F46 核材料、核燃料及其分析试验方法 标准查询与下载

ASTM C1165-17 用控制电位库仑计法在铂工作电极上测定硫酸中钚的标准试验方法

5.1 This test method is to be used to ascertain whether or not materials meet specifications for plutonium content or plutonium assay, or both. 5.2 A chemical calibration of the coulometer is necessary for accurate results. FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL) 5.3 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications. 1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions. 1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium. 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. Specific precautionary statements are given in Section 9. 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 Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

ASTM C1022-17 浓缩铀矿石的化学分析和原子吸收分析的标准试验方法

4.1 The test methods in this standard are designed to show whether a given material meets the specifications prescribed in Specification C967. 4.2 Because of the variability of matrices of uranium-ore concentrate and the limited availability of suitable reference or calibration materials, the precision and bias of these test methods should be established by each individual laboratory that will use them. The precision and bias statements given for each test method are those reported by various laboratories and can be used as a guideline. 4.3 Instrumental test methods such as X-ray fluorescence and emission spectroscopy can be used for the determination of some impurities where such equipment is available. 1.1 These test methods cover procedures for the chemical and atomic absorption analysis of uranium-ore concentrates to determine compliance with the requirements prescribed in Specification C967. 1.2 The analytical procedures appear in the following order:   Sections Uranium by Ferrous Sulfate Reduction—Potassium Dichromate 8199; Titrimetry 8199;   9 Nitric Acid-Insoluble Uranium  10 to 18 Extractable Organic Material  19 to 26 Determination of Arsenic  27 Carbonate by CO2 Gravimetry  

Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

ASTM C776-17 用于轻水反应堆的烧结二氧化铀芯块的标准规格

1.1 This specification is for finished sintered UO2 pellets. It applies to UO2 pellets containing uranium (U) of any 235U concentration 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 UO2 pellets made from 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 unirradiated 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 (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Government documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 70, Title 10, Part 71, and Title 49, Part 173. 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 precautionary 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, health, and environmental practices and determine the applicability or 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 Sintered Uranium Dioxide Pellets for Light Water Reactors

ASTM C1108-17 用控制电位库仑计法对钚的标准试验方法

5.1 Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment. 5.1.1 This test method determines 5 to 20 mg of plutonium with prior dissolution using Practice C1168. 5.1.2 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. 5.1.3 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). 5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications. 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 6. 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This interna......

Standard Test Method for Plutonium by Controlled-Potential Coulometry

ASTM C1267-17 使用铁II在磷酸中还原后在有钒的情况下滴铬(VI)的铀标准试验方法

5.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, homogeneity of material sampled, sample purity, desired level of reliability, and facility available equipment. 5.2 This uranium assay method is referenced in the Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets (Test Methods C696) and in the Test Methods for Chemical, Mass Spectrometric, and Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions (Test Methods C799). This uranium assay method may also be used for uranium hexafluoride and uranium ore concentrate. This test method determines 20 to 200 mg of uranium; is applicable to product, fuel, and scrap material after the material is dissolved; is tolerant towards most metallic impurity elements usually specified in product and fuel; and uses no special equipment. 5.3 The ruggedness of the titration method has been studied for both the volumetric (6) and the weight (7) titration of uranium with dichromate. 5.4 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications. 5.4.1 When used in conjunction with the appropriate certified reference materials (SRM6 or CRM), this procedure can demonstrate traceability to the national measurement base. However, use of the test method does not automatically guarantee regulatory acceptance of the resulting safeguards measurements. It remains the sole responsibility of the user of this test method to assure that its application to safeguards has the approval of the proper regulatory authorities. 1.1 This test method, commonly referred to as the Modified Davies and Gray technique, covers the titration of uranium in product, fuel, and scrap materials after the material is dissolved. The test method is versatile and has been ruggedness tested. With appropriate sample preparation, this test method can give precise and unbiased uranium assays over a wide variety of material types (1, 2).2 Details of the titration procedure in the presence of plutonium with appropriate modifications are given in Test Method C1204. 1.2 Uranium levels titrated are usually 20 to 50 mg, but up to 200 mg uranium can be titrated using the reagent volumes stated in this test method. 1.3 The values stated ......

Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium

EJ/T 20140-2016 核级二氧化钚粉末中241Am的测定 γ能谱法

Determination of 241Am in Nuclear Grade Plutonium Dioxide Powder by Gamma Spectroscopy

EJ/T 20142-2016 核级二氧化钚粉末中碳的测定 高频燃烧红外吸收法

Determination of Carbon in Nuclear Grade Plutonium Dioxide Powder High Frequency Combustion Infrared Absorption Method

EJ/T 20146-2016 烧结钴芯块中氢的测定 惰气熔融热导法

Determination of Hydrogen in Sintered Cobalt Pellets - Inert Gas Fusion Thermal Conductivity Method

EJ/T 20147-2016 钴粉及烧结钴芯块中镁等13种杂质元素的测定 ICP-AES法

Determination of 13 impurity elements such as magnesium in cobalt powder and sintered cobalt pellets by ICP-AES method

EJ/T 20148-2016 钴粉及烧结钴芯块中氧氮的测定

Determination of Oxygen and Nitrogen in Cobalt Powder and Sintered Cobalt Pellets

EJ/T 20141-2016 核级二氧化钚粉末中微量铀的测定 激光荧光法

Determination of Trace Uranium in Nuclear Grade Plutonium Dioxide Powder by Laser Fluorescence Method

ISO 22765:2016 核燃料技术. (U,Pu)O2烧结芯块. 微观结构检验的陶瓷相准备指南

Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination

ISO 12183:2016 核燃料技术.钚的控制电势库仑法分析

Nuclear fuel technology - Controlled-potential coulometric assay of plutonium

DIN EN ISO 15366-1:2016 核燃料技术.采用溶剂萃取色谱法对同位素和同位素稀释分析用的硝酸溶液进行铀和钚的化学分离和纯化.第1部分:微克范围内含钚的样品和毫克范围内含铀的样品(ISO 15366-1-2014).德文版本EN ISO 15366-1-2016

Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range

DIN EN ISO 15646:2016 UO2, (U,Gd)O2和(U,Pu)O2颗粒的再烧结试验(ISO 15646-2014).德文版本EN ISO 15646-2016

Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets (ISO 15646:2014); German version EN ISO 15646:2016

DIN EN ISO 15366-2:2016 核燃料技术.采用溶剂萃取色谱法对同位素和同位素稀释分析用的硝酸溶液进行铀和钚的化学分离和纯化.第2部分:纳克及以下范围内含钚和铀的样品(ISO 15366-2-2014).德文版本EN ISO 15366-2-2016

Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nan

EJ/T 20128-2016 铀燃料元件制造厂安全要求

本标准规定了铀燃料元件制造厂选址、设计、建造、调试、运行和退役全寿期内的安全要求。 本标准适用于操作、加工和贮存U富集度不大于6%低富集度铀（来源于天然铀、浓缩铀或后处理铀）的铀燃料元件制造厂。完整的燃料组件（例如压水堆、沸水堆和重水堆用燃料组件）在被运输到核电厂之前贮存于燃料制造厂中，这样的贮存设施也被认为是铀燃料元件制造厂的一部分。 本标准限于铀燃料元件制造厂的安全，不涉及制造出的燃料组件可能对将使用此燃料组件的反应堆的影响。

Safety requirements of uranium fuel fabrication facilities

ASTM C1458-16 采用量热法对钚, 氚和241Am进行无损测量的标准试验方法

5.1 This test method is considered to be the most accurate NDA technique for the assay of many physical forms of Pu. Isotopic measurements by gamma-ray spectroscopy or destructive analysis techniques are part of this test method when it is applied to the assay of Pu. 5.1.1 Calorimetry has been applied to a wide variety of Pu-bearing solids including metals, alloys, oxides, fluorides, mixed Pu-U oxides, mixed oxide fuel pins, waste, and scrap, for example, ash, ash heels, salts, crucibles, and graphite scarfings) (2, 3). This test method has been routinely used at U.S. and European facilities for Pu process measurements and nuclear material accountability since the mid 1960’s (2-9). 5.1.2 Pu-bearing materials have been measured in calorimeter containers ranging in size from about 0.025 m to about 0.63 m in diameter and from about 0.076 m to about 1.38 m in height. 5.1.3 Gamma-ray spectroscopy typically is used to determine the Pu isotopic composition and8201;241Am to Pu ratio (see Test Method C1030). However, isotopic information from mass spectrometry and alpha counting measurements may be used instead (see Test Method C697). 5.2 This test method is considered to be the most accurate NDA method for the measurement of tritium. For many physical forms of tritium compounds calorimetry is currently the only practical measurement technique available. 5.3 Physical standards representative of the materials being assayed are not required for the test method. 5.3.1 This test method is largely independent of the elemental distribution of the nuclear materials in the matrix. 5.3.2 The accuracy of the method can be degraded for materials with inhomogeneous isotopic composition. 5.4 The thermal power measurement is traceable to national measurement systems through electrical standards used to directly calibrate the calorimeters or to calibrate secondary8201;238Pu heat standards. 5.5 Heat-flow calorimetry has been used to prepare secondary standards for neutron and gamma-ray assay systems (7-12).

Standard Test Method for Nondestructive Assay of Plutonium, Tritium and&x2009;²⁴¹Am by Calorimetric Assay

ASTM C1502-16 测定二氧化铀和氧化钆中氯和氟总含量的标准试验方法

5.1 The method is designed to show whether or not the tested materials meet the specifications as given in either Specification C753, C776, C888 or C922. 1.1 This test method covers the determination of chlorine and fluorine in nuclear-grade uranium dioxide (UO2) powder and pellets, nuclear grade gadolinium oxide (Gd2O3 ) powder and gadolinium oxide-uranium oxide (Gd2O3-UO2) powder and pellets. 1.2 With a 2 gram UO2 sample size the detection limit of the method is 4 µg/g for chlorine and 2 µg/g for fluorine. The maximum concentration determined with a 2 gram sample is 500 µg/g for both chlorine and fluorine. The sample size used in this test method can vary from 1 to 10 grams resulting in a corresponding change in the detection limits and range. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide

ASTM C708-16 核级氧化铍粉末的标准规格

1.1 This specification defines the physical and chemical requirements of nuclear-grade beryllium oxide (BeO) powder to be used in fabricating nuclear components. 1.2 This specification does not include requirements for health and safety (1-5).2 It recognizes the material as a Class B poison and suggests that producers and users become thoroughly familiar with and comply to applicable federal, state, and local regulations and handling guidelines (1). 1.3 Special tests and procedures are given in Annex A1 and Annex A2. 1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

Standard Specification for Nuclear-Grade Beryllium Oxide Powder