F80 核仪器与核探测器综合 标准查询与下载

IEC 61562:2001 辐射防护仪器 测量粮食中β-辐射放射性核素的比活度用的便携设备

This International Standard applies to portable instruments used for measuring the specific activity of beta-emitting radionuclides in food/foodstuffs and intended for operation under field conditions. This does not apply to low background laboratory instrumentation requiring highly skilled personnel. The instruments designed for measurement of beta contamination in foodstuffs under field conditions should not require special sample preparation other than machining (cutting, grinding, etc.). These instruments may be used in principle to measure beta emitting surface contamination and other radiation measurements as well, but these applications lie outside the scope of this standard. The same instruments intended for measuring foodstuffs can also be used for the measurement of environmental samples, such as soil, sewage, plant and animal life, etc. These instruments can be used to determine specific beta activity for a wide variety of samples under this standard. The purpose of this standard is to specify the main performance characteristics of instruments intended for measurement of specific activity of beta-emitting radionuclides in foodstuffs, their methods of testing and documentation requirements.

Radiation protection instrumentation - Portable equipment for measuring specific activity of beta-emitting radionuclides in foodstuffs

NF C01-394/A2:2001 电工词汇.第394章:核用仪器仪表.仪表

Electrotechnical vocabulary - Chapter 394 : nuclear instrumentation - Instruments.

ASTM C1508-01(2006) 用X射线荧光光谱测定法UF-6和硝酸铀酰中溴和氯的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 Specifications C 787 and C 788.1.1 This method covers the determination of bromine (Br) and chlorine (Cl) in uranium hexafluoride (UF6) and uranyl nitrate solution. The method as written covers the determination of bromine in UF6 over the concentration range of 0.2 to 8 956;g/g, uranium basis. The chlorine in UF6 can be determined over the range of 4 to 160 956;g/g, uranium basis. Higher concentrations may be covered by appropriate dilutions. The detection limit for Br is 0.2 956;g/g uranium basis and for Cl is 4 956;g/g uranium basis.1.2 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 Bromine and Chlorine in UF₆ and Uranyl Nitrate by X-Ray Fluorescence (XRF) Spectroscopy

ASTM C1415-01a(2007) 用α能谱测定法测定钚-238同位素丰度的标准试验方法

This test method is used when the determined of 238Pu isotopic abundance is required for plutonium samples.1.1 This test method covers the use of alpha spectrometry for determining the 238Pu isotopic abundance in plutonium samples. It is particularly useful for samples in which the 238Pu content is less than 1 % of the total plutonium content. For such samples, mass spectrometric results are less reliable than those from alpha spectrometry because of interference from any 238U isobar remaining after ion exchange.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 determine the applicability of regulatory limitations prior to use.

Standard Test Method for ²³⁸Pu Isotopic Abundance by Alpha Spectrometry

ASTM C1415-01 用α能谱测定法测定钚-238同位素丰度的标准试验方法

1.1 This test method covers the use of alpha spectrometry for determining the 238Pu isotopic abundance in plutonium samples. It is particularly useful for samples in which the 238Pu content is less than 1% of the total plutonium content. For such samples, mass spectrometric results are less reliable than those from alpha spectrometry because of interference from any 238U isobar remaining after ion exchange. 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 determine the applicability of regulatory limitations prior to use.

Standard Test Method for ²³⁸Pu Isotopic Abundance by Alpha Spectrometry

ASTM C1508-01 用X射线荧光光谱测定法UF-6和硝酸铀酰中溴和氯的含量的标准试验方法

1.1 This method covers the determination of bromine (Br) and chlorine (Cl) in uranium hexafluoride (UF6) and uranyl nitrate solution. The method as written covers the determination of bromine in UF6 over the concentration range of 0.2 to 8 956;g/g, uranium basis. The chlorine in UF6 can be determined over the range of 4 to 160 956;g/g, uranium basis. Higher concentrations may be covered by appropriate dilutions. The detection limit for Br is 0.2 956;g/g uranium basis and for Cl is 4 956;g/g uranium basis.1.2 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 Bromine and Chlorine in UF₆ and Uranyl Nitrate by X-Ray Fluorescence (XRF) Spectroscopy

ASTM C1507-01 土壤中锶-90的放射化学的测定的标准试验方法

1.1 This test method is applicable to the determination of strontium-90 in soil at levels of detection dependent on count time, sample size, detector efficiency, background, and recovery.1.2 This test method is designed for the analysis of ten grams of soil, previously collected and treated as described in Practices C 998 and C 999. This test method may not be able to completely dissolve all soil matrices.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 Test Method for Radiochemical Determination of Strontium-90 in Soil

ASTM E721-01 电子辐射强度试验用中子激活箔测定中子能谱的标准指南

1.1 This guide covers procedures for determining the energy-differential fluence spectra of neutrons used in radiation-hardness testing of electronic semiconductor devices. The types of neutron sources specifically covered by this guide are fission or degraded energy fission sources used in either a steady-state or pulse mode.1.2 This guide provides guidance and criteria that can be applied during the process of choosing the spectrum adjustment methodology that is best suited to the available data and relevant for the environment being investigated. 1.3 This guide is to be used in conjunction with Guide E 720 to characterize neutron spectra. Note 18212;Although Guide E 720 only discusses activation foil sensors, any energy-dependent neutron-responding sensor for which a response function is known may be used (1).Note 28212;For terminology used in this guide, see Terminology E 170.1.4 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 Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics

IEC 61976:2000 核仪器装置.光谱测定法.HPGe核γ射线光谱测定法中光谱底色的特性

This International Standard applies to gamma-ray spectra collected with hyperpure germanium detectors (HPGe) for use in gamma-ray spectrometry, especially for low-background detectors and measurements. This standard defines terms used to describe the background and the background spectrum itself. This standard does not present methods that describe how to reduce the background. The object of this standard is to provide a uniform method for describing and characterizing the background in a spectrum from an HPGe detector. Definitions and methods are applied to define values for an HPGe detector that is considered to be used for low-background measurements. This approach provides both manufacturers and end users with a way to specify the low-background performance of the detector and allows the comparison of detectors used for these kinds of measurements. The background and peak values determined by the procedures in this standard will provide the user with information regarding the expected background performance of the detector, in particular to allow for the comparison of several different detectors.

Nuclear instrumentation - Spectrometry - Characterization of the spectrum background in HPGe nuclear gamma-ray spectrometry

ISO 12789:2000 中子参考辐射 模拟工作场所中子场的产生的特性及方法

This International Standard gives guidance for producing and characterizing simulated workplace neutron fields that are to be used for calibrating neutron-measuring devices for radiation protection purposes. Both calculational and spectrometric measurement methods are discussed. Neutron energies in these reference fields range from approximately thermal neutron energies to several hundred GeV. The methods of production and the monitoring techniques for the various types of neutron fields are discussed, and the methods of evaluating and reporting uncertainties for these fields are also given.

Reference neutron radiations - Characteristics and methods of production of simulated workplace neutron fields

IEC 61577-2:2000 辐射防护仪表 氡和氡降解产品的测量仪器 第2部分:氡测量仪器的专门要求

The requirements of this part of IEC 61577 are applicable to instruments for measuring airborne radon volume activity. This part is applicable to instruments used to measure radon in work places, in dwellings, outdoors and in soil. The method of measurement depends on the exact objective but the requirements are for general purpose instruments to be used for radiological protection or research applications. This standard applies to all types of radon measuring instruments that are based on grab sampling, continuous and integrated methods. The activity can be measured continuously by pumping or by diffusing the air containing radon into the detector or at a particular moment by measuring the activity of an air sample (grab sampling). The purpose of this part of IEC 61577 is to specify the main performance characteristics of instruments intended for measurement of airborne radon volume activity, their specific method of testing and documentation requirements. This part is to be used with IEC 61577-1.

Radiation Protection Instrumentation - Radon and Radon Decay Product Measuring Instruments - Part 2: Specific Requirements for Radon Measuring Instruments (Edition 2.0)

BS EN 60580:2000 放射区域剂量计

This International Standard specifies the performance and testing of DOSE AREA PRODUCT METERS with IONIZATION CHAMBERS intended to measure DOSE AREA PRODUCT and/or DOSE AREA PRODUCT RATE to which the PATIENT is exposed during MEDICAL RADIOLOGICAL EXAMINATIONS. The object of this International Standard is 1) to establish requirements for a satisfactory level of performance for DOSE AREA PRODUCT METERS, and 2) to standardize the methods for the determination of compliance with this level of performance.

Dose area product meters

ISO 3999-1:2000 辐射防护 工业用Υ辐射照相设备 第1部分:性能、设计和试验规范

This part 01 ISO 3999 specriies the perlormance, design and test requirements oi apparatus lor gamma radiography with portable. mobiie and fixed exposure containers oi the various categories defined In clause 4. it applies to apparatus designed to allow the controlled use oi gamma radiation emitted by a sealed radioactive source tor industrial radiography purposes in order that persons will be saieguarded when the apparatus is used in conformity with the regulations in force regarding radiation protection. It is emphasised, however, that so far as transport oi apparatus and sealed radioactive source is concerned, compliance with this part oi ISO 3999 Is no substitute for satisfying the requirements oi international relevant transport regulations (IAEA Fleguiations tor the safe transport ol radioactive materials, rel. IAEA-STI-PUD 998, Safety Standards Series ST】 and ST2﹐ and/or the relevant national transport regulations). The operational use oi apparatus ior industrial gamma radiography is not covered by this part at ISO 3999〈 Users of this equipment shall compiy With national regulations and codes oi practice.

Radiation protection - Apparatus for industrial gamma radiography - Part 1: Specifications for performance, design and tests

BS IEC 60692:2000 核仪器法.利用电离辐射的密度计.定义和试验方法

This International Standard relates to definitions, test methods and procedures for density gauges utilizing ionizing radiation, designed for measuring the density of liquids, gas vapours, slurries, or fluidized solids. The output signals from density gauges may be either analogue or digital. The measurement system may also include multiple input signals with various means of compensation and signal conditioning prior to the output signals. Reference to compliance with this standard shall identify any deviations and the reasons for such deviations. Safety aspects are covered in other IEC and ISO standards (for example IEC 60405, ISO 2919, ISO 7205, ISO 9978). Consideration should also be given to compliance with all applicable national and local regulations and codes of practice. NOTE 1 Many density measuring systems in use today have multiple sensors (i.e. temperature and pressure) and employ various means of compensating the basic sensor signals to minimize the effects of extraneous influence quantities that introduce measurement errors, or to correct the density reading to a standard reference temperature or pressure. Dedicated microprocessors have further enhanced multiple input signal processing and error compensation techniques. NOTE 2 In this standard, the term "density" means the density of the irradiated material being measured. It is used interchangeably to mean mass per volume or per cent solids. Radiometric sensors in density applications generally measure mass attenuation of a photon beam. The object of this standard is to establish definitions, specifications and test methods for nuclear density gauges.

Nuclear instrumentation - Density gauges utilizing ionizing radiation - Definitions and test methods

ASTM C1476-00 感应耦合等离子质谱法分析锝99用尿的标准试验方法

1.1 This test method covers the determination of the concentration of technetium-99 in urine using inductively coupled plasma-mass spectrometry (ICP-MS). This test method can be used to support uranium enrichment and reclamation facility bioassay programs.1.2 The minimum detectable concentration for this test method, using a quadrupole ICP-MS, is approximately 1.0 ng/L (0.62 Bq/L).

Standard Test Method for Analysis of Urin for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry

ASTM C1458-00 用量热分析进行钚、氚和241Am无损试验的标准试验方法

1.1 This test method describes the nondestructive assay (NDA) of plutonium, tritium, and 241Am using heat flow calorimetry. For plutonium the range of applicability corresponds to 1 g to > 2000 g quantities while for tritium the 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.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 Nondestructive Assay of Plutonium, Tritium and ²⁴¹Am by Calorimetric Assay

ASTM C1473-00 α光谱法放化测定尿中铀同位素含量的标准试验方法

1.1 This test method is applicable to the determination of uranium in urine at levels of detection dependent on sample size, count time, detector efficiency, background, and tracer yield. It is designed as a screening tool for detection of possible exposure of occupational workers.1.2 This test method is designed for 50 mL of urine. This test method does not address the sampling protocol or sample preservation methods associated with its use.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 Test Method for Radiochemical Determination of Uranium Isotopes in Urine by Alpha Spectrometry

ASTM C1475-00 土壤中镎237测定的标准指南

1.1 This guide covers the detemination of neptunium-237 in soil by means of radiochemical separations and alpha spectrometry. This guide provides options in the selection of sample preparation, separation, and measurement. Although neptunium-237 is not a component of global fallout, it is a product of production reactors and spent fuel processing. This guide is designed for analysis of ten grams of soil previously collected and treated in accordance with Practices C998 and C999. Larger-size samples of environmental soil may also be analyzed, as long as the concentrations of interferences such as uranium and thorium are at or near environmental concentrations. Depending on the choice of a sample dissolution method, all chemical forms of neptunium may not be completely solubilized. This guide should allow the determination of neptunium-237 concentrations from sub becquerel per gram levels to applicable standards depending on count time, sample size, detector efficiency, background, and tracer yield. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibilityof the user of this standard to establish appropriate safety and health practices and determine the applicability of limitations prior to use. Specific precautionary statements are given in Section 8.

Standard Guide for Determination of Neptunium-237 in Soil

ASTM C1455-00 用Υ射线光谱法对特殊核物质含量的无损分析的标准指南

1.1 This guide addresses methods used to prepare for and to perform, using gamma-ray measurements, the nondestructive assay (NDA) of radioisotopes, for example, 235U, or 239Pu, remaining as holdup in nuclear facilities. Holdup occurs in facilities where nuclear material is processed. This guide includes the measurement of holdup of Special Nuclear Material (SNM) in places where holdup may occur, such as in process equipment, and in exhaust ventilation systems. This guide includes information useful for management planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources.1.2 The measurement of nuclear material help up in process equipment is both an art and a science. It is subject to the constraints of politics, economics plus health and safety requirements, as well as to the laws of physics. The measurement process often is long and tedious and is performed under difficult circumstances of location and environment. The work combines the features of a detective investigation and a treasure hunt. Nuclear material held up in pipes, ductwork, gloveboxes, heavy equipment, and so forth, usually is distributed in a diffuse and irregular manner. It is difficult to define the measurement geometry, identify the form of the material, and measure it without interference from adjacent sources of radiation. A scientific knowledge of radiation sources and detectors, calibration procedures, geometry and error analysis also is needed ().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 Guide for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods

ASTM E2059-00a 快中子剂量测定用核研究乳剂的应用和分析的标准实施规程

1.1 Nuclear Research Emulsions (NRE) have a long and illustrious history of applications in the physical sciences, earth sciences and biological sciences (,). In the physical sciences, NRE experiments have led to many fundamental discoveries in such diverse disciplines as nuclear physics, cosmic ray physics and high energy physics. In the applied physical sciences, NRE have been used in neutron physics experiments in both fission and fusion reactor environments (). Numerous NRE neutron experiments can be found in other applied disciplines, such as nuclear engineering, environmental monitoring and health physics. Given the breadth of NRE applications, there exist many textbooks and handbooks that provide considerable detail on the techniques used in the NRE method. As a consequence, this practice will be restricted to the application of the NRE method for neutron measurements in reactor physics and nuclear engineering with particular emphasis on neutron dosimetry in benchmark fields (see Matrix E 706).1.2 NRE are passive detectors and provide time integrated reaction rates. As a consequence, NRE provide fluence measurements without the need for time-dependent corrections, such as arise with radiometric (RM) dosimeters (see Test Method E 1005). NRE provide permanent records, so that optical microscopy observations can be carried out anytime after exposure. If necessary, NRE measurements can be repeated at any time to examine questionable data or to obtain refined results.1.3 Since NRE measurements are conducted with optical microscopes, high spatial resolution is afforded for fine structure experiments. The attribute of high spatial resolution can also be used to determine information on the angular anisotropy of the in-situ neutron field (,,). It is not possible for active detectors to provide such data because of in-situ perturbations and finite-size effects (see Section ).1.4 The existence of hydrogen as a major constituent of NRE affords neutron detection through neutron scattering on hydrogen, that is, the well known (n,p) reaction. NRE measurements in low power reactor environments have been predominantly based on this (n,p) reaction. NRE have also been used to measure the 6Li ( n,t) 4He and the 10B (n,) 7Li reactions by including 6Li and 10B in glass specks near the mid-plane of the NRE (,). Use of these two reactions does not provide the general advantages of the (n,p) reaction for neutron dosimetry in low power reactor environments (see Section ). As a consequence, this standard will be restricted to the use of the (n,p) reaction for neutron dosimetry in low power reactor environments.1.5 Limitations The NRE method possesses three major limitations for applicability in low power reactor environments.1.5.1 Gamma-Ray SensitivityGamma-rays create a significant limitation for NRE measurements. Above a gamma-ray exposure of approximately 3R, NRE can become fogged by gamma-ray induced electron events. At this level of gamma-ray exposure, neutron induced proton-recoil tracks can no longer be accurately measured. As a consequence, NRE experiments are limited to low power environments such as found in critical assemblies and benchmark fields. Moreover, applications are only possible in environments where the buildup of radioactivity, for example, fission products, is limited.1.5.2 Low Energy Limit In the measurement of track length for proton recoil events, track length decreases as proton-recoil energy decreases. Proton-recoil track length below approximately 3 in NRE can not be adequately measured with optical microscopy techniques. As proton-recoil track length decreases below approximately 3, it becomes very difficult to measure track length accurately. This 3 track length limit corresponds to a l......

Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry