27.120.30 裂变物质 标准查询与下载

EN ISO 18256-1:2021 核燃料技术.含二氧化钚材料的溶解.第1部分:二氧化钚粉末的溶解

Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)

EN ISO 9463:2021 核能.核燃料技术.分光光度法测定硝酸溶液中的钚

Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019)

EN ISO 16793:2021 核燃料技术.微观结构检查用烧结的二氧化铀丸状材料的陶瓷相准备指南

Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018)

T/CNS 43-2020 高温气冷堆核动力厂球形燃料元件设计准则

本文件规定了球床模块式高温气冷堆（简称高温气冷堆）核动力厂球形燃料元件设计应满足的要求。

Design criteria for the spherical fuel element of high temperature gas cooled reactor nuclear power plant

20/30415219 DC BS ISO 16796 核能 使用电感耦合等离子体源 (ICP-AES) 通过原子发射光谱法测定钆燃料混合物和钆燃料芯块中的 Gd2O3 含量

BS ISO 16796. 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)

ASTM C1205-20 通过Alpha光谱法测定土壤中Americ -241的标准测试方法

1.1 This test method covers the determination of 241 Am in soil by means of chemical separations and alpha spectrometry. It is designed to analyze up to 10 g of soil or other sample matrices that contain up to 30 mg of combined rare earths. This test method allows the determination of 241 Am concentrations from ambient levels to applicable standards. 1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Test Method for The Radiochemical Determination of Americium-241 in Soil by Alpha Spectrometry

ASTM E321-20 铀和钚燃料原子百分比分数的标准测试方法（钕-148法）

1.1 This test method covers the determination of stable fission product 148 Nd in irradiated uranium (U) fuel (with initial plutonium (Pu) content from 0 to 50 %) as a measure of fuel burnup (1-3).2 1.2 It is possible to obtain additional information about the uranium and plutonium concentrations and isotopic abundances on the same sample taken for burnup analysis. If this additional information is desired, it can be obtained by precisely measuring the spike and sample volumes and following the instructions in Test Method E267. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)

BS ISO 7195:2020 核能 六氟化铀（UF6）运输包装

Nuclear energy. Packagings for the transport of uranium hexafluoride (UF6)

ASTM E2089-15(2020) 空间应用材料的地面实验室原子氧相互作用评估标准实践

1.1 The intent of these practices is to define atomic oxygen exposure procedures that are intended to minimize variability in results within any specific atomic oxygen exposure facility as well as contribute to the understanding of the differences in the response of materials when tested in different facilities. 1.2 These practices are not intended to specify any particular type of atomic oxygen exposure facility but simply specify procedures that can be applied to a wide variety of facilities. 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Practices for Ground Laboratory Atomic Oxygen Interaction Evaluation of Materials for Space Applications

ISO 7195:2020 核能. 六氟化铀(UF6)的运输包装

This document provides the following: — specifications for cylinders for the transport of uranium hexafluoride (UF6) to provide compatibility among different users, — description of cylinder designs, but is not intended to develop new designs, — fabrication requirements for the procurement of new cylinders designed for the transport of 0,1 kg or more of uranium hexafluoride, — fabrication requirements for the procurement of new valve protections, valves and plugs, and — requirements for cylinders and valve protections in service.

Nuclear energy - Packagings for the transport of uranium hexafluoride (UF6)

ASTM C1411-20 在同位素分析前对铀和钚进行离子交换分离的标准实践

1.1 This practice is for the ion exchange separation of uranium and plutonium from each other and from other impurities for subsequent isotopic analysis by thermal ionization mass spectrometry. Plutonium-238 and uranium-238, and plutonium-241 and americium-241, will appear as the same mass peak and must be chemically separated prior to analysis. Only high purity solutions can be analyzed reliably using thermal ionization mass spectrometry. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis

