27.120.30 裂变物质 标准查询与下载

BS ISO 24459:2021 L-吸收边缘光谱法测定核燃料循环样品中的铀含量

Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry

ISO 24459:2021 L-吸收边光谱法测定核燃料循环样品中的铀含量

This document specifies a method for the determination of uranium concentrations in nitric acid or TBP-DILUANT (for example TBP-kerosene) solutions coming from the nuclear fuel cycle. The method is applicable — for process control of solutions, free of suspension, which contain between 10 g/l to 300 g/l uranium, and — for high accuracy purposes (Safeguards) to nitric acid solutions, free of suspension, which contain between 100 g/l and 220 g/l uranium. Having — the content of neptunium and plutonium impurities in the solution less than 1 % of the uranium content. — the content of neutron poisons (gadolinium, erbium) less than 1 % of the uranium content to ensure the absence of significant interferences at the level of required precision, for high accuracy purposes. The method is applicable to solid samples as well, provided that they can be fully dissolved in nitric acid.

Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry

ASTM C1838-16(2021) 1S和2S瓶清洁的标准实施规程

1.1 This practice provides a description of the different ways to clean uranium hexafluoride (UF6) bottles. 1.2 This practice describes two kinds of sample bottles: 1S and 2S bottles. 1.3 Units—The values stated in SI units are to be regarded as the 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 Practice for Cleaning for 1S and 2S Bottles

ASTM C757-16(2021) 轻水反应堆用核级二氧化钚粉末的标准规范

1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium. 1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162 , and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322 . 1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user. 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 Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors

ASTM C1553-21 乏核燃料干燥的标准指南

1.1 This guide discusses three steps in preparing spent nuclear fuel (SNF) for placement in a sealed dry storage system: (1) evaluating the needs for drying the SNF after removal from a water storage pool and prior to placement in dry storage, (2) drying the SNF, and (3) demonstrating that adequate dryness has been achieved. 1.1.1 The scope of SNF includes nuclear fuel of any design (fuel core, clad materials, and geometric configuration) discharged from power reactors and research reactors and its condition as impacted by reactor operation, handling, and water storage. 1.1.2 The guide addresses drying methods and their limitations when applied to the drying of SNF that has been stored in water pools. The guide discusses sources and forms of water that may remain in the SNF, the container, or both after the drying process has been completed. It also discusses the important and potential effects of the drying process and any residual water on fuel integrity and container materials during the dry storage period. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments. 1.1.3 The basic issues in drying are: (1) to determine how dry the SNF must be in order to prevent problems with fuel retrievability, container pressurization, or container corrosion during storage, handling, and transfer, and (2) to demonstrate that adequate dryness has been achieved. Achieving adequate dryness may be straightforward for intact commercial fuel but complex for any SNF where the cladding is breached prior to or during placement and storage at the spent fuel pools. Challenges in achieving adequate dryness may also result from the presence of sludge, CRUD, and any other hydrated compounds. These may be transferred with the SNF to the storage container and may hold water and resist drying. 1.1.4 Units are given in both SI and non-SI units as is industry standard. In some cases, mathematical equivalents are given in parentheses. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 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 Guide for Drying of Spent Nuclear Fuel

ASTM C1233-15(2021) 测定核材料中等效硼含量的标准实施规程

1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum. 1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice. 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 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 Determining Equivalent Boron Contents of Nuclear Materials

ASTM C788-03(2021) 核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 % 235 U intended for subsequent manufacture into either UF6 (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors). 1.2 This specification is intended to provide the nuclear industry with a general standard for 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, Title 10, Part 50 (latest edition). 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals

ASTM C1462-21 浓缩至低于20%²³⁵U的金属铀标准规范

1.1 This specification covers nuclear grade uranium metal that has either 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 235 U mass fraction below 20 % and that is intended for research reactor and generation IV nuclear reactor fuel fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural uranium, reprocessed uranium, or highly enriched uranium. Commercial natural uranium, reprocessed uranium and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium isotope limits for commercial grade enriched uranium metal. 1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used in the production of research reactor and generation IV nuclear reactor fuel. 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 standard does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or any other way of using uranium metal (see, for example, C996 regarding references). 1.4 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. 1.5 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 Specification for Uranium Metal Enriched to Less Than 20 % ²³⁵U

ASTM C1429-21 用双标准多收集器气体质谱仪进行六氟化铀同位素分析的标准试验方法

1.1 This test method covers a quantitative test method applicable to determining the mass percent of uranium isotopes in uranium hexafluoride (UF6) samples. This method as described is for concentrations of 235 U between 0.1 and 10 mass %, and 234 U and 236 U between 0.0001 and 0.1 mass %. 1.2 This test method is for laboratory analysis by a gas mass spectrometer with a multi-collector. 1.3 This standard complements Test Methods C761, the double-standard method for gas mass spectrometers using a single collector, by providing a method for spectrometers using a multi-collector. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, 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 Isotopic Analysis of Uranium Hexafluoride by Double-Standard Multi-Collector Gas Mass Spectrometer

ASTM C753-16a(2021) 核级可烧结二氧化铀粉末标准规范

1.1 This specification covers nuclear-grade, sinterable UO2 powder. It applies to UO2 powder containing uranium (U) of any 235 U concentration in the production of nuclear fuel pellets for use in nuclear reactors. 1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design. 1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. 1.4 This specification refers expressly to UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller. 1.5 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. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder

DIN EN ISO 10276:2021 核能 燃料技术 用于运输放射性物质的包装的耳轴系统（ISO 10276:2019）；德文版 EN ISO 10276:2021

This document covers trunnion systems used for tie-down, tilting and/or lifting of a package of radioactive material during transport operations. Aspects included are the design, manufacture, maintenance, inspection and management system. Regulations which can apply during handli

Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019); German version EN ISO 10276:2021

UNI EN ISO 10276:2021 核能 燃料技术 用于运输放射性物质的包裹的耳轴系统

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

BS EN ISO 10276:2021 核能 燃料技术 用于运输放射性物质的包装件的耳轴系统

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

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

DS/EN ISO 10276:2021 核能“燃料技术”用于运输放射性物质的包装的耳轴系统（ISO 10276:2019）

Nuclear energy – Fuel technology – Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)

NF M60-468*NF EN ISO 10276:2021 核能. 燃料技术. 用于运送放射性材料的包装用耳轴系统

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

EN ISO 10276:2021 核能.燃料技术.运输放射性物质用包装的耳轴系统

Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)

SN EN ISO 10276:2021 核能 燃料技术 用于运输放射性物质的包装的耳轴系统（ISO 10276:2019）

Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)

PN-EN ISO 9463-2021-07 E 核能 核燃料技术 分光光度法测定硝酸溶液中的钚（ISO 9463:2019）

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

PN-EN ISO 9161-2021-07 E 二氧化铀粉末 表观密度和振实密度的测定（ISO 9161:2019）

Uranium dioxide powder -- Determination of apparent density and tap density (ISO 9161:2019)

PN-EN ISO 8299-2021-07 E 核燃料技术 用热电离质谱法测定硝酸溶液中核材料的同位素和元素铀和钚浓度（ISO 8299:2019）

Nuclear fuel technology -- Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019)