F40 核材料、核燃料综合 标准查询与下载

ASTM C1009-06 制定核工业化学分析实验室质量保证计划的标准指南

1.1 This guide covers the establishment of a quality assurance (QA) program for analytical chemistry laboratories within the nuclear industry. Reference to key elements of ANSI/ISO/ASQC Q9001, Quality Systems, provides guidance to the functional aspects of analytical laboratory operation. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program.1.2 The essential, basic elements of a laboratory QA program appear in the following order:

Standard Guide for Establishing a Quality Assurance Program for Analytical Chemistry Laboratories Within the Nuclear Industry

ASTM C1636-06a 六氟化铀中铀232测定的标准指南

The method is applicable to the analysis of materials to demonstrate compliance with the specifications set forth in Specifications C 787 and C 996.1.1 This method covers the determination of 232U in uranium hexafluoride by alpha spectrometry.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 to determine the applicability of regulatory limitations prior to use.

Standard Guide for the Determination of Uranium-232 in Uranium Hexafluoride

ASTM C1636-06 六氟化铀中铀232测定的标准指南

1.1 This method covers the determination of 232U in uranium hexafluoride by alpha spectrometry.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 to determine the applicability of regulatory limitations prior to use.

Standard Guide for the Determination of Uranium-232 in Uranium Hexafluoride

ASTM C1210-06 制定核工业分析化学实验室用测量系统质量控制计划的标准指南

1.1 This standard provides guidance for establishing and maintaining a measurement system quality control program. Guidance is provided for general program considerations, preparation of quality control samples, analysis of quality control samples, quality control data analysis, analyst qualification, measurement system calibration, measurement method qualification, and measurement system maintenance.1.2 This guidance is provided in the following sections:

Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within the Nuclear Industry

ASTM C787-06 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 UF6 (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

ISO 11483:2005 核燃料技术.钚源的制备以及利用α谱仪测定238Pu/239Pu同位素比值

This International Standard describes three simple and fast procedures to prepare plutonium sources and a procedure to measure the activity ratio of Pu to (Pu + Pu) by α spectrometry. The α spectrometry method is used for the determination of isotopic abundance of Pu in combination with mass spectrometry and eliminates the possible interferences of U in the latter method. It applies to the analysis of purified solutions of plutonium in 2 mol/l to 4 mol/l nitric acid containing 50 μg to 200 μg of plutonium per millilitre, as may result from the chemical treatment and purification preceding plutonium isotopic analysis by mass spectrometry. This International Standard applies to plutonium solutions free from Am and those containing less than 10% of other non-volatile impurities relative to the plutonium content. Anion exchange chromatography in accordance with ISO 8299:1993 , Subclauses 7.2 and 7.3, or solvent extraction chromatography in ISO 15366 are suitable purification methods. The methods given in this International Standard are intended for use in conjunction or in parallel with mass spectrometry for the isotopic analysis of plutonium in spent-fuel solutions or nuclear-grade plutonium products.

Nuclear fuel technology - Preparation of plutonium sources and determination of <(hoch)238>Pu/<(hoch)239>Pu isotope ratio by alpha spectrometry

BS ISO 14943:2004 核能源.核燃料技术.临界安全的相关管理标准

This International Standard provides criteria for the administration of nuclear criticality-safety-related activities for operations which take place outside of reactors and for which there exists a potential for criticality accidents. The responsibilities of management, supervision, and the nuclear criticality-safety staff are addressed. The Objectives and characteristics of operating and emergency procedures are included in this International Standard.

Nuclear energy - Nuclear fuel technology - Administrative criteria related to criticality safety

ISO 16796:2004 核能.感应耦合等离子体源原子辐射光谱测定法(ICP-AES)测定钆燃料混合物和钆燃料丸中三氧化二钆的含量

This International Standard is applicable to the determination of Gd2O3 in powder blends and sintered pellets of Gd2O3 + UO2 from 1 % to 10 %, by the ICP-AES method.

Nuclear energy - Determination of Gd₂O₃ content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES)

EJ/T 1173-2004 铀矿山闭坑地质报告编写规范

本标准规定了铀矿山闭境地质报告的性质和用途及其编写要求等内容。 本标准适用于铀矿山闭坑地质报告(以下简称闭坑地质报告) 的编写。

Specifications for drafting geological report on closed pit of uranium mines

EJ/T 1174-2004 铀矿勘查地质报告编写规范

本标准规定了钠矿勘查地质报告的性质和用途及其编写要求等内容。 本标准适用于铀矿勘查地质报告《以下简称勘查地质报告) 的编写。

Specifications for drafting geological report on uranium exploration

NF M60-320:2004 核能.核燃料技术.废弃物.用液体闪烁法测定废弃物中碳14活性

Nuclear energy - Nuclear fuel technology - Waste - Determination of carbone 14 activity in waste by liquid scintillation.