ASTM C1217-00(2020) 核放射材料加工设备标准指南

1.1 Intent: 1.1.1 This guide covers equipment used in shielded cell or canyon facilities for the processing of nuclear and radioactive materials. It is the intent of this guide to set down the conditions and practices that have been found necessary to ensure against or to minimize the failures and outages of equipment used under the subject circumstances. 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, and installation of equipment capable of meeting the stringent demands of operating, dependably and safely, in a nuclear processing environment that operators can neither see nor reach directly. 1.1.3 This guide sets forth generalized criteria and guidelines for the design, fabrication, and installation of equipment used in this service. This service includes the processing of radioactive wastes. Equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. In the type of shielded cell or canyon facility of interest to users of this guide, either the background radiation level remains high at all times or it is impractical to remove the process sources of radiation to facilitate in situ repairs or carry out maintenance procedures on equipment. The equipment is operated remotely, either with or without visual access to the equipment. 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 longterm 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 material handled or processed must be retained, contained, and confined within known bounds for reasons of accountability or to minimize the spread of radioactive contamination. 1.2.1.4 The materials handled or processed must be kept and maintained within one or more of the following conditions: (1) In a specific geometric array or configuration, and (2) Within a range of conditions that have been determined to be a critically safe set of conditions for that piece of equipment, that is: (a) In a given and specified operational position where adjacent nuclear criticality interaction conditions are known and unchanging, (b) For a given and specified set or range of operating conditions, and (c) For a given and specified process. 1.2.1.5 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without intervening shielded viewing windows, periscopes, or a television monitoring system. 1.2.2 This guide is intended to be applicable to the design of equipment for the processing of materials containing uranium and transuranium elements in any physical form under the following conditions: 1.2.2.1 Such materials constitute an unacceptable radiation hazard to the operators and maintenance personnel, 1.2.2.2 The need exists for the confinement of the in-process material, of dusts and particulates, or of vapors and gases arising or resulting from the handling and processing of such materials, and 1.2.2.3 Any of the conditions cited in 1.2.1 apply. 1.2.3 This guide is intended to apply to the design, fabrication, and installation of ancillary and support services equipment under the following conditions: 1.2.3.1 Such equipment is installed in shielded cell or canyon environments, or 1.2.3.2 Such equipment is an integral part of an in-cell processing equipment configuration, or an auxiliary component or system thereof, even though an equipment item or system may not directly hold or contain nuclear or radioactive materials under normal processing conditions. 1 This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.09 on Nuclear Processing. Current edition approved July 1, 2020. Published July 2020. Originally approved in 2000. Last previous edition approved in 2012 as C1217 – 00 (2012). DOI: 10.1520/C1217-00R20. Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. 1 NOTE 1—Upsets, accidents, or certain emergency conditions may be specified (and thus required) design considerations, but not necessarily acceptable or normal operating circumstances under this definition. 1.2.4 This guide is intended to apply to the design and fabrication of any and all types of equipment for radioactive wastes processing when any of the conditions cited in 1.2.1 apply. This would include equipment for waste concentration; for incorporation of wastes in selected host materials or matrices; and for the fixation, encapsulation, or canning of such wastes. It is intended to apply to all such wastes, regardless of the product waste composition or form. The product radioactive waste may have a glass, ceramic, metallic, concrete, bituminous, or other type of host material or matrices (composition), and may be in pelletized, solid, or granular form. 1.3 User Caveats: 1.3.1 This guide 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 guide to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.3.2 (Warning—This guide pertains to equipment used in and for the handling and processing of nuclear and radioactive materials. These operations are known to be hazardous for a variety of reasons, one being chemical toxicity.) 1.3.3 This guide is not a substitute for applied engineering skills. Its purpose is to provide guidance. 1.3.3.1 The guidance set forth in this guide 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 acquisition of reliable equipment for the subject service conditions. 1.3.3.2 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 trouble, or causes of failure. 1.3.4 It is often necessary to maintain the materials being processed within specific chemical composition or concentration ranges, or both. When such constraints apply, it may also be necessary to create and maintain a specific geometric array to minimize the chances of a nuclear criticality incident. Designers and engineers are referred to other standards for additional guidance when such requirements apply. 1.3.5 Equipment usage intent, service conditions, size and configuration, plus the configuration and features of the operating and maintenance environments have an influence on equipment design. Therefore, not all of the criteria, conditions, caveats, or features would be applicable to every equipment item. 1.3.6 It is intended that equipment designed, fabricated, procured, or obtained by transfer or adaptation and re-use of existing equipment, and installed in accordance with this guide meet or exceed statutory, regulatory, and safety requirements for that equipment under the applicable operating and service conditions. 1.3.7 This guide does not supersede federal or state regulations, or both, and codes applicable to equipment under any conditions. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials

ASTM C1052-20 液体铀六氟化物的批量采样标准实践

1.1 This practice covers methods for withdrawing representative samples of liquid uranium hexafluoride (UF6) from bulk quantities of the material. Such samples are then prepared for further analytical testing in accordance with Practices C1689 and C1346. Multiple different methods are used for determining compliance with the applicable commercial specification, for example Specifications C787 and C996. Methods used for compliance to each of these standards can be found in the Referenced Documents section of each respective specification. 1.2 It is assumed that the bulk liquid UF6 being sampled comprises a single quality and quantity of material. This practice does not address any special additional arrangements that might be required for taking proportional or composite samples. When the sampled bulk material is being added to UF6 residues already in a container (“heels recycle”) additional arrangements are required to avoid cross contamination of the bulk UF6, these are addressed in Specifications C787 and C996. 1.3 The number of samples to be taken, their nominal sample weight, and their disposition shall be agreed upon between the parties. 1.4 The scope of this practice does not include provisions for preventing criticality incidents. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Practice for Bulk Sampling of Liquid Uranium Hexafluoride

ASTM D8325-20 用气体吸附测量法评定核石墨表面积和孔隙率的标准指南

1.1 The purpose of this Guide is to provide methodologic information specific to highly graphitized, low surface area materials used in the nuclear industry. It applies to nitrogen adsorption measurements at 77 K for the characterization of graphite pore structure, such as: (1) specific surface area; (2) cumulative volume of open pores (for pore sizes less than about 300 nm); and (3) distribution of pore volumes as a function of pore sizes (for pore sizes less than about 30 nm). These properties are related to graphite’s reactivity in oxidative environments, graphite’s ability to retain fission products, and gas transport through graphite’s pore system. 1.2 Characterization of surface area (also known as the Brunauer-Emmett-Teller “BET” method) and porosity in nuclear graphite by gas adsorption is challenged by nuclear graphite’s low specific surface area, weak adsorption interactions, and energetic and structural heterogeneity of surface sites in gas-accessible pores. This guide provides recommendations and practical information related to the nitrogen adsorption method, including guidance on specimen preparation, selection of experimental conditions, data processing, and interpretation of results. 1.3 Other porosity characterization methods used for nuclear graphite, such as krypton adsorption at 77 K, argon adsorption at either 77 K or 87 K, helium pycnometry (Test Method B923), and mercury intrusion porosimetry, are not in the scope of this guide. 1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Guide for Evaluation of Nuclear Graphite Surface Area and Porosity by Gas Adsorption Measurements

ASTM C787-20 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, 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 (for example, see TID-7016, DP-532, ORNLNUREG-CSD-6, and DOE O 474.1). 1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Uranium Hexafluoride for Enrichment

ASTM C967-20 铀精矿标准规范

1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium. 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 conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2). 1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Uranium Ore Concentrate

BS ISO 22946:2020 核临界安全 固体废物 不包括经过辐照和未经辐照的核燃料

What is ISO 22946 about?    ISO 22946 provides specific requirements and guidance on the nuclear criticality safety of waste containing fissile nuclides, generated during normal operations. This document is intended to be used alongside and in addition to ISO 1709 .   ISO 22946 applies specifically to the nuclear criticality safety of solid nuclear wastes. It also applies to residual quantities of liquids and/or slurries that are either intimately associated with the solid nuclear waste materials or arise as a result of processing or handling the waste.   ISO 22946 does not apply to bulk or process liquids (including higher concentration process solutions) or irradiated or un-irradiated fuel elements.   NOTE The term fuel element is sometimes applied to fuel assembly, fuel bundle, fuel cluster, fuel rod, fuel plate, etc. All these terms are based on one or more fuel elements. A cylindrical fuel rod (sometimes referred to as a fuel pin) for a light-water reactor is an example of a fuel element.  All stages of the waste life cycle are within the scope of the document. ISO 22946 can...

Nuclear criticality safety. Solid waste excluding irradiated and non-irradiated nuclear fuel

ISO 22946:2020 核临界安全.不包括辐照和非辐照核燃料的固体废物

This document provides specific requirements and guidance on the nuclear criticality safety of waste containing fissile nuclides, generated during normal operations. This document is intended to be used along-side and in addition to ISO 1709. This document applies specifically to the nuclear criticality safety of solid nuclear wastes. It also applies to residual quantities of liquids and/or slurries which are either intimately associated with the solid nuclear waste materials or arise as a result of processing or handling the waste. This document does not apply to bulk or process liquids (including higher concentration process solutions) or irradiated or un-irradiated fuel elements. NOTE The term fuel element is sometimes applied to fuel assembly, fuel bundle, fuel cluster, fuel rod, fuel plate, etc. All these terms are based on one or more fuel elements. A cylindrical fuel rod (sometimes referred to as a fuel pin) for a light-water-reactor is an example of a fuel element. All stages of the waste life cycle are within the scope of the document. This document can also be applied to the transport of solid nuclear waste outside the boundaries of nuclear establishments.

Nuclear criticality safety — Solid waste excluding irradiated and non-irradiated nuclear fuel

ASTM C784-20 核级氧化铝 - 碳化硼复合颗粒标准规范

1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. 1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.3 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets

ASTM C751-20 核级碳化硼粒子标准规范

1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors. 1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard. 1.3 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Nuclear-Grade Boron Carbide Pellets