F46 核材料、核燃料及其分析试验方法 标准查询与下载

BS ISO 16966:2013 核能. 核燃料技术. 评估核反应堆产生的活性废料放射性的理论活性计算方法

Nuclear energy. Nuclear fuel technology. Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors

BS ISO 8300:2013 核燃料技术. 核级二氧化钚中钚含量的测定. 重量法

Nuclear fuel technology. Determination of plutonium content in plutonium dioxide of nuclear grade quality. Gravimetric method

ISO 8300:2013 核燃料技术.核级二氧化钚中钚含量的测定.重量法

This International Standard specifies a precise and accurate gravimetric method for determining the plutonium content in plutonium dioxide (PuO) of nuclear grade quality, containing a mass fraction of less than 0,65 % of non-volatile impurities. The method is used to cross-check accountancy analyses of plutonium dioxide.

Nuclear fuel technology.Determination of plutonium content in plutonium dioxide of nuclear grade quality.Gravimetric method

ISO 8425:2013 核燃料技术.纯硝酸钚溶液中钚的测定.重量法

This International Standard specifies a precise and accurate gravimetric method for determining the concentration of plutonium in pure plutonium nitrate solutions and reference solutions, containing between 100 g and 300 g of plutonium per litre, in a nitric acid medium.

Nuclear fuel technology.Determination of plutonium in pure plutonium nitrate solutions.Gravimetric method

ISO 21483:2013 未辐照的铀钚混合氧化燃料芯块(U,Pu)O₂中钚在硝酸中溶解度的测定

This International Standard specifies an analytical method for determining the solubility in nitric acid of plutonium in pellets of unirradiated mixed oxide fuel (light-water reactor fuels). The results provide information about the expected dissolution behaviour of irradiated pellets under industrial reprocessing conditions. In this aspect, the specific conditions (e.g. time of the test) may vary depending upon the need to match to a specific reprocessor’s requirements. The test is aimed at determining solubility under equilibrium conditions rather than the kinetics of dissolution and hence allows for a second dissolution period.

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O₂

BS ISO 21483:2013 未辐照的铀钚混合氧化燃料芯块 (U, Pu) O2中的钚在硝酸中溶解度的测定

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O₂

EJ/T 20015-2012 硬岩型铀矿资源/储量估算指南

本标准规定了硬岩型铀矿资源/储量估算原贝止 矿体圈定的原则、 确定指标和参数的方法、 选择估 算方法的耍求，并对工作区仨度累计资源量估算等作了具体规定和耍求。 本标准适月于硬岩型铀矿资源/储堂的估算，并可作为硬岩卿铀矿资源/储量勘查报告评肖的依据。

Hard Rock Uranium Resource/Reserves Estimation Guide

EJ/T 1083-2012 核材料分析化学实验室测量控制大纲

本标准规定了核材料分析化学实验室测量控制大纲的基本要素，包括技术和管理两个方面。 本标准适用于核材料分析化学实验室的测量控制，其它分析实验室的测量控制也可参照使用。

Nuclear Material Analytical Chemistry Laboratory Measurement Control Program

ASTM C1771-13 固相萃取除铀后用电感耦合等离子体质谱法测定水解六氟化铀中硼、硅和锝的标准试验方法

5.1 This method is capable of measuring the concentration of boron, silicon and technetium in UF6. Limits for these contaminants are set in Specifications C787 and C996. 1.1 This test method covers the determination of boron, silicon and technetium in hydrolyzed uranium hexafluoride (UF6) by Inductively Coupled Plasma Mass Spectrometry (ICP-MS) after separation of the uranium by solid phase extraction. 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 and health practices and determine the applicability of regulatory limitations prior to use. Some specific hazards statements are given in Section 7 on Hazards.

Standard Test Method for Determination of Boron, Silicon, and Technetium in Hydrolyzed Uranium Hexafluoride by Inductively Coupled Plasmamdash;Mass Spectrometer After Removal of Uranium by Solid Phase Extraction

ASTM C967-13 铀矿石浓缩物的标准规格

1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass8201;% 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

ASTM C1770-13 二氧化钚松散体密度和叩击松密度测定的标准试验方法

5.1 This test method is intended for determination of bulk loose or tapped density or both for plutonium oxide or similar metallic powders or compounds in the nuclear industry. It is intended for use when the quantity of available material for performing the measurements is limited because of reasons such as nuclear safety or laboratory scale limits on nuclear inventory. 5.2 Values of loose bulk density obtained using this test method should be used with caution since they can vary considerably depending on the initial state of dispersion of the test specimen, height-to-diameter ratio of the specimen in the graduated cylinder, the dryness of the powder, and other factors. 5.3 The data from the tapped bulk density test can be used to estimate the needed volume of small containers holding a fixed mass of powder that has been compacted. 5.4 This test method may be useful for the determination of the Carr Compressibility Index as described in Test Method D6393. 1.1 This test method specifies a method for the determination of loose and tapped bulk density of plutonium oxide powder. 1.2 This test method is applicable when limited quantities of powder are available for performance of the measurements. Alternative test methods, such as Test Methods B527 or D7481, may be used when sufficient quantities are available. 1.3 This test method contains notes that are explanatory and are not part of the mandatory requirements of the method. 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 and health practices and determine the applicability of regulatory limitations prior to use. Some specific hazards statements are given in Section 7 on Hazards.

Standard Test Method for ???Determination of Loose and Tapped Bulk Density of Plutonium Oxide

ASTM C1295-13 六氟化铀裂变产物释放的γ射线能量辐射的标准试验方法

4.1 Specific gamma-ray emitting radionuclides in UF6 are identified and quantified using a high-resolution gamma-ray energy analysis system, which includes a high-resolution germanium detector. This test method shall be used to meet the health and safety specifications of C787, C788, and C996 regarding applicable fission products in reprocessed uranium solutions. This test method may also be used to provide information to parties such as conversion facilities on the level of uranium decay products in such materials. 1.1 This test method covers the measurement of gamma energy emitted from fission and decay products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C787 and C996 and uranyl nitrate specification C788. 1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background. 1.3 The nuclides to be measured are8199;106Ru/ 106Rh,8201;103Ru, 137Cs, 144Ce, 144Pr, 141Ce, 95Zr, 95Nb, and 125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

ASTM C1647-13 铀或钚材料中杂质检定用铀或钚或两者的清除标准实施规程

5.1 This practice can be used to separate uranium or plutonium, or both, prior to the impurity analysis by various techniques. The removal of uranium and plutonium prior to quantification can improve the detection limits by minimizing the signal suppression caused by uranium or plutonium when using ICP techniques. Detection limits of ~1–10 part-per-billion (PPB) may be obtainable by matrix removal. Also, removal of the uranium and plutonium may allow the impurities analysis to be performed on a non-glove box enclosed instrument. 5.2 Other test methods exist to determine impurities in uranium or plutonium. Test Method C1517 is able to determine many impurities in uranium at detection levels of ~1–10 part-per-million (ppm) by DC-Arc Spectrometry. Test Method C1287 is able to determine impurities in uranium at detection levels of ~100 ppb by ICP-MS. Test Method C1432 provides an alternative technique to remove plutonium by ion exchange prior to analysis of the impurities by ICP-AES. 5.3 This practice can be used to demonstrate compliance with nuclear fuel specifications, for example, Specifications C753, C757, C776, C787, C788, and C996. 1.1 This practice covers instructions for using an extraction chromatography column method for the removal of plutonium or uranium, or both, from liquid or digested oxides or metals prior to impurity measurements. Quantification of impurities can be made by techniques such as inductively coupled plasma mass spectrometry (ICP-MS), inductively coupled plasma atomic emission spectrometry (ICP-AES) or atomic absorption spectrometry (AAS.) 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Removal of Uranium or Plutonium, or both, for Impurity Assay in Uranium or Plutonium Materials

ASTM C1637-13 钚金属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

4.1 This test method may be run together with Test Method C1432 to analyze for trace impurities in Pu metal. Using the technique described in this test method and the technique described in Test Method C1432 will provide the analyst with a more thorough verification of the impurity concentrations contained in the Pu metal sample. In addition, Test Method C1432 can be used to determine impurity concentrations for analytes such as Ca, Fe, Na, and Si, which have not been determined using this test method. 4.2 This test method can be used on Pu matrices in nitrate solutions. 4.3 This test method has been validated for use on materials that meet the specifications described in Specification C757 and Test Methods C758 and C759. 4.4 This test method has been validated for all elements listed in Table 1.TABLE 1 Impurity Elements, Mean Percent Recoveries and Percent Relative Standard Deviations Element N Mean R, %8199;8199; RSD, %8199;8199; Lithium 22 93.65 7.26 Beryllium 22 96.46 8.14 Boron

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

ASTM C1636-13 六氟化铀中铀232测定的标准指南

5.1 The method is applicable to the analysis of materials to demonstrate compliance with the specifications set forth in Specifications C787 and C996. Some other specifications may be expressed in terms of mass of 232U per mass of only 238U (see ISO 21847–3:2007). 1.1 This method covers the determination of 232U in uranium hexafluoride by alpha 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 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 C809-13 核纯级氧化铝和氧化铝-碳化硼复合丸状材料化学、质谱和光谱化学分析的标准试验方法

3.1 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specification C785. 3.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. 3.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity content as described in Specification C784. 3.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser. 3.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaser's specifications. 3.2.3 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 aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Boron by Titrimetry and ICP OES 7 to 16 Separation of Boron for Mass Spectrometry 17 to 22 Isotopic Composition by Mass Spectrometry 23 to 26 Separation of Halides by Pyrohydrolysis 27 to 30 Chloride and Fluoride by Ion-Selective Electrode

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and AluminumOxide-Boron Carbide Composite Pellets

ASTM C833-13 烧结(铀钚)二氧化物芯块标准规格

1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 158201;% weight (that is, 0.15 g Pu / g (U+Pu+Am)). 1.2 Pellets produced under this specification are available in four grades. 1.2.1 Grade R???240Pu content of (Pu+Am) (that is, g 240Pu / g (Pu+Am)) is at least 19 %. 1.2.2 Grade F???240Pu content of (Pu+Am) is at least 7 % and less than 19 %. 1.2.3 Grade N1???240Pu content of (Pu+Am) is less than 7 %. 1.2.4 Grade N2???240Pu /239Pu does not exceed 0.10. 1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) 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, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50???Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71???Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173???General Requirements for Shipments and Packaging. 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 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: 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 Specification for Sintered (Uranium-Plutonium) Dioxide Pellets

ASTM C1254-13 用X射线荧光法测定无机酸中铀的标准试验方法

5.1 This test method is applicable to aqueous solutions of uranium containing 0.05 to 20 g uranium per litre of solution presented to the spectrometer. 5.2 Either wavelength-dispersive or energy-dispersive X-ray fluorescence systems may be used provided the software accompanying the system is able to accommodate the use of internal standards. 1.1 This test method covers the steps necessary for the preparation and analysis by X-ray fluorescence (XRF) of mineral acid solutions containing uranium. 1.2 This test method is valid for those solutions containing 0.05 to 20 g uranium/L as presented to the spectrometer. Higher concentrations may be covered by appropriate dilutions. 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 and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 9 and Note 1.

Standard Test Method for Determination of Uranium in Mineral Acids by X-Ray Fluorescence

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

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

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