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

ASTM C996-04 235U低于5％的浓缩六氟化铀标准规范

1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any 235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF 6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, the parties concerned may agree to other appropriate conditions.1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O474.1).1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % ²³⁵U

ASTM C698-04 核纯级混合氧化物(UO2,PuO2)的化学、质谱及光谱化学分析标准试验方法

Mixed oxide, a mixture of uranium and plutonium oxides, is used as a nuclear-reactor fuel in the form of pellets. The plutonium content may be up to 10 weight %, and the diluent uranium may be of any 235U enrichment. In order to be suitable for use as a nuclear fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specification C 833. 3.1.1 The material is assayed for uranium and plutonium to determine whether the plutonium content is as specified by the purchaser, and whether the material contains the minimum combined uranium and plutonium contents specified on a dry weight basis. 3.1.2 Determination of the isotopic content of the plutonium and uranium in the mixed oxide is made to establish whether the effective fissile content is in compliance with the purchaserrsquo;specifications. 3.1.3 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 mixed oxides, (U, Pu)O2, powders and pellets to determine compliance with specifications.1.2 The analytical procedures appear in the following order: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 precaution statements, see Sections 11, 20, 64, and 112 and 102.6.1.)

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O₂)

ASTM C759-04 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

These test methods are designed to show whether a given material meets the purchaserrsquo;specifications. 3.1.1 An assay is performed to determine whether the material has the specified plutonium content. 3.1.2 Determination of the isotopic content of the plutonium in the plutonium-nitrate solution is made to establish whether the effective fissile content is in compliance with the purchaserrsquo;specifications. 3.1.3 Impurity content is determined by a variety of methods to ensure that the maximum concentration limit of specified impurities 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, 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: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. For specific safeguard and safety hazard statements, see Section 6.

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

ASTM C1188-04(2011) 制定铀转换装置的质量保证大纲的标准指南

Quality assurance provides a planned and systematic approach for establishing practices to meet requirements of safe facility operation and product quality. In the operation of a uranium conversion facility there are many requirements established by regulatory bodies, codes, customers, and the facility itself. These requirements are identified by facility management and acted upon by various facility groups. Implementation of the practices described in this guide are intended to assist with compliance with these requirements. In the operation of a uranium conversion facility there is a potential for both chemical and radiological exposure to employees, the public, and the environment. This potential is reduced by implementation of the practices described in this guide. The development of this guide, as part of sound management practice, provides a means for ensuring consistency between facilities, and documentation and formalization of existing practices. To establish a quality assurance program for a uranium conversion facility, the practices in use should be evaluated against the recommended practices of this guide. Existing practices may then be modified or new practices implemented to correct any identified deficiencies. This approach highlights the fact that the basic foundation of a quality assurance program is already present. ANSI/ASME NQA-1 is a quality assurance standard that is being applied broadly across the nuclear industry. NQA-1 was used as guidance in the development of the program elements of this guide. The program functions detailed in this guide should be selected based on the particular needs and applications at the facility. Those activities or programs to be included in a uranium conversion facility should be defined in that program.1.1 This guide provides guidance and recommended practices for establishing a comprehensive quality assurance program for uranium conversion facilities. 1.2 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 health and safety practices and determine the applicability of regulatory limitations prior to use. 1.3 The basic elements of a quality assurance program appear in the following order:

Standard Guide for Establishing a Quality Assurance Program for Uranium Conversion Facilities

ASTM C1380-04(2011) 用同位素稀释质谱仪测定铀含量和同位素成份的标准试验方法

Determination of percent uranium content and 235U abundance in oxides and other materials containing high concentrations of uranium is required for special nuclear materials accountability, regulatory requirements, and process control.1.1 This test method covers a method for the determination of the uranium concentration in uranium oxides by isotope dilution mass spectrometry (IDMS). The isotopic composition of the oxide is measured simultaneously. 1.2 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 Uranium Content and Isotopic Composition by Isotope Dilution Mass Spectrometry

ASTM C1441-04 用傅里叶转换红外(FTIR)光谱法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

This test method (Part A) utilizes FTIR spectroscopy to determine the percent Refrigerant-114 impurity in uranium hexafluoride. Refrigerant-114 is an example of an impurity gas in uranium hexafluoride. The detection of hydrocarbons, chlorocarbons, and partially or completely substituted halohydrocarbons in UF6 (Part B) is governed by the provisions in Specification C 996.1.1 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 C761-04e1 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

ASTM C761-04 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

ASTM C697-04 核纯级二氧化钚粉末及丸状材料的化学、质谱及光谱化学分析的标准试验方法

Plutonium dioxide is used in mixtures with uranium dioxide as a nuclear-reactor fuel. In order to be suitable for this purpose, the material must meet certain criteria for plutonium content, 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 Specification C 757. 3.1.1 An assay is performed to determine whether the material has the minimum plutonium content specified on a dry weight basis. 3.1.2 Determination of the isotopic content of the plutonium in the plutonium dioxide powder is made to establish whether the effective fissile content is in compliance with the purchaserrsquo;specifications. 3.1.3 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 plutonium dioxide powders and pellets 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. For specific precautionary statements, see Sections 6, 15, 24, 111, and 52.9 and 101.5.1.

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

ASTM C888-03 核纯级氧化钆(Gd₂0₃)粉末的标准规范

1.1 This specification provides the chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications, for example, as an addition to uranium dioxide.1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and comply with all federal, state, and local regulations pertaining to possessing, shipping, processing, or using this material.

Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd₂O₃) Powder

ASTM C787-03e2 浓缩用六氟化铀标准规范

1.1 This specification covers uranium hexafluoride (UF6) intended for feeding to an enrichment plant. Included are specifications for UF6 derived from unirradiated natural uranium and UF6 derived from irradiated uranium that has been reprocessed and converted to UF6 for enrichment and subsequent reuse. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Commercial Natural UF6 feedstock so that the corresponding enriched uranium is essentially equivalent to enriched uranium made entirely from virgin natural UF6; and (2) To define additional limits for Reprocessed UF 6 (or any mixture of Reprocessed UF6 and Commercial Natural UF6). For such UF6, special provisions may be needed to ensure that no extra hazard arises to the work force, process equipment, or the environment.1.2 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O 474.1).1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Specification for Uranium Hexafluoride for Enrichment

ASTM C787-03e1 浓缩用六氟化铀标准规范

1.1 This specification covers uranium hexafluoride (UF6) intended for feeding to an enrichment plant. Included are specifications for UF6 derived from unirradiated natural uranium and UF6 derived from irradiated uranium that has been reprocessed and converted to UF6 for enrichment and subsequent reuse. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Commercial Natural UF6 feedstock so that the corresponding enriched uranium is essentially equivalent to enriched uranium made entirely from virgin natural UF6; and (2) To define additional limits for Reprocessed UF 6 (or any mixture of Reprocessed UF6 and Commercial Natural UF6). For such UF6, special provisions may be needed to ensure that no extra hazard arises to the work force, process equipment, or the environment.1.2 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O 474.1).1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Specification for Uranium Hexafluoride for Enrichment

ASTM C1554-03 热室用物料搬运设备的标准指南

1.1 Intent:1.1.1 This guide covers materials handling equipment used in hot cells (shielded cells) for the processing and handling of nuclear and radioactive materials. The intent of this guide is to aid in the selection and design of materials handling equipment for hot cells in order to minimize equipment failures and maximize the equipment utility.1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, installation, maintenance, repair, replacement, and decontamination and decommissioning of materials handling equipment capable of meeting the stringent demands of operating, dependably and safely, in a hot cell environment where operator visibility is limited due to the radiation exposure hazards.1.1.3 This guide may apply to materials handling equipment in other radioactive remotely operated facilities such as suited entry repair areas and canyons, but does not apply to materials handling equipment used in commercial power reactors.1.1.4 This guide covers mechanical master-slave manipulators and electro-mechanical manipulators, but does not cover electro-hydraulic manipulators.1.2 Applicability:1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, e.g., without shielded viewing windows, periscopes, or a video monitoring system.1.3 User Caveats:1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance.1.3.1.1 The guidance set forth in this standard relating to design of equipment is intended only to alert designers and engineers to those features, conditions, and procedures that have been found necessary or highly desirable to the design, selection, operation and maintenance of reliable materials handling equipment for the subject service conditions.1.3.1.2 The guidance set forth results from discoveries of conditions, practices, features, or lack of features that were found to be sources of operational or maintenance problems, or causes of failure.1.3.2 This standard does not supersede federal and/or state regulations, or codes applicable to equipment under any conditions.1.3.3 This standard does not cover design features of the hot cell, e.g., windows, drains, and shield plugs. This standard does not cover pneumatic or hydraulic systems. Refer to Guides C 1533, C 1217, and ANS Design Guides for Radioactive Material Handling Facilities Equipment for information and references to design features of the hot cell and other hot cell equipment.1.3.4 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 Guide for Materials Handling Equipment for Hot Cells

ASTM C888-03(2014) 核纯级氧化钆(Gd203)粉末的标准规格

1.1 This specification provides the chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications, for example, as an addition to uranium dioxide. 1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and comply with all federal, state, and local regulations pertaining to possessing, shipping, processing, or using this material. 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-Grade Gadolinium Oxide 40;Gd2O341; Powder

ASTM C1432-03 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).1.2 This test method is specific for the determination of impurities in 8 M 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 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 C1432-03(2008) 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 specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C 753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %. 1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction to UO2 powder. This specification is applicable to uranium oxide powders for such use from any source. 1.3 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 specification does not relieve the user of the obligation to conform to all international, national, state, and local regulations for processing, shipping, or any other way of using uranium oxide powders (see 2.2 and 2.3). 1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.5 The following safety hazards caveat pertains only to the test methods portion of the annexes in 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 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 C1156-03 用于分析核燃料循环材料的测量方法用校准方法的确定的标准指南

Calibration is a fundamental part of making measurements and its effect on the quality of measurement data is significant. Thus, sufficient attention must be given to calibration when it is established for a measurement method so that the data produced will be acceptable. The use of an inappropriate calibration standard, inadequate instructions for calibration, and poor documentation of the calibration process are examples of circumstances that can adversely affect the validity of a calibration. Thus, the calibration process must conform to criteria established to ensure the validity of calibration results. Such criteria are given in Guide C 1009, in which calibration is identified as a component of laboratory quality assurance (see Fig. 1). This guide expands upon those criteria to provide more comprehensive guidance for establishing calibration. The manner of calibration and other technical requirements for calibrating a measurement method are usually established when a method is first introduced into a laboratory, which may be through validation and qualification as defined by Guide C 1068 (see Fig. 1). However, calibration involves more than the technical aspects of the calibration process. The other dimension of the process is the operational requirements that are necessary to ensure that calibration results are valid and that they are documented and verifiable should their integrity be questioned. The provisions of this guide provide those operational requirements and should be considered whenever calibration is planned and established. FIG. 1 Quality Assurance of Analytical Laboratory Data1.1 This guide provides the basis for establishing calibration for a measurement method typically used in an analytical chemistry laboratory analyzing nuclear materials. Guidance is included for such activities as preparing a calibration procedure, selecting a calibration standard, controlling calibrated equipment, and documenting calibration. The guide is generic and any required technical information specific for a given method must be obtained from other sources.1.2 The guidance information is provided in the following sections:SectionGeneral Considerations4Calibration Procedure5Calibration Standard6Control of Calibrated Equipment7Documentation8Keywords91.3 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 Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials

ASTM C1297-03 核燃料循环材料分析用实验室分析法的鉴定标准指南

This is one of a series of guides designed to provide guidance for implementing activities that meet the requirements of a sound laboratory quality assurance program. The first of these, Guide C 1009, is an umbrella guide that provides general criteria for ensuring the quality of analytical laboratory data. Other guides provide expanded criteria in various areas affecting quality, producing a comprehensive set of criteria for controlling data quality. The approach to ensuring the quality of analytical measurements described in these guides is depicted in Fig. 1. The training and qualification of analysts is one of the elements of laboratory quality assurance presented in Guide C 1009, which provides some general criteria regarding qualification. This guide expands on those criteria to provide more comprehensive guidance for qualifying analysts. As indicated in Guide C 1009, the qualification process can vary in approach; this guide provides one such approach. This guide describes an approach to analyst qualification that is designed to be used in conjunction with a rigorous program for the qualification and control of the analytical measurement system. This requires an existing data base which defines the characteristics (precision and bias) of the system in routine use. The initial development of this data base is described in Guide C 1068. The process described here is intended only to qualify analysts when such a data base exists and the method is in control. The qualification activities described in this guide assume that the analyst is already proficient in general laboratory operations. The training or other activities that developed this proficiency are not covered in this guide. This guide describes a basic approach and principles for the qualification of laboratory analysts. Users are cautioned to ensure that the qualification program implemented meets the needs and requirements of their laboratory. FIG. 1 Quality Assurance of Analytical Laboratory Data1.1 This guide covers the qualification of analysts to perform chemical analysis or physical measurements of nuclear fuel cycle materials. The guidance is general in that it is applicable to all analytical methods, but must be applied method by method. Also, the guidance is general in that it may be applied to initial qualification or requalification.1.2 The guidance is provided in the following sections:SectionQualification Considerations4Demonstration Process5Statistical Tests61.3 This standard does not apply to maintaining qualification during routine use of a method. Maintaining qualification is included in Guide C 1210.1.4 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 Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials

ASTM C1156-03(2011) 用于分析核燃料循环材料的测量方法用校准方法的确定的标准指南

Calibration is a fundamental part of making measurements and its effect on the quality of measurement data is significant. Thus, sufficient attention must be given to calibration when it is established for a measurement method so that the data produced will be acceptable. The use of an inappropriate calibration standard, inadequate instructions for calibration, and poor documentation of the calibration process are examples of circumstances that can adversely affect the validity of a calibration. Thus, the calibration process must conform to criteria established to ensure the validity of calibration results. Such criteria are given in Guide C1009, in which calibration is identified as a component of laboratory quality assurance (see Fig. 1). This guide expands upon those criteria to provide more comprehensive guidance for establishing calibration. The manner of calibration and other technical requirements for calibrating a measurement method are usually established when a method is first introduced into a laboratory, which may be through validation and qualification as defined by Guide C1068 (see Fig. 1). However, calibration involves more than the technical aspects of the calibration process. The other dimension of the process is the operational requirements that are necessary to ensure that calibration results are valid and that they are documented and verifiable should their integrity be questioned. The provisions of this guide provide those operational requirements and should be considered whenever calibration is planned and established.1.1 This guide provides the basis for establishing calibration for a measurement method typically used in an analytical chemistry laboratory analyzing nuclear materials. Guidance is included for such activities as preparing a calibration procedure, selecting a calibration standard, controlling calibrated equipment, and documenting calibration. The guide is generic and any required technical information specific for a given method must be obtained from other sources.

Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials

ASTM C788-03 核纯级硝酸铀酰溶液或晶体的标准规范

1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 % 235U 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 aqueous uranyl nitrate solution or crystals. 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 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 Uranyl Nitrate Solution or Crystals