F46 核材料、核燃料及其分析试验方法 标准查询与下载

ASTM C759-10 核纯级硝酸钚溶液的化学、质谱和光谱化学分析的标准试验方法

These test methods are designed to show whether a given material meets the purchaser's specifications. An assay is performed to determine whether the material has the specified plutonium content. Determination of the isotopic content of the plutonium in the plutonium-nitrate solution is made to establish whether the effective fissile content is in compliance with the purchaser's specifications. Impurity content is determined by a variety of methods to ensure that the maximum concentration limit of specified impurities is not exceeded. Determination of impurities is also required for calculation of the equivalent boron content (EBC).1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order:

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

ASTM C1718-10 使用层析成象γ扫描法对放射性物质进行无损分析的标准试验方法

The TGS provides a nondestructive means of mapping the attenuation characteristics and the distribution of the radionuclide content of items on a voxel by voxel basis. Typically in a TGS analysis a vertical layer (or segment) of an item will be divided into a number of voxels. By comparison, a segmented gamma scanner (SGS) can determine matrix attenuation and radionuclide concentrations only on a segment by segment basis. It has been successfully used to quantify 238Pu, 239Pu, and 235U. SNM loadings from 0.5 g to 200 g of 239Pu (5, 6), from 1 g to 25 g of 235U (7), and from 0.1 to 1 g of 238Pu have been successfully measured. The TGS technique has also been applied to assaying radioactive waste generated by nuclear power plants (NPP). Radioactive waste from NPP is dominated by activation products (for example, 54Mn, 58Co, 60Co, 110mAg) and fission products (for example, 137Cs, 134Cs). The radionuclide activities measured in NPP waste is in the range from 3.7E+04 Bq to 1.0E+07 Bq. Some results of TGS application to non-SNM radionuclides can be found in the literature (8). The TGS technique is well suited for assaying items that have heterogeneous matrices and that contain a non-uniform radionuclide distribution. Since the analysis results are obtained on a voxel by voxel basis, the TGS technique can in many situations yield more accurate results when compared to other gamma ray techniques such as SGS. In determining the radionuclide distribution inside an item, the TGS analysis explicitly takes into account the cross talk between various vertical layers of the item. The TGS analysis technique uses a material basis set method that does not require the user to select a mass attenuation curve apriori, provided the transmission source has at least 2 gamma lines that span the energy range of interest. A commercially available TGS system consists of building blocks that can easily be configured to operate the system in the SGS mode or in a far-field geometry. The TGS provides 3-dimensional maps of gamma ray attenuation and radionuclide concentration within an item that can be used as a diagnostic tool. Item preparation is limited to avoiding large quantities of heavily attenuating materials (such as lead shielding) in order to allow sufficient transmission through the container and the matrix.1.1 This test method describes the nondestructive assay (NDA) of gamma ray emitting radionuclides inside containers using tomographic gamma scanning (TGS). High resolution gamma ray spectroscopy is used to detect and quantify the radionuclides of interest. The attenuation of an external gamma ray transmission source is used to correct the measurement of the emission gamma rays from radionuclides to arrive at a quantitative determination of the radionuclides present in the item. 1.2 The TGS technique covered by the test method may be used to assay scrap or waste material in cans or drums in the 1 to 500 litre volume range. Other items may be assayed as well. 1.3 The test method will cover two implementations of the TGS procedure: (1) Isotope Specific Calibration that uses standards of known radionuclide masses (or activities) to determine system response in a mass (or activity) versus corrected count rate calibration, that applies to only those specific radionuclides for which it is calibrated, and (2) Response Curve Calibration that uses gamma ray standards to determine system response as a function of gamma ray energy and thereby establishes calibration for all gamma emitting radionuclides of interest. 1.4 This test method will also include a technique to extend th......

Standard Test Method for Nondestructive Assay of Radioactive Material by Tomographic Gamma Scanning

ASTM C1287-10 感应耦合等离子体质谱法测定核级铀化合物中杂质的标准试验方法

1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as 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. WarningThe ICP-MS is a source of intense ultra-violet radiation from the radio frequency induced plasma. Protection from radio frequency radiation and UV radiation is provided by the instrument under normal operation.

Standard Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry

ASTM C697-10 核工业级二氧化钚粉末和颗粒的化学、质谱和光谱化学分析的标准试验方法

Plutonium dioxide is used in mixtures with uranium dioxide as a nuclear-reactor fuel. In order to be suitable for this purpose, the material must meet certain criteria for plutonium content, isotopic composition, and 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 C757. An assay is performed to determine whether the material has the minimum plutonium content specified on a dry weight basis. Determination of the isotopic content of the plutonium in the plutonium dioxide powder is made to establish whether the effective fissile 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. Determination of impurities is also required for calculation of the equivalent boron content (EBC).1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade plutonium dioxide powders and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order:

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets

ASTM C698-10 核纯级混合氧化物((U、Pu))O_{2化学、质谱和光谱化学分析用标准试验方法}

Mixed oxide, a mixture of uranium and plutonium oxides, is used as a nuclear-reactor fuel in the form of pellets. The plutonium content may be up to 10 weight %, and the diluent uranium may be of any 235U enrichment. In order to be suitable for use as a nuclear fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specification C833. The material is assayed for uranium and plutonium to determine whether the plutonium content is as specified by the purchaser, and whether the material contains the minimum combined uranium and plutonium contents specified on a dry weight basis. Determination of the isotopic content of the plutonium and uranium in the mixed oxide is made to establish whether the effective fissile 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. Determination of impurities is also required for calculation of the equivalent boron content (EBC).1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade mixed oxides, (U, Pu)O2, powders and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order:

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O₂)

KS A ISO 9161:2009 二氧化铀粉末.表观密度和堆积密度的测定

이 표준은 핵연료로 사용하기 위해 이산화우라늄(UO2) 소결체를 만들고 소결하는 데 사용되

Uranium dioxide powder-Determination of apparent density and tap density

NF M60-406:2009 核能.核燃料技术.分光光度法测定硝酸溶液中钚元素的含量

Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry.

ISO 9463:2009 核能.核燃料技术.分光光度法测定硝酸溶液中的钚

Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry

ISO 13465:2009 核能.核燃料技术.用分光光度测定法测定硝酸溶液中的镎

Nuclear energy - Nuclear fuel technology - Determination of neptunium in nitric acid solutions by spectrophotometry

NF M60-466:2009 核燃料技术.MOX球粒中的O/M比值的测定.重量法

Nuclear fuel technology - Determination of the O/M ratio in MOX pellets - Gravimetric method.

NF M60-458*NF ISO 9278:2009 核能.二氧化铀芯块.开孔和闭孔密度及容积率的测定

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

ASTM C1517-09 用直流电弧发射光谱分析法测定铀金属或化合物中金属杂质的标准试验方法

This test method is applicable to uranium metal, uranium oxides and compounds soluble in nitric or sulfuric acid, and uranium solutions which can be converted to uranium oxide (U3O8) in a muffle furnace. It may be used to determine the impurities in uranium compounds as listed in Specifications C 753, C 776, C 788, and C 967.1.1 This test method describes the steps necessary for the preparation and determination of impurity metals in uranium metal and uranium compounds by DC arc emission spectroscopy. 1.2 The method is valid for those materials that can be dissolved in acid and/or converted to an oxide in a muffle furnace (see Practice C 1347). 1.3 This method uses the carrier distillation technique to selectively carry the impurities into the arc, leaving the uranium oxide in the electrode. If it is necessary to determine the carrier metal(usually a silver or strontium, or gallium compound) as an impurity, another technique must be chosen for that element. 1.4 Units8212;The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only. 1.5 This standard may involve hazardous materials, operations and equipment. 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 Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy

ASTM C750-09 核纯级碳化硼粉末的标准规范

1.1 This specification defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. Because each application has a different need for impurity and boron requirements, three different chemical compositions of powder are specified. In using this specification, it is necessary to dictate which type of powder is intended to be used. In general, the intended applications for the various powder types are as follows: 1.1.1 Type 18212;For use as particulate material in nuclear reactor core applications. 1.1.2 Type 28212;Powder that will be further processed into a fabricated shape for use in a nuclear reactor core or used in non-core applications when the powder directly or indirectly may cause adverse effects on structural components, such as halide stress corrosion of stainless steel. 1.1.3 Type 38212;Powder that will be used for non-core applications or special in-core applications. 1.2 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 Boron Carbide Powder

ASTM C1066-09 核纯级氧化锆的标准规范

1.1 This specification applies to pellets of stabilized zirconium oxide used 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 Zirconium Oxide Pellets

ASTM C1458-09e1 用量热分析进行钚、氚和241Am无损试验的标准试验方法

This test method is 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 the test method when it is applied to the assay of Pu. 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 for the last 40 years (2-9). Pu-bearing materials have been measured in calorimeter containers ranging in size from about 0.025 m to about 0.60 m in diameter and from about 0.076 m to about 0.9 m in height. Gamma-ray spectroscopy typically is used to determine the Pu-relative isotopic composition and 241Am to Pu ratio (see Test Method C 1030). Isotopic information from mass spectrometry and alpha counting measurements may be used (see Test Method C 697). This test method is the most accurate NDA method for the measurement of tritium. For many physical forms of tritium compounds calorimetry is the only practical measurement technique available. Physical standards representative of the materials being assayed are not required for the test method. This test method is largely independent of the elemental distribution of the nuclear materials in the matrix. The accuracy of the method can be degraded for materials with inhomogeneous isotopic composition. The thermal power measurement is traceable to national measurement systems through electrical standards used to directly calibrate the calorimeters or to calibrate secondary 238Pu heat standards. Heat-flow calorimetry has been used to prepare secondary standards for neutron and gamma-ray assay systems (7-12). Calorimetry measurement times are typically longer than other NDA techniques. Four parameters of the item and the item packaging affect measurement time. These four parameters are density, mass, thermal conductivity, and change in temperature. The measurement well of passive calorimeters will also affect measurement time because it too will need to come to the new equilibrium temperature. Calorimeters operated in servo mode maintain a constant measurement well temperature and have no effect on measurement time. Calorimeter measurement times range from 20 minutes (13) for smaller, temperature-conditioned, containers up to 24 h for larger containers and items with long thermal-time constants. Measurement times may be reduced by using equilibrium prediction techniques, by temperature preconditioning of the item to be measured, or operating the calorimeter using the servo-control technique.1.1 This test method describes the nondestructive assay (NDA) of plutonium, tritium, and 241Am using heat flow calorimetry. For plutonium the typical range of applicability corresponds to ~1 g to ~2000 g quantities while for tritium the typical range extends from ~0.001 g to~ 10 g. This test method can be applied to materials in a wide range of container sizes up to 50 L. It has been used routinely to assay items whose thermal power ranges from 0.001 W to 135 W. 1.2 This test method requires knowledge of the relative abundances of the plutonium isotopes and the 241Am/Pu mass ratio to determine the total plutonium mass. 1.3 This test method provides a direct measure of tritium content. 1.4 This test method provides a measure of 241Am either as a single isotope or mixed with plutonium. 1.......

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

ASTM C1076-09 核纯级氧化铪颗粒的标准规范

1.1 This specification applies to pellets of stabilized cubic hafnium oxide used 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 Hafnium Oxide Pellets

ASTM E263-09 用铁的放射性测量快中子反应速率的标准试验方法

DESIG: E 263 09 ^TITLE: Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron ^SIGNUSE: Refer to Guide E 844 for guidance on 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 rate with threshold detectors. Pure iron in the form of foil or wire is readily available and easily handled. Fig. 1 shows a plot of cross section as a function of neutron energy for the fast-neutron reaction 54Fe(n,p)54Mn (1). This figure is for illustrative purposes only to indicate the range of response of the 54Fe(n,p)54Mn reaction. Refer to Guide E 1018 for descriptions of recommended tabulated dosimetry cross sections. 54Mn has a half-life of 312.13 days (3) (2) and emits a gamma ray with an energy of 834.845 keV (5). (2) Interfering activities generated by neutron activation arising from thermal or fast neutron interactions are 2.57878 (46)-h 56Mn, 44.95-d (8) 59Fe, and 5.2710-y (8) 60Co (2,3). (Consult Ref (2) for more precise values currently accepted for the half-lives.) Interference from 56Mn can be eliminated by waiting 48 h before counting. Although chemical separation of 54Mn from the irradiated iron is the most effective method for eliminating 59Fe and 60Co, direct counting of iron for 54Mn is possible using high-resolution detector systems or unfolding or stripping techniques, especially if the dosimeter was covered with cadmium or boron during irradiation. Altering the isotopic composition of the iron dosimeter is another useful technique for eliminating interference from extraneous activities when direct sample counting is to be employed. The vapor pressures of manganese and iron are such that manganese diffusion losses from iron can become significant at temperatures above about 700°C. Therefore, precautions must be taken to avoid the diffusion loss of 54Mn from iron dosimeters at high temperature. Encapsulating the iron dosimeter in quartz or vanadium will contain the manganese at temperatures up to about 900°C. Sections 6, 7 and 8 that follow were specifically written to describe the method of chemical separation and subsequent counting of the 54Mn activity. When one elects to count the iron dosimeters directly, those portions of Sections 6, 7 and 8 that pertain to radiochemical separation should be disregarded. Note 18212;The following portions of this test method apply also to direct sample-counting methods: 6.1-6.3, 7.4, 7.9, 7.10, 8.1-8.5, 8.18, 8.19, and 10-13. FIG. 1 54Fe(n,p)54Mn Cross Section ^SCOPE: 1.1 This test method describes procedures for measuring reaction rates by the activation reaction 54Fe(n,p)54Mn. 1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.2 MeV and for irradiation times up to about 3 years (for longer irradiations, see Practice E 261). 1.3 With suitable techniques, fission-neutron fluence rates above 108 cm−2·s−1 can be determin......

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron

ASTM C1502-09 氧化铀和氧化钆中氯和氟总含量的标准试验方法

The method is designed to show whether or not the tested materials meet the specifications as given in either Specification C 753, C 776, C 888 or C 922.1.1 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 C1408-09 用直接燃烧红外探测法测定氧化铀粉末和颗粒中总碳量的标准试验方法

Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order to be suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed to determine whether the carbon content meets Specifications C 753, C 776, C 888, and C 922.1.1 This test method covers the determination of carbon in nuclear-grade uranium oxide powders and pellets to determine compliance with specifications. 1.2 Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method. 1.3 This test method covers the determination of 5 to 500 μg of residual carbon. 1.4 This test method describes an induction furnace carrier gas combustion system equipped with an infrared detector. It may also be applied to a similar instrument equipped with a thermal conductivity detector. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.5.1 The preferred system of units is micrograms carbon per gram of sample (μg/g sample) or micrograms carbon per gram of uranium (μg/g U). 1.6 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 Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method

ASTM C1233-09 核材料中当量硼含量测定的标准实施规范

1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic their masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum. 1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials