F46 核材料、核燃料及其分析试验方法 标准查询与下载

GB/T 11848.6-1989 铀矿石浓缩物中氟的测定 离子选择性电极法

本标准规定了铀矿石浓缩物中氟的测定原理、适用范围、使用的试剂和仪器、分析步骤、分析结果的计算和方法的精密度。 本标准适用于铀矿石浓缩物中大于6.0×10％氟的测定。

Determination of fluoride in uranium ore concentrate by ion-selective electrode

GB 11848.4-1989 铀矿石浓缩物中砷的测定二乙基二硫代氨基甲酸盐光度法

Determination of arsenic in uranium ore concentrates diethyldithiocarbamate spectrophotometric method

GB/T 11848.2-1989 铀矿石浓缩物中硝酸不溶铀的测定

本标准规定了铀矿石浓缩物中硝酸不溶铀的测定原理、适用范围、使用的试剂和仪器、分析步骤、分析结果的计算和方法的精密度。 本标准适用于铀矿石浓缩物中含量大于0.01％的硝酸不溶铀的测定。

Determination of nitric acid-insoluble uranium in uranium ore concentrate

GB/T 11848.7-1989 铀矿石浓缩物中卤素的测定 伏尔哈德法

本标准规定了铀矿石浓缩物中除氟外卤素的测定原理、适用范围、使用的试剂和仪器、分析步骤、分析结果的计算及方法的精密度。 本标准适用于铀矿石浓缩物中含量为0.025％～0.8％的卤素（除氟外）总量的测定。

Determination of halidess in uranium ore concentrate--Volhard titration

GB/T 11840-1989 二氧化铀芯块水分含量测定方法

本标准规定了核级二氧化铀芯块水分含量测定方法。 本标准适用于核级二氧化铀芯块水分含量的测定。其他二氧化铀芯块，如含二氧化铀芯块中的水分含量的测定也可参照执行。检测下限为10μg。

Determination of moisture in uranium dioxide pellets

GB/T 11848.11-1989 铀矿石浓缩物中钍的测定 钍试剂光度法

本标准规定了铀矿石浓缩物中钍的测定原理、适用范围、使用的试剂和仪器、分析步骤、分析结果的计算和方法的精密度。 本标准适用于铀矿石浓缩物中钍含量大于0.0025％的钍的测定。

Determination of thorium in uranium ore concentrate by thorin photometric method

GB/T 11839-1989 二氧化铀芯块中硼的测定 姜黄素萃取光度法

本标准规定了二氧化铀芯块中硼的测定原理、操作步骤、结果计算及方法精密度。 本标准适用于二氧化铀芯块中硼的测定，也适用于核纯八氧化三铀中硼的测。取样量为0.500g 测定范围：二氧化铀中硼含量为0.1～1.0μg/g。

Determination of boron in uranium dioxide pellets--The curcumin extraction--Spectrophotometric method

GB/T 11848.8-1989 铀矿石浓缩物中水分的测定 110℃下失重法

本标准规定了铀矿石浓缩物中水分的测定原理、适用范围、使用的试剂和仪器、分析步骤、分析结果的计算和方法的精密度。 本标准适用于铀矿石浓缩物中含量小于2％的水分的测定。

Determination of moisture in uranium ore concentrate--Loss of weight at 110 Centigrade

GB/T 11848.1-1989 铀矿石浓缩物中铀的测定 硫酸亚铁还原-重铬酸钾滴定法

本标准规定了铀矿石浓缩物中铀的测定原理、适用范围、使用试剂和仪器、分析步骤、分析结果的计算和方法的精密度。 本标准适用于铀矿石浓缩物中铀的测定。

Determination of uranium in uranium ore concentrate by ferrous sulfate reduction potassium dichromate titrimatric method

GB/T 10270-1988 六氟化铀中铀的重量法测定

Determination of uranium in uranium hexafluoride by gravimetric method

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

DIN 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(ISO 16793-2018); 英文版本EN ISO 16793-2021

This document describes the ceramographic preparation of uranium dioxide (UO2) sintered pellets for qualitative and quantitative microstructure examinations.These examinations can be carried out before and after thermal or chemical etching.They enable- observations of fissures, i

Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018); English version EN ISO 16793:2021

DIN EN ISO 8299:2021 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, 元素铀和钚的浓度(ISO 8299-2019); 英文版本EN ISO 8299-2021

This document specifies a method for the determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry.The method applies to uranium and plutonium isotope composition and conc

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); English version EN ISO 8299:2021

DIN EN ISO 9463:2021 核能. 核燃料技术. 通过分光光度法测定硝酸溶液中的钚(ISO 9463-2019); 德文版本EN ISO 9463-2021

This document specifies an analytical method by spectrophotometry, for determining the plutonium concentration in nitric acid solutions, with spectrophotometer implemented in hot cell and glove box allowing the analysis of high activity solutions. Commonly, the method is applicab

Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019); English version EN ISO 9463:2021

DIN EN ISO 9161:2021 二氧化铀粉末. 表观密度和振实密度的测定(ISO 9161-2019); 英文版本EN ISO 9161-2021

This document specifies a method of determining the apparent density and tap density of free-flowing uranium dioxide (UO2) powder which will be used for pelleting and sintering of UO2 pellets as a nuclear fuel.This method can be used for different UO2 powder types including grain

Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019); English version EN ISO 9161:2021

ASTM C1907-21 测定氟化物、氯化物或两者的热水解法制备钚材料的标准规程

1.1?This practice provides a procedure for the preparation of samples of plutonium (Pu) materials, using pyrohydrolysis, for subsequent measurement of fluoride, chloride, or both, by ion chromatography (IC) or ion-selective electrode (ISE). 1.2?This practice utilizes a sample s

Standard Practice for Preparation of Plutonium Materials by Pyrohydrolysis for Determination of Fluoride, Chloride, or Both

ASTM C1637-21 钚材料中杂质的标准试验方法. 酸消解法和电感耦合等离子体质谱(ICP-MS)分析

1.1?This test method covers the determination of trace elements in plutonium (Pu) materials such as Pu metal, Pu oxides, and Pu/uranium (U) mixed oxides. The Pu sample is dissolved in acid, and the concentration of the trace impurities are determined by Inductively Coupled Plasm

Standard Test Method for Determination of Impurities in Plutonium Materials—Acid Digestion and Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) Analysis

ASTM C996-20 235U低于5％的浓缩六氟化铀标准规格

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 UF6 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, and DOE O474.1). 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.

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

EJ/T 20150.27-2018 压水堆棒束型燃料组件辐照后检查 第27部分：燃料棒绝对燃耗测量 质谱法

Post-irradiation inspection of fuel assemblies of pressurized water reactor bundle type - Part 27: Mass spectrometry for absolute burnup measurement of fuel rods

EJ/T 20150.30-2018 压水堆棒束型燃料组件辐照后检查 第30部分：燃料包壳管表面沉积物中Fe、Ni、Cr、Mn、Si、Cu元素含量测量 原子发射光谱法

Post-irradiation inspection of PWR rod-bundle fuel assemblies—Part 30: Measurement of Fe, Ni, Cr, Mn, Si, Cu element content in fuel cladding surface deposits by atomic emission spectrometry