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 C1592-04 无损分析测量的标准指南

1.1 This guide is a compendium of Good Practices for performing measurements of radioactive material using nondestructive assay (NDA) instruments. The primary purpose of the guide is to assist its users in arriving at quality NDA results, that is, results that satisfy the end users needs. This is accomplished by providing an acceptable and uniform basis for the collection, analysis, comparison, and application of data. The recommendations are not compulsory or pre requisites to achieving quality NDA measurements, but are considered contributory in most areas.1.2 This guide applies to the use of NDA instrumentation for the measurement of nuclear materials by the observation of spontaneous or stimulated nuclear radiations, including photons, neutrons, or the flow of heat. Recommended calibration, operating, and assurance methods represent guiding principles based on current NDA technology. The diversity of industry-wide nuclear materials measurement applications and instrumentation precludes discussion of specific measurement situations. As a result, compliance with practices recommended in this guide must be based on a thorough understanding of contributing variables and performance requirements of the specific measurement application.1.3 Selection of the best instrument for a given measurement application and advice on the use of this instrument must be provided by a qualified NDA professional following guidance provided in Guide C 1490. This guide is to be used as a reference, and to supplement the critical thinking, professional skill, expert judgement, and experimental test and verification needed to ensure that the instrumentation and methods have been properly implemented.1.4 The intended audience for this guide includes but is not limited to Management, Auditor Support, NDA Qualified Instrument Operators, NDA Technical Specialists, and NDA Professionals.

Standard Guide for Nondestructive Assay Measurements

ASTM C1188-04 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.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.1.2 The basic elements of a quality assurance program appear in the following order:FUNCTIONSECTIONOrganizationQuality Assurance ProgramDesign ControlInstructions, Procedures DrawingsDocument ControlProcurementIdentification and TraceabilityProcesses Inspection Control of Measuring and Test EquipmentHandling, Storage and Shipping Inspection, Test and Operating Status Control of Nonconforming Items Corrective Actions Quality Assurance Records Audits

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

ISO 12800:2003 核燃料技术.氧化铀粉末比表面积的BET测量方法指南

This International Standard covers 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, and 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.

Nuclear fuel technology - Guide to the measurement of the specific surface area of uranium oxide powders by the BET method

ASTM C1133-03 分段无源γ射线扫描法对低密度废料及残渣中特殊核材料进行无损检验的标准试验方法

Segmented gamma-ray scanning provides a nondestructive means of measuring the nuclide content of scrap and waste where the specific nature of the matrix and the chemical form and relationship between the nuclide and matrix may be unknown. The procedure can serve as a diagnostic tool that provides a vertical profile of transmission and nuclide concentration within the item. Sample preparation is generally limited to good waste/scrap segregation practices that produce relatively homogeneous items that are required for any successful waste/inventory management and assay scheme, regardless of the measurement method used. Also, process knowledge should be used, when available, as part of a waste management program to complement information on sample parameters, container properties, and the appropriateness of calibration factors.1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3).1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9,10).1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning (SGS) procedure: (1) Isotope Specific (Mass) Calibration, the original SGS procedure, uses standards of known radionuclide masses to determine detector response in a mass versus corrected count rate calibration that applies only to those specific radionuclides for which it is calibrated, and (2) Efficiency Curve Calibration, an alternative method, typically uses non-SNM radionuclide sources to determine system detection efficiency vs. gamma energy and thereby calibrate for all gamma-emitting radionuclides of interest (11). These two methods will be covered in detail in the remainder of the main body of this test method and Annex A1.1.2.1.1 Efficiency Curve Calibration, over the energy range for which the efficiency is defined, has the advantage of providing calibration for many gamma-emitting nuclide for which half-life and gamma emission intensity data are available.1.3 The assay technique may be applicable to loadings up to several hundred grams of nuclide in a 208-L (55-gal) drum, with more restricted ranges to be applicable depending on specific packaging and counting equipment considerations.1.4 Measured transmission values must be available for use in calculation of segment-specific attenuation corrections at the energies of analysis.1.5 A related method, SGS with calculated correction factors based on sample content and density, is not included in this standard.1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.7 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.

Standard Test Method for Nondestructive Assay of Special Nuclear Material in Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning

ASTM C982-03 能量扩散的X射线荧光系统的构件选择标准指南

This guide describes typical prospective analytical X-ray fluorescence systems that may be used for qualitative and quantitative elemental analysis of materials related to the nuclear fuel cycle. Standard methods for the determination of materials using energy-dispersive XRF5 usually employ apparatus with the components described in this document.1.1 This guide describes the components for an energy-dispersive X-ray fluorescence (XRF) system for materials analysis. It can be used as a reference in the apparatus section of test methods for energy-dispersive X-ray fluorescence analyses of nuclear materials.1.2 The components recommended include X-ray detectors, signal processing electronics, data acquisition and analysis systems, and excitation sources that emit photons (See ).1.3 Detailed data analysis methods are not described or recommended, as they may be unique to a particular analysis problem. Some applications may require the use of spectrum deconvolution to separate partially resolved peaks or to correct for matrix effects in data reduction.1.4 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 Guide for Selecting Components for Energy-Dispersive X-Ray Fluorescence (XRF) Systems

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 C1561-03 Alpha光谱测定法测量六氟环氧丙烷铀中钚和镎的标准指南

The method is applicable to the analysis of materials to demonstrate compliance with the specifications set forth in Specifications C 787 and C 996.1.1 This method covers the determination of plutonium and neptunium isotopes in uranium hexafluoride by alpha spectroscopy. The method could also be applicable to any matrix that may be converted to a nitric acid system.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 requirements prior to use.

Standard Guide for Determination of Plutonium and Neptunium in Uranium Hexafluoride by Alpha Spectrometry

EJ/T 1157-2002 地浸砂岩型铀矿地质勘查规范

本标准规定了地没砂岩型铀矿地质勘查的目的任务、勘查工作程度、勘查控制程度、勘查工作质重、 可行性评价工作、 铀矿资源/储量分类及类型条件、 铀矿资源/储重估算等. 本标准适用于地浸砂岩型铀矿地质勘查各阶段的工作-

Exploration specifications on in-situ leaching sandstone type uranium deposits