.0001 to 0.100 mole percent, depending on the analyte. 1.6 These test methods can also be used for the determination of non-metallic fluorides such as silicon tetrafluoride (SiF4), phosphorus pentafluoride (PF5), boron trifluoride (BF3), and hydrofluoric acid (HF), plus metal-containing fluorides such as molybdenum hexafluoride (MoF6). The availabilty of high quality standards for these gases is necessary for quantitative analysis. 1.7 These methods can be extended to other carbon-containing and inorganic gases as long as: 1.7.1 There are not any spectral interferences from uranium hexafluoride's infrared absorbances. 1.7.2 There shall be a known calibration or known "K" (value[s]) for these other gases. 1.8 The values stated in SI units are to be regarded as the standard. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for the Analysis of Refrigerant 114, Plus Other Carbon-Containing and Fluorine-Containing Compounds in Uranium Hexafluoride via Fourier-Transform Infrared (FTIR) Spectroscopy

ASTM C1008-99 烧结二氧化铀钚丸的标准规范.快速反应堆燃料

1.1 These test methods cover procedures for testing rigid electrical insulation normally manufactured in flat sheet or plate form. They are generally used as terminal boards, spacers, voltage barriers, and circuit boards. Note 18212;For tests applying to vulcanized fiber reference should be made to Test Methods D 619. Note 28212;This standard resembles IEC 60893-2, Specification for Rigid Industrial Laminated Sheets Based On Thermosetting Resins for Electrical Purpose, Methods of Tests.1.2 The test methods appear in the following sections:TestSectionsASTM Test MethodAcetone extractable matter 83 to 84D 494Arc resistance47 D 495Ash56 to 60 ...Bonding strength49 to 54...Burning rate and flame resistance61 to 75...Compressive strength25 D 695Conditioning4 D 6054Dissipation factor34 to 40D 669Dielectric strength28 to 33D 149Expansion (linear thermal)76D 696Flexural properties12 to 24D 790Hardness (Rockwell)55 D 785Insulation resistance and resistivity41 to 46D 257Permittivity34 to 40D 150Resistance to impact26 D 256Tensile properties7 to 11D 638Thickness5 to 6D 374Tracking resistance48 D 2132Warp or twist77 to 82...Water absorption27 D 5701.3 The values stated in inch-pound units are to be regarded as the standard. The metric equivalents of inch-pound units given in these test methods may be approximate.1.4 This is a fire-test-response standard. See Sections 61 through 75, which are the procedures for burning rate and flame resistance.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. Specific precautionary statements are given in 31.1 and 61.5.

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets-Fast Reactor Fuel

ASTM C799-99(2005) 核纯级硝酸铀酰溶液的化学的、质谱的、光谱化学的、核(放射性)及放射化学分析的标准试验方法

Uranyl nitrate solution is used as a feed material for conversion to the hexafluoride as well as for direct conversion to the oxide. In order to be suitable for this purpose, the material must meet certain criteria for uranium content, isotopic composition, acidity, radioactivity, and impurity content. These methods are designed to show whether a given material meets the specifications for these items described in Specification C 788. 3.1.1 An assay is performed to determine whether the material has the specified uranium content. 3.1.2 Determination of the isotopic content of the uranium is made to establish whether the effective fissile content is in accordance with the purchaserrsquo;specifications. 3.1.3 Acidity, organic content, and alpha, beta, and gamma activity are measured to establish that they do not exceed their maximum limits. 3.1.4 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. Impurity concentrations are also required for calculation of the equivalent boron content (EBC), and the total equivalent boron content (TEBC).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: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. Specific precautionary statements are given in Section 5.

Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions

ASTM C696-99 核纯级二氧化铀粉末及丸的化学、质谱及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 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 7 to 15 Dichromate Titration Method Uranium and Oxygen Uranium Atomic Ratio by the Ignition 16 to 22 (Gravimetric) Impurity Correction Method Carbon (Total) by Direct Combustion-Thermal Conductivity 23 to 32 Method Total Chlorine and Fluorine by Pyrohydrolysis Ion-Selective 33 to 39 Electrode Method Moisture by the Coulometric, Electrolytic Moisture Analyzer 40 to 47 Method Nitrogen by the Kjeldahl Method 48 to 55 Isotopic Uranium Composition by Multiple-Filament Surface- Ionization Mass Spectrometric Method Spectrochemical Determination of Trace Elements in High-Purity 56 to 63 Uranium Dioxide Silver, Spectrochemical Determination of, by Gallium Oxide 64 to 65 Carrier D-C Arc Technique Rare Earths by Copper Spark-Spectrochemical Method 66 to 75 Impurity Elements by a Spark-Source Mass Spectrographic 76 to 82 Method Surface Area by Nitrogen Absorption Method 83 to 89 Total Gas in Reactor-Grade Uranium Dioxide Pellets 90 to 97 Thorium and Rare Earth Elements by Spectroscopy 98 to 105 Hydrogen by Inert Gas Fusion 106 to 115 Uranium Isotopic Analysis by Mass Spectrometry 116 to 124

