F46 核材料、核燃料及其分析试验方法 标准查询与下载

KS A ISO 9891:2012 二氧化铀粉末和烧结芯块中碳含量的测定.高频感应炉燃烧.滴定法/库仑法/红外吸收法

이 표준은 이산화우라늄 분말과 소결체 내 탄소함량을 결정하기 위해 시험 시료를 유도로 안에

Determination of carbon content in uranium dioxide powder and sintered pellets－High-frequency induction furnace combustion－Titrimetric/coulometric/infrared absorption methods

KS A ISO 9279:2012 二氧化铀芯块.密度和总孔隙率的测定.汞置换法

이 표준은 UO2 소결체의 밀도와 총 공극률 결정을 위한 방법에 관하여 기술하고 있다. 이

Uranium dioxide pellets－Determination of density and total porosity－Mercury displacement method

KS A ISO 9278:2012 核能.丸状二氧化铀.开口孔隙率和封闭孔隙率密度以及体积分率的测定

이 표준은 UO2 소결체의 겉보기 밀도와 개/폐 공극률 양을 결정하기 위한 두 가지 방법에

Nuclear energy-Uranium dioxide pellets-Determination of density and volume fraction of open and closed porosity

KS A ISO 18213-2:2012 核燃料技术.核材料衡算用容器校准和体积测定.第2部分:容器校准数据的标准化

이 표준은 측정 과정에서 발생하는 주위 조건으로 인한 변화의 영향을 최소화하기 위하여 고정

Nuclear fuel technology-Tank calibration and volume determination for nuclear materials accountancy-Part 2:Data standardization for tank calibration

KS A ISO 18213-1:2012 核燃料技术.核材料衡算用容器校准和体积测定.第1部分:程序综述

이 표준은 액체 함량 결정을 위하여 압력 측정 시스템이 장착된 핵공정 탱크의 교정 및 부피

Nuclear fuel technology－Tank calibration and volume determination for nuclear materials accountancy－Part 1：Procedural overview

KS A ISO 9892:2012 铀金属、二氧铀粉末和芯块以及硝酸铀酰溶液.氟含量的测定.氟离子选择电极法

1.1 이 표준은 금속 우라늄, 이산화우라늄 분말과 소결체 및 질산우라닐 용액 내 불소함량

Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions－Determination of fluorine content－Fluoride ion selective electrode method

KS A ISO 7476:2012 核燃料技术.核级硝酸铀酰溶液中铀的测定.重量法

이 표준은 1 kg당 100 g 이상의 우라늄을 포함한 핵등급 질산우라닐의 질량비를 결정하

Nuclear fuel technology－Determination of uranium in uranyl nitrate solutions of nuclear grade quality－Gravimetric method

KS A ISO 9889:2012 二氧化铀粉末和烧结芯块中碳含量的测定.电阻炉燃烧.滴定法/库仑法/红外线吸收分析法

이 표준은 이산화우라늄 분말과 소결체 내 탄소함량을 결정하기 위한 적정법/전기량법/적외선

Determination of carbon content in uranium dioxide powder and sintered pellets－Resistance furnace combustion－Titrimetric/coulometric/infrared absorbtion method

ISO 16424:2012 核能.钆混合燃料中Gd分布均匀性评估和利用铀和钆元素测定钆燃料芯块中Gd2O3含量.

This International Standard is applicable to the evaluation of the homogeneity of Gd distribution within gadolinium fuel blends, and the determination of the Gd2O3 content in sintered fuel pellets of Gd2O3+UO2 from 1 % to 10 %, by measurements of gadolinium (Gd) and uranium (U) elements using ICP-AES. After performing measurements of Gd and U elements using ICP-AES, if statistical methodology is additionally applied, homogeneity of Gd distribution within a Gd fuel pellet lot can also be evaluated. However, this International Standard covers the statistical methodology only on a limited basis. NOTE 1 using an inductively coupled plasma source (ICP-AES). The methodology of ISO 16796 is different from the one of this International Standard. NOTE 2 In this International Standard, gadolinium fuel blend represents a mixture of uranium dioxide (UO2) powder and gadolinium oxide (Gd2O3) powder. The physically blended and homogenized powder may additionally contain in it rather large quantities of uranium oxide (U3O8) powder particles and/or the M3O8 powder particles obtained by oxidation of Gd pellets. In this International Standard, the symbol “M” in the chemical formula “M3O8” and in the terminology “O/M ratio” represents metallic elements U and Gd.

Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd₂O₃ content in gadolinium fuel pellets by measurements of uranium and gadolinium elements

NB/T 25009-2012 压水堆核电厂能量统计规程

本标准规定了核电厂能量统计的内容、方法和要求。本标准适用于压水堆核电厂的能量统计工作,其他堆型核电厂的能量统计工作可参照本标准执行。

Energy statistics procedure in pressurized water nuclear power plants

ASTM C799-12 核纯级硝酸铀酰溶液的化学,质谱,光谱化学,核(放射性)及放射化学分析标准试验方法

Uranyl nitrate solution is used as a feed material for conversion to the hexafluoride as well as for direct conversion to the oxide. In order to be suitable for this purpose, the material must meet certain criteria for uranium content, isotopic composition, acidity, radioactivity, and impurity content. These methods are designed to show whether a given material meets the specifications for these items described in Specification C788. An assay is performed to determine whether the material has the specified uranium content. Determination of the isotopic content of the uranium is made to establish whether the effective fissile content is in accordance with the purchaser’s specifications. Acidity, organic content, and alpha, beta, and gamma activity are measured to establish that they do not exceed their maximum limits. Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. Impurity concentrations are also required for calculation of the equivalent boron content (EBC), and the total equivalent boron content (TEBC).1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium28 Determination of Chromium29 Determination of Molybdenum30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry43 Determination of Chloride and Bromide44 Determination of Sulfur by X-Ray Fluorescence45 Sulfate Sulfur by (Photometric) Turbidimetry46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method62-69 Carbon by Persulfate Oxidation-Acid Titrimetry70 Conversion to U3O871-74 Boron by Emission Spectrography75-81 Impurity Elements by Spark Source Mass Spectrography

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

ANSI N14.1-2012 六氟化铀.运输包装

Uranium Hexafluoride - Packagings for Transport

ASTM C968-12 分析烧结氧化钆及二氧化铀丸粒标准试验方法

The test methods in this method are designed to show whether a given material is in accordance with Specification C922.1.1 These test methods cover procedures for the analysis of sintered gadolinium oxide-uranium dioxide pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Section Carbon (Total) by Direct CombustionThermal Conductivity Method C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Gadolinia Content by Energy-Dispersive X-Ray Spectrometry C1456 Test Method for Determination of Uranium or Gadolinium, or Both, in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray Fluorescence (XRF) Hydrogen by Inert Gas Fusion C1457 Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction Isotopic Uranium Composition by Multiple-Filament Surface-Ionization Mass Spectrometric Method C1413 Test Method for Isotopic Analysis of Hydrolysed Uranium Hexafluoride And Uranyl Nitrate Solutions By Thermal Ionization Mass Spectrometry C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis Nitrogen by DistillationNessler Reagent (Photometric) Method6 to 16 Oxygen-to-Metal Ratio of Sintered Gadolinium Oxide-Uranium Dioxide Pellets C1430 Test Method for Determination of Uranium, Oxygen to Uranium, and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration Spectrochemical Determination of Trace Impurity Elements

Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

ASTM C791-12 核纯级碳化硼的化学、质谱和光谱化学分析的标准试验方法

Boron carbide is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet certain criteria for assay, isotopic composition, and impurity content. These methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C750 and C751. An assay is performed to determine whether the material has the specified boron content. Determination of the isotopic content of the boron is made to establish whether the content is in compliance with the purchaser’s specifications. Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Total Carbon by Combustion in an Inductive Furnace and Infrared Measurement 7-16 Total Boron by Titrimetry and ICP OES17-27 Isotopic Composition by Mass Spectrometry28-32 Pyrohydrolysis33-40 Chloride by Constant-Current Coulometry41-49 Chloride and Fluoride by Ion-Selective Electrode50-58 Water by Constant-Voltage Coulometry and Weight Loss on Drying59-62 Metallic Impurities63 and 64 Soluble Boron by Titrimetry and ICP OES65-79 Free Carbon by a Coulometric Method80-89

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Boron Carbide

ASTM C1625-12 用热电离质谱法测定铀和钚浓度和其同位素丰度的标准试验方法

Uranium and plutonium oxides can be used as a nuclear-reactor fuel in the form of pellets. In order to be suitable for use as a nuclear fuel the starting material must meet certain specifications, such as found in Specifications C757, C833, C753, C776, C1008, or as specified by the purchaser. The uranium and/or plutonium concentration and isotopic abundances are measured by mass spectrometry following this test method. The separated heavy element fractions placed on mass spectrometric filaments must be very pure. The quantity required depends upon the sensitivity of the instrument detection system. If an electron multiplier detector is to be used, only a few nanograms are required. If a Faraday cup is used, a few micrograms are needed. Chemical purity of the sample becomes more important as the sample size decreases, because ion emission of the sample is suppressed by impurities.1.1 This test method covers the determination of the concentration and isotopic composition of uranium and plutonium in solutions. The purified uranium or plutonium from samples ranging from nuclear materials to environmental or bioassay matrices is loaded onto a mass spectrometric filament. The isotopic ratio is determined by thermal ionization mass spectrometry, the concentration is determined by isotope dilution. 1.2 The values stated in SI units are to be regarded as the standard. Values in parentheses are for information only. 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 safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry

ASTM C1108-12 控制电势库仑法测定钚的标准试验方法

Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment. This test method determines 5 to 20 mg of plutonium with prior dissolution using Practice C1168. This test method calculates plutonium concentration in solutions or mass fraction in solids using an electrical calibration based upon Ohm’s Law and the Faraday Constant. Chemical standards are used for quality control. When prior chemical separation of plutonium is necessary to remove interferences, the quality control standards should be included with each chemical separation batch (9). Committee C-26 Safeguards Statement : The materials (plutonium metal, plutonium oxide or mixed oxide [(U, Pu) O2] powders and pellets) to which this test method applies are subject to nuclear safeguards regulations governing their possession and use. Materials for use by the commercial nuclear community must also meet compositional specifications. The analytical method in this test method both meets U. S. Department of Energy guidelines for acceptability of a measurement method for generation of safeguards accountability measurement data and also provides data that may be used to demonstrate specification compliance in buyer-seller interactions.1.1 This test method describes the determination of dissolved plutonium from unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 M HNO3, 1 M HClO4, 1 M HCl, 5 M HCl, and 0.5 M H2SO4. Limitations on the use of selected supporting electrolytes are discussed in Section 5. Optimum quantities of plutonium for this procedure are 5 to 20 mg. 1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials. 1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 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 Test Method for Plutonium by Controlled-Potential Coulometry

ASTM C967-12 铀矿石浓缩物的标准规格

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 the standard. The values given in parentheses are for information only.

Standard Specification for Uranium Ore Concentrate

DB34/T 1563.1-2011 ITER馈线系统(FEEDER)故障模式及影响分析(FMEA)指南 第1部分:术语和基本要求

本部分适用于产品在论证、方案、工程研制与定型、生产和使用等寿命周期各阶段开展的FMEA工作。

Guide to failure mode and effects analysis of ITER Feeder system Part 1: terms and basic requirements

DB34/T 1563.1.1-2011 ITER馈线系统（FEEDER）故障模式及影响分析（FMEA）指南 第1部分：术语和基本要求

DB34/T 1563的本部分规定了国际热核聚变实验堆（ITER）馈线系统(FEEDER)故障模式及影响分析(FMEA)的术语和定义、基本要求。 本部分适用于产品在论证、方案、工程研制与定型、生产和使用等寿命周期各阶段开展的FMEA工作。

ITER Feeder System (FEEDER) Failure Mode and Effects Analysis (FMEA) Guidelines Part 1: Terminology and Basic Requirements

DB34/T 1563.2.2-2011 ITER馈线系统（FEEDER）故障模式及影响分析（FMEA）指南 第2部分：功能及硬件

DB34/T 1563 的本部分规定了国际热核聚变实验堆（ITER）馈线系统(FEEDER) 故障模式及影响分析(FMEA)的内容和方法，FEEDER功能及硬件FMEA的方法。 本部分适用于ITER馈线系统(FEEDER) 功能及硬件的故障模式及影响分析(FMEA)。

ITER Feeder System (FEEDER) Failure Mode and Effects Analysis (FMEA) Guide Part 2: Function and Hardware