F46 核材料、核燃料及其分析试验方法 标准查询与下载

ASTM C1430-07 用大气均衡法测定烧结的二氧化铀和氧化钆-二氧化铀颗粒中铀、氧铀比(O/U)和氧金属比(O/M)的标准试验方法

Uranium dioxide is used as a nuclear-reactor fuel. This test method is designed to determine whether the percent uranium and O/U or O/M content meet Specifications C 776 and C 922.1.1 This test method applies to the determination of uranium, the oxygen to uranium (O/U) ratio in sintered uranium dioxide pellets, and the oxygen to metal (O/M) ratio in sintered gadolinium oxide-uranium dioxide pellets with a Gd2O3 concentration of up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid solution.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. For specific hazards statements, see Section 8.

Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration

ASTM C1672-07 用热电离质谱分光计通过总数蒸发法测定铀或钚同位素组成或浓度的标准试验方法

1.1 This method describes the determination of the isotopic composition and/or the concentration of uranium and plutonium as nitrate solutions by the thermal ionization mass spectrometric (TIMS) total evaporation method. Purified uranium or plutonium nitrate solutions are loaded onto a degassed metal filament and placed in the mass spectrometer. Under computer control, ion currents are generated by heating of the filament(s). The ion beams are continually measured until the sample is exhausted. The measured ion currents are integrated over the course of the run, and normalized to a reference isotope ion current to yield isotopic ratios.1.2 In principle, the total evaporation method should yield isotopic ratios that do not require mass bias correction. In practice, some samples may require this bias correction. When compared to the conventional TIMS method, the total evaporation method is approximately two times faster, improves precision from two to four fold, and utilizes smaller sample sizes.1.3 The total evaporation method may lead to biases in minor isotope ratios due to peak tailing from adjacent major isotopes, depending on sample characteristics. The use of an electron multiplier equipped with an energy filter may eliminate or diminish peak tailing effects. Measurement of instrument abundance sensitivity may be used to ensure that such biases are negligible, or may be used to bias correct minor isotope ratios.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 Uranium or Plutonium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer

ASTM E385-07 使用14兆电子伏特的中子活化和直接计数技术测定氧含量的标准试验方法

The conventional determination of oxygen content in liquid or solid samples is a relatively difficult chemical procedure. It is slow and usually of limited sensitivity. The 14-MeV neutron activation and direct counting technique provides a rapid, highly sensitive, nondestructive procedure for oxygen determination in a wide range of matrices. This test method is independent of the chemical form of the oxygen. This test method can be used for quality and process control in the metals, coal, and petroleum industries, and for research purposes in a broad spectrum of applications.1.1 This test method covers the measurement of oxygen concentration in almost any matrix by using a 14-MeV neutron activation and direct-counting technique. Essentially, the same system may be used to determine oxygen concentrations ranging from over 50 % to about 10 g/g, or less, depending on the sample size and available 14-MeV neutron fluence rates. Note 1 - The range of analysis may be extended by using higher neutron fluence rates, larger samples, and higher counting efficiency detectors.1.2 This test method may be used on either solid or liquid samples, provided that they can be made to conform in size, shape, and macroscopic density during irradiation and counting to a standard sample of known oxygen content. Several variants of this method have been described in the technical literature. A monograph is available which provides a comprehensive description of the principles of activation analysis using a neutron generator (1).1.3 The values stated in either SI or inch-pound units are to be regarded separately as the standard. The values given in parentheses are for information only.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 precautions are given in Section 8.

Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique

ASTM C751-07 核纯级碳化硼丸的标准规范

1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors.1.2 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 Nuclear-Grade Boron Carbide Pellets

ASTM C1430-07(2011)e1 用大气平衡法测定烧结的二氧化铀和氧化钆-二氧化铀颗粒中铀,氧铀比(O/U)和氧金属比(O/M)的标准试验方法

Uranium dioxide is used as a nuclear-reactor fuel. This test method is designed to determine whether the percent uranium and O/U or O/M content meet Specifications C776 and C922.1.1 This test method applies to the determination of uranium, the oxygen to uranium (O/U) ratio in sintered uranium dioxide pellets, and the oxygen to metal (O/M) ratio in sintered gadolinium oxide-uranium dioxide pellets with a Gd2O3 concentration of up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid solution. 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. For specific hazards statements, see Section 8.

Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration

ASTM E265-07e1 用硫-32的放射性测量快速中子流量密度和反应速率的测试方法

Refer to Guides E 720 and E 844 for the selection, irradiation, and quality control of neutron dosimeters. Refer to Practice E 261 for a general discussion of the determination of fast-neutron fluence and fluence rate with threshold detectors. The activation reaction produces 32P, which decays by the emission of a single beta particle in 100 % of the decays, and which emits no gamma rays. The half life of 32P is 14.262 (14) days (1) and the maximum beta energy is 1710 keV(2). Elemental sulfur is readily available in pure form and any trace contaminants present do not produce significant amounts of radioactivity. Natural sulfur, however, is composed of 32S (95.02 % (9)), 34S (4.21 % (8)) (1), and trace amounts of other sulfur isotopes. The presence of these other isotopes leads to several competing reactions that can interfere with the counting of the 1710-keV beta particle. This interference can usually be eliminated by the use of appropriate techniques, as discussed in Section 8.1.1 This test method describes procedures for measuring reaction rates and fast-neutron fluences by the activation reaction 32S(n,p)32P. 1.2 This activation reaction is useful for measuring neutrons with energies above approximately 3 MeV. 1.3 With suitable techniques, fission-neutron fluences from about 5 × 108 to 1016 n/cm2 can be measured. 1.4 Detailed procedures for other fast-neutron detectors are described in Practice E 261. 1.5 This standard does not purport to address all of the safety problems, 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 Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32

NF M60-452:2006 二氧化铀粉末.表观密度和振实密度的测定

Uranium dioxide powder - Determination of apparent density and tap density.

NF M60-457*NF ISO 15647:2006 核能.六氟化铀的同位素分析.双标准气源质谱法

Nuclear energy - Isotopic analysis of uranium hexafluoride - Double-standard gas-source mass spectrometric method.

NF M60-400-2*NF ISO 7097-2:2006 核燃料技术.溶液、六氟化铀和固体中铀的测定.第2部分:铁(II)还原/铈(IV)氧化/滴定法

Nuclear fuel technology - Determination of uranium in solutions, uranium hexafluoride and solids - Part 2 : iron (II) reduction/cerium (IV) oxidation/titrimetric method.

NF M60-400-1*NF ISO 7097-1:2006 核燃料技术.溶液、六氟化铀和固体中铀的测定.第1部分:铁(II)还原/重铬酸钾氧化/滴定法

Nuclear fuel technology - Determination of uranium in solutions, uranium hexafluoride and solids - Part 1 : iron (II) reduction/potassium dichromate oxidation/titrimetric method.

ASTM C776-06 烧结的二氧化铀丸标准规范

1.1 This specification is for finished sintered uranium dioxide pellets. It applies to uranium dioxide pellets containing uranium of any 235U concentration for use in nuclear reactors.1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO 2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO 2 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 or (b) 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 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 71, and Title 49, Part 173.The following precautionary caveat pertains only to the technical requirements portion, Section , 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 or regulatory limitations prior to use.

Standard Specification for Sintered Uranium Dioxide Pellets

ASTM C776-06(2011) 烧结的二氧化铀丸标准规格

1.1 This specification is for finished sintered uranium dioxide pellets. It applies to uranium dioxide pellets containing uranium of any 235U concentration for use in nuclear reactors. 1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for uranium dioxide 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 uranium. 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 or (b) 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 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 71, and Title 49, Part 173. 1.4 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 and health practices and determine the applicability or regulatory limitations prior to use.

Standard Specification for Sintered Uranium Dioxide Pellets

ASTM C889-06 核纯级的氧化钆(Gd2O3)粉末的化学和质谱分析标准试验方法

Gadolinium oxide powder is used, with subsequent processing, in nuclear fuel applications, such as an addition to uranium dioxide. These test methods are designed to determine whether the material meets the requirements described in Specification C 888. 3.1.1 The material is analyzed to determine whether it contains the minimum gadolinium oxide content specified. 3.1.2 The loss on ignition and impurity content are determined to ensure that the weight loss and the maximum concentration limit of specified impurity elements are not exceeded.1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications.1.2 The analytical procedures appear in the following order: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. For specific hazard statements, see Section .1.3 This test method covers the loss-on-ignition of volatile constituents from nuclear-grade gadolinium oxide (Gd2O 3) powder.1.4 The percent gadolinium oxide content of powders, exclusive of volatiles, is determined by calculation after the material has been analyzed to determine the total impurities.

Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd₂O₃) Powder

ASTM C757-06(2011)e1 核纯级可烧结的二氧化钚粉末的规格

1.1 This specification covers nuclear grade plutonium dioxide, sinterable powder obtained by the oxalate precipitation route, calcined above 500°C, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide 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 national and local regulations on processing, shipping, or using source or special nuclear materials. 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-7016 , and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-532 . 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 the 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 Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable

ASTM C1638-06(2013) 铀氧化物中碘-129测定的标准指南

4.1 The determination of 8201;129I is not typically requested in nuclear fuel specifications however it is commonly requested for disposal of the spent fuel, or for disposal of excess uranium from national weapon complexes. This practice can provide results of sufficient quality for waste disposal repositories. 1.1 This method covers the determination of iodine-129 (129I) in uranium oxide by gamma-ray spectrometry. The method could also be applicable to the determination of 8201; 129I in aqueous matrices. 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 and health practices and to determine the applicability of regulatory limitations prior to use.

Standard Guide for the Determination of Iodine-129 In Uranium Oxide

ASTM C1267-06 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

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. 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 C 696) and in the Test Methods for Chemical, Mass Spectrometric, and Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions (Test Methods C 799). 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. The ruggedness of the titration method has been studied for both the volumetric (6) and the weight (7) titration of uranium with dichromate. Committee C26 Safeguards Statement: 4.4.1 The materials (nuclear grade uranium in product, fuel, and scrap) to which this test method applies are subject to nuclear safeguard regulations governing their possession and use. The analytical method in this standard meets U.S. Department of Energy guidelines for acceptability of a measurement method for generation of safeguards accountability measurement data. 4.4.2 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). Details of the titration procedure in the presence of plutonium with appropriate modifications are given in Test Method C 1204.1.2 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.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. For specific safeguard and safety precaution statements, see Section .

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

ASTM C968-06 烧结氧化钆及二氧化铀丸粒的标准试验方法

The test methods in this method are designed to show whether a given material is in accordance with Specification C 922.1.1 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:1.3 The values stated in SI units are to be regarded as the standard.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.1.4 This test method describes the determination of nitrogen in gadolinium oxide-uranium dioxide pellets (Gd2O 3/UO2). With a 2 to 5-g sample, concentrations from 5 to 100 g of nitrogen are determined without interference.1.5 The homogeneity of Gd2O3 in UO2 has been cited in Specification C 922 as an important requirement for this fuel form. The uniform distribution of gadolinia in urania will result in up to three components in the pellet: free Gd 2O3, free UO2, and a Gd2O3-UO 2 solid solution. There are a number of ways for assessing uniformity of which the ceramographic method described here may not be the most definitive. This technique has been used over the gadolinia concentration range from 1 to 10 weight %.

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

ASTM C757-06 核纯级可烧结的二氧化钚粉末的规格

1.1 This specification covers nuclear grade plutonium dioxide, sinterable powder obtained by the oxalate precipitation route, calcined above 500C, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide 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 national and local regulations on processing, shipping, or using source or special nuclear materials. 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-7016, and "Handbook of Nuclear Safety", H. K. Clark, U.S. Atomic Energy Commission Report, DP-532.1.3 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 the standard.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 Nuclear-Grade Plutonium Dioxide Powder, Sinterable

EJ/T 686-2005 反应堆燃料棒²³⁵U富集度检测方法γ射线能谱法

本标准规定了用无源式γ射线能谱法检测反应堆燃料棒U富集度的方法及合格判定。 本标准适用于检测低浓铀燃料棒的U富集度和燃料棒内与标称富集度不相符的燃料芯块。

Measurement method for U enrichment of PWR fuel rod by gamma spectrometry

EJ/T 1184-2005 贫化四氟化铀中微量硅的分光光度法测定

本标准规定了分光光度法测定贫化四氟化铀中微量硅的方法原理、试剂、仪器、分析步骤、结果计算和方法的精密度。 本标准适用于贫化四氟化铀中微量硅的测定，其它丰度的四氟化铀中微量硅的测定可参照使用。 当取祥量为0.25g四氟化铀时，硅的测定范围为：(10～120)μg/g。在测量范围内，40μg磷、3μg耐不干扰硅的测定。

Determination of micro silicon in depleted uranium tetrafluoride by spectrophotometric method