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

ASTM C1431-99(2005) 维护容器清理用铝基废核燃料腐蚀检验的标准导则

1.1 This guide covers corrosion testing of aluminum-based spent nuclear fuel in support of geologic repository disposal (per the requirements in 10 CFR 60 and 40 CFR 191). The testing described in this document is designed to provide data for analysis of the chemical stability and radionuclide release behavior of aluminum-based waste forms produced from aluminum-based spent nuclear fuels. The data and analyses from the corrosion testing will support the technical basis for inclusion of aluminum-based spent nuclear fuels in the repository source term. Interim storage and transportation of the spent fuel will precede geologic disposal; therefore, reference is also made to the requirements for interim storage (per 10 CFR 72) and transportation (per 10 CFR 71). The analyses that will be based on the data developed are also necessary to support the safety analyses reports (SARs) and performance assessments (PAs) for disposal systems. 1.2 Spent nuclear fuel that is not reprocessed must be safely managed prior to transportation to, and disposal in, a geologic repository. Placement is an interim storage facility may include direct placement of the irradiated fuel or treatment of the fuel prior to placement, or both. The aluminum-based waste forms may be required to be ready for geologic disposal, or road ready, prior to placement in extended interim storage. Interim storage facilities, in the United States, handle fuel from civilian commercial power reactors, defense nuclear materials production reactors, and research reactors. The research reactors include both foreign and domestic reactors. The aluminum-based fuels in the spent fuel inventory in the United States are primarily from defense reactors and from foreign and domestic research reactors. The aluminum-based spent fuel inventory includes several different fuel forms and levels of 235U enrichment. Highly enriched fuels (235U enrichment leves 062 20%) are part of this inventory. 1.3 Knowledge of the corrosion behavior of aluminum-based spent nuclear fuels is required to ensure safety and to support licensing or other approval activities, or both, necessary for disposal in a geologic repository. The response fo the aluminum-based spent nuclear fuel waste form(s) to disposal environments must be established for configuration-safety analyses, criticality analyses, PAs, and other analyses required to assess storage, treatment, transportation, and disposal of spent nuclear fuels. This is particularly important for the highly enriched, aluminum-based spent nuclear fuels. The test protocols described in this guide are designed to establish material response under the repository relevant conditions. 1.4 The majority of the aluminum-based spent nuclear fuels are aluminum clad, aluminum-uranium alloys. The aluminum-uranium alloy typically consists of uranium aluminide particles dispersed in an aluminum matrix. Other aluminum-based fuels include dispersions of uranium oxide, uranium silicide, or uranium carbide particles in an aluminum matrix. These particles, including the aluminides, are generally cathodic to the aluminum matrix. Selective leaching of the aluminum in the exposure environment may provide a mechanism for redistribution and relocation of the uranium-rich particles. Particle redistribution tendencies will depend on the nature of the aluminum corrosion processes and the size, shape, distribution and relative reactivity of the uranium-rich particles. Interpretation of test data will require an understanding of the material behavior. This understanding will enable evaluation of the design and configuration of the waste package to ensure that unfilled regions in the waste package do not provide sites for the relocation of the uranium-rich particles into nuclear critical configurations. Test samples must be evaluated, prior to testing, to ensure that the size and shape of the uranium-rich particles in the test samples are......

Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal

ASTM C1429-99(2009) 采用双标准多收集器气体质谱仪进行六氟化铀同位素分析的标准试验方法

Uranium hexafluoride used to produce nuclear-reactor fuel must meet certain criteria for its isotopic composition. This test method may be used to help determine if sample materials meet the criteria described in Specifications C 787 and C 996.1.1 This test method covers a quantitative test method applicable to determining the mass percent of uranium isotopes in uranium hexafluoride (UF6) samples. This method as described is for concentrations of 235U between 0.1 and 10 mass %, and 234U and 236U between 0.0001 and 0.1 mass %. 1.2 This test method is for laboratory analysis by a gas mass spectrometer with a multi-collector. 1.3 This standard complements Test Methods C 761, sections 35 through 40, the double-standard method for gas mass spectrometers using a single collector, by providing a method for spectrometers using a multi-collector. 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.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Double-Standard Multi-Collector Gas Mass Spectrometer

ASTM C889-99 核纯级的氧化钆(Gd2O3)粉末的化学和质量光谱分析标准试验方法

1.1 These test methods cover procedures for the chemical and mass spectrographic 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 Combustion---Thermal Conductivity 7 to 16 Total Chlorine and Fluorine by Pyrohydrolysis Ion- 17 to 23 Selective Electrode Loss of Weight on Ignition 24 to 30 Sulfur by Combustion---Iodometric Titration 31 to 38 Impurity Elements by a Spark-Source Mass Spectrographic 39 to 45 Gadolinium Content in Gadolinium Oxide by Impurity 46 to 49 Correction 1.2 This standard does not purport to address all of the safety problems 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.

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

ASTM C1429-99(2009)e1 用双标准多收集器气体质谱仪进行六氟化铀同位素分析标准试验方法

Uranium hexafluoride used to produce nuclear-reactor fuel must meet certain criteria for its isotopic composition. This test method may be used to help determine if sample materials meet the criteria described in Specifications C 787 and C 996.1.1 This test method covers a quantitative test method applicable to determining the mass percent of uranium isotopes in uranium hexafluoride (UF6) samples. This method as described is for concentrations of 235U between 0.1 and 10 mass %, and 234U and 236U between 0.0001 and 0.1 mass %. 1.2 This test method is for laboratory analysis by a gas mass spectrometer with a multi-collector. 1.3 This standard complements Test Methods C 761, the double-standard method for gas mass spectrometers using a single collector, by providing a method for spectrometers using a multi-collector. 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.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Double-Standard Multi-Collector Gas Mass Spectrometer

ASTM C1108-99 控制电势库仑法测定钚的试验方法

1.1 This test method describes the determination of plutonium in solutions of unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 HNO 3 , 1 HClO 4 , 1 HCl, 5 HCl, and 0.5 H 2 SO 4 . Limitations on the use of selected supporting electrolytes are discussed in Section 5. Optimum quantities of plutonium for this procedure are 5 to 10 mg. 1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials. 1.3 The values stated in SI units are to be regarded as the 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Plutonium by Controlled-Potential Coulometry

ASTM C1429-99 用双支架多收集器气体质谱仪进行六氟化铀的同位素分析的标准试验方法

1.1 This is a quantitative test method applicable to determine the mass percent of uranium isotopes in uranium hexafluoride (UF6) samples. This method as described is for concentrations of 235U between 0.1 and 10 mass percent, and 234U and 236U between 0.0001 to 0.1 mass percent. 1.2 This test method is for laboratory analysis by a gas mass spectrometer with a multi-collector. 1.3 This standard complements C 761, sections 35 through 40, the double-standard method for gas mass spectrometers using a single collector, by providing a method for spectrometers using a multi-collector. 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.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Double-Standard Multi-Collector Gas Mass Spectrometer

ASTM C799-99e1 核纯级硝酸铀酰溶液的化学的、质谱的、光谱化学的、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 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 Uranium by Ferrous Sulfate Reduction-Potassium 7 to 14 Dichromate Titrimetry Uranium by Ignition Gravimetry 15 to 21 Specific Gravity by Pycnometry 22 to 27 Free Acid by Oxalate Complexation 28 to 34 Thorium by the Arsenazo (III) (Photometric) Method 35 to 42 Chromium by the Diphenylcarbazide (Photometric) Method 43 to 49 Molybdenum by the Thiocyanate (Photometric) Method 50 to 56 Halogens Separation by Steam Distillation 57 to 61 Fluorine by Specific Ion Electrode 62 to 68 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by 69 to 75 Amperometric Microtitrimetry Bromine by the Fluorescein (Photometric) Method 76 to 84 Sulfate Sulfur by (Photometric) Turbidimetry 85 to 92 Phosphorus by the Molybdenum Blue (Photometric) Method 93 to 100 Silicon by the Molybdenum Blue (Photometric) Method 101 to 108 Carbon by Persulfate Oxidation-Acid Titrimetry 109 to 116 Impurities by Emission Spectroscopy 117 to 120 Boron by Emission Spectrography 121 to 127 Impurity Elements by Spark Source Mass Spectrography 128 to 134 Isotopic Composition by Multiple Filament Surface-Ionization 135 to 140 Mass Spectrometry Uranium-232 by Alpha Spectrometry 141 to 147 Total Alpha Activity by Direct Alpha Counting 148 to 154 Fission Product Activity by Beta and Gamma Counting 155 to 161 Entrained Organic Matter by Infrared Spectrophotometry 162 to 174 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. Specific precautionary statements are given in Section 5.

Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions

ASTM C788-98 核纯级的硝酸铀酰溶液标准规范

1.1 This specification applies to nuclear-grade uranyl nitrate solution not exceeding 5% 235 U intended for subsequent manufacture into either UF6 (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors). 1.2 This specification is intended to provide the nuclear industry with a general standard for uranyl nitrate solution. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6 for subsequent processing. 1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment. 1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations (latest edition), Title 10, Part 50. 1.5 This standard does not purport to address all of the safety problems, 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 Nuclear-Grade Uranyl Nitrate Solution

ASTM C1408-98 用直接燃烧红外探测法测定氧化铀粉末和颗粒中总碳量的标准试验方法

1.1 This test method covers the determination of carbon in nuclear-grace uranium oxide powders and pellets to determine compliance with specifications. 1.2 Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method. 1.3 This test method covers the determination of 5 to 500 181g of residual carbon. 1.4 This test method describes an induction furnace carrier gas combustion system equipped with an infrared detector. It may also be applied to a similar instrument equipped with a thermal conductivity detector. 1.5 The preferred system of units is micrograms carbon per gram of uranium (181g/g U). 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 Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method

ASTM C697-98 核纯级二氧化钚粉末及丸的化学、质谱及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 nuclear-grade plutonium dioxide powders and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium Sample Handling 8 to 10 Plutonium by Controlled-Potential Coulometry 2 Plutonium by Ceric Sulfate Titration 20 to 27 Plutonium by Amperometric Titration with Iron(II) 2 Nitrogen by Distillation Spectrophotometry Using Nessler 37 to 44 Reagent Carbon (Total) by Direct Combustion-Thermal Conductivity 45 to 56 Total Chlorine and Fluorine by Pyrohydrolysis 57 to 64 Sulfur by Distillation Spectrophotometry 65 to 73 Plutonium Isotopic Analysis by Mass Spectrometry 3 Rare Earth Elements by Spectroscopy 82 to 89 Trace Elements by Carrier-Distillation Spectroscopy 90 to 97 Impurity Elements by Spark-Source Mass Spectrography 98 to 104 Moisture by the Coulometric Electrolytic Moisture Analyzer 105 to 112 Total Gas in Reactor-Grade Plutonium Dioxide Pellets 113 to 120 Plutonium-238 Isotopic Abundance by Alpha Spectrometry 121 to 128 Rare Earths By Copper Spark-Spectroscopy 129 to 138 Plutonium Isotopic Analysis by Mass Spectrometry 139 to 147 Oxygen-To-Metal Atom Ratio by Gravimetry 148 to 156 1.3 This standard does not purport to address all of the safety problems, 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 precautionary statements, see Sections 6, 41, 50, 153, and 86.9 and144.5.1.

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

ASTM C759-98 核纯级硝酸钚溶液的化学、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 the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry 2 Plutonium by Amperometric Titration with Iron (II) 2 Free Acid by Titration in an Oxalate Solution 16 to 23 Free Acid by Iodate Precipitation- Potentiometric Titration Test Method 24 to 30 Uranium by Arsenazo I Spectrophotometric Test Method 31 to 41 Thorium by Thorin Spectrophotometric Test Method 42 to 50 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 51 to 58 Chloride by Thiocyanate Spectrophotometric Test Method 59 to 66 Fluoride by Distillation-Spectrophotometric Test Method 67 to 74 Sulfate by Barium Sulfate Turbidimetric Test Method 75 to 82 Isotopic Composition by Mass Spectrometry 83 to 84 Americium-241 by Extraction and Gamma Counting 85 to 93 Americium-241 by Gamma Counting 94 to 102 Gamma-Emitting Fission Products, Uranium, and Thorium by Gamma-Ray Spectroscopy 103 to 110 Rare Earths by Copper Spark Spectrochemical Test Method 111 to 113 Tungsten, Niobium (Columbium), and Tantalum by Spectro-chemical Test Method 114 to 122 Sample Preparation for Spectrographic Analysis for General Impurities 123 to 126 1.3 This standard does not purport to address all of the safety problems, 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 hazard statements, see Section 5.

Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions

ASTM C1233-98 核材料中当量硼含量测量的标准规范

1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) values for elements that are of potential significance as thermal neutron poisons. The values are determined from a knowledge of the atomic weight of elements and the thermal neutron absorption cross section in barns. This practice is illustrated by using the EBC factors of Table 1 which are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy characteristics of the applicable reactor system.1.2 The following elements do not require to be included in the EBC calculations, as their EBC factors are less than or equal to 0.0001: aluminum; fluorine; rubidium; barium; lead; silicon; beryllium; neon; tin; bismuth; oxygen; zirconium; carbon; magnesium; cerium; phosphorus. Their contribution to the total poison effect is not considered significant.

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials