F80 核仪器与核探测器综合 标准查询与下载

ASTM E720-04e1 电子辐射强度试验中中子波谱测定用中子探测器的选择和使用标准指南

Because of the wide variety of materials being used in neutron-activation measurements, this guide is presented with the objective of bringing improved uniformity to the specific field of interest here: hardness testing of electronics primarily in critical assembly reactor environments. Note 28212;Some of the techniques discussed are useful for 14-MeV dosimetry. See Test Method E 496 for activation detector materials suitable for 14-MeV neutron effects testing. Note 38212;The materials recommended in this guide are suitable for 252Cf or other weak source effects testing provided the fluence is sufficient to generate countable activities. This guide is organized into two overlapping subjects; the criteria used for sensor selection, and the procedures used to ensure the proper determination of activities for determination of neutron spectra. See Terminology E 170 and General Methods E 181. Determination of neutron spectra with activation sensor data is discussed in Guides E 721 and E 944.1.1 This guide covers the selection and use of neutron-activation detector materials to be employed in neutron spectra adjustment techniques used for radiation-hardness testing of electronic semiconductor devices. Sensors are described that have been used at many radiation hardness-testing facilities, and comments are offered in table footnotes concerning the appropriateness of each reaction as judged by its cross-section accuracy, ease of use as a sensor, and by past successful application. This guide also discusses the fluence-uniformity, neutron self-shielding, and fluence-depression corrections that need to be considered in choosing the sensor thickness, the sensor covers, and the sensor locations. These considerations are relevant for the determination of neutron spectra from assemblies such as TRIGA- and Godiva-type reactors and from Californium irradiators. This guide may also be applicable to other broad energy distribution sources up to 20 MeV.Note 18212;For definitions on terminology used in this guide, see Terminology E 170.1.2 This guide also covers the measurement of the gamma-ray or beta-ray emission rates from the activation foils and other sensors as well as the calculation of the absolute specific activities of these foils. The principal measurement technique is high-resolution gamma-ray spectrometry. The activities are used in the determination of the energy-fluence spectrum of the neutron source. See Guide E 721.1.3 Details of measurement and analysis are covered as follows:1.3.1 Corrections involved in measuring the sensor activities include those for finite sensor size and thickness in the calibration of the gamma-ray detector, for pulse-height analyzer deadtime and pulse-pileup losses, and for background radioactivity.1.3.2 The primary method for detector calibration that uses secondary standard gamma-ray emitting sources is considered in this guide and in General Methods E 181. In addition, an alternative method in which the sensors are activated in the known spectrum of a benchmark neutron field is discussed in Guide E 1018.1.3.3 A data analysis method is presented which accounts for the following: detector efficiency; background subtraction; irradiation, waiting, and counting times; fission yields and gamma-ray branching ratios; and self-absorption of gamma rays and neutrons in the sensors.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 ap......

Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics

ASTM E720-04 电子辐射强度试验中中子波谱测定用中子探测器的选择和使用标准指南

1.1 This guide covers the selection and use of neutron-activation detector materials to be employed in neutron spectra adjustment techniques used for radiation-hardness testing of electronic semiconductor devices. Sensors are described that have been used at many radiation hardness-testing facilities, and comments are offered in table footnotes concerning the appropriateness of each reaction as judged by its cross-section accuracy, ease of use as a sensor, and by past successful application. This guide also discusses the fluence-uniformity, neutron self-shielding, and fluence-depression corrections that need to be considered in choosing the sensor thickness, the sensor covers, and the sensor locations. These considerations are relevant for the determination of neutron spectra from assemblies such as TRIGA- and Godiva-type reactors and from Californium irradiators. This guide may also be applicable to other broad energy distribution sources up to 20 MeV.Note 18212;For definitions on terminology used in this guide, see Terminology E 170.1.2 This guide also covers the measurement of the gamma-ray or beta-ray emission rates from the activation foils and other sensors as well as the calculation of the absolute specific activities of these foils. The principal measurement technique is high-resolution gamma-ray spectrometry. The activities are used in the determination of the energy-fluence spectrum of the neutron source. See Guide E 721.1.3 Details of measurement and analysis are covered as follows:1.3.1 Corrections involved in measuring the sensor activities include those for finite sensor size and thickness in the calibration of the gamma-ray detector, for pulse-height analyzer deadtime and pulse-pileup losses, and for background radioactivity.1.3.2 The primary method for detector calibration that uses secondary standard gamma-ray emitting sources is considered in this guide and in General Methods E 181. In addition, an alternative method in which the sensors are activated in the known spectrum of a benchmark neutron field is discussed in Guide E 1018.1.3.3 A data analysis method is presented which accounts for the following: detector efficiency; background subtraction; irradiation, waiting, and counting times; fission yields and gamma-ray branching ratios; and self-absorption of gamma rays and neutrons in the sensors.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 Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics

ANSI N42.20-2003 个人放射性辐射监视仪的性能标准

Prevents performance criteria for active personnel radiation monitors.

Performance Criteria for Active Personnel Radiation Monitors

ISO/ASTM 51400:2003 高剂量照射剂量测定校准实验室的特征和性能规程

1 This practice addresses the specific requirements for laboratories engaged in dosimetry calibrations involving ion-izing radiation, namely, gamma-radiation, electron beams or X-radiation (bremsstrahlung) beams. It specifically describes the requirements for the characterization and performance criteria to be met by a high-dose radiation dosimetry calibra-tion laboratory. 2 The absorbed-dose range is typically between 10 and 10 Gy. 3 This practice addresses criteria for laboratories seeking accreditation for performing high-dose dosimetry calibrations, and is a supplement to the general requirements described in ISO/IEC 17025. 3.1 By meeting these criteria and those in ISO/IEC 17025, the laboratory may be accredited by a recognized accreditation organization. 3.2 Adherence to these criteria will help to ensure high standards of performance and instill confidence regarding the competency of the accredited laboratory with respect to the services it offers. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory

ISO/ASTM 51631:2003 电子束剂量测量和剂量仪标定用测热计量系统的使用规程

1 This practice covers the preparation and use of semi-adiabatic calorimeters for measurement of absorbed dose and routine dosimeter calibration when irradiated with electrons for radiation processing applications. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam. 2 This practice applies to electron beams in the energy range from 1.5 to 12 MeV. 3 The absorbed dose range depends on the absorbing material and the irradiation and measurement conditions. Minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy. 4 The average absorbed-dose rate range shall generally be greater than 10 Gy·s. 5 The temperature range for use of these calorimeters depends on the thermal resistance of the materials, on the calibrated range of the temperature sensor, and on the sensi-tivity of the measurement device. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations

ISO/ASTM 51401:2003 重铬酸盐剂量测定系统的使用规程

1 This practice covers the preparation, testing, and proce-dure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the sys-tem will be referred to as the dichromate system. It is classified as a reference standard dosimetry system (see ISO/ASTM Guide 51261). 2 This practice describes the spectrophotometric analysis procedures for the dichromate system. 3 This practice applies only to γ-rays, x-rays/ bremsstrahlung, and high energy electrons. 4 This practice applies provided the following conditions are satisfied: 4.1 The absorbed dose range is from 2 × 10 to 5 × 10 Gy. 4.2 The absorbed dose rate does not exceed 600 Gy /pulse (12.5 pulses per second), or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources (1). 4.3 For radionuclide gamma-ray sources, the initial pho-ton energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. Note 1—The lower energy limits given are appropriate for a cylindri-cal dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (2). The dichromate system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35). 4.4 The irradiation temperature of the dosimeter shall be above 0℃ and should be below 80℃. Note 2—The temperature coefficient of dosimeter response is known only in the range of 5°to 50℃ (see 4.3). Use outside this range requires determination of the temperature coefficient. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. Specific precau-tionary statements are given in 8.3. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this practice.

Practice for use of a dichromate dosimetry system

ISO 16794:2003 核能.六氟化铀红外线光谱法中碳化合物和氟化物的测定

This International Standard specifies a test method for the determination of hydrocarbons, chlorocarbons and partially or completely substituted halocarbons or halohydrocarbons contained as impurities in uranium hexafluoride (UF6) by infrared (IR) spectrometry. This method cannot be used for compounds giving IR rays with interference by UF6 (for example CF4). The test method is quantitative and applicable in the mole fraction from 0,000 1 % or 0,001 0 %, depending on the type of impurity, up to 0,100 %. The test method can also be used for the determination of hydrofluoric acid (HF) and several elements existing as fluorides; boron in BF3, silicon in SiF4, phosphorus in PF5, molybdenum in MoF6 and tungsten in WF6.

Nuclear energy - Determination of carbon compounds and fluorides in uranium hexafluoride infrared spectrometry

ASTM E2304-03 荧光照相胶片剂量测定系统使用的标准规程

1.1 This practice covers the handling, testing, and procedure for using a lithium fluoride (LiF)-based photo-fluorescent film dosimetry system to measure absorbed dose (relative to water) in materials irradiated by photons or electrons. Other alkali halides that may also exhibit photofluorescence (for example, NaCl, NaF, and KCl) are not covered in this practice. Although various alkali halides have been used for dosimetry for years utilizing thermoluminescence, the use of photoluminescence is relatively new.1.2 This practice applies to photo-fluorescent film dosimeters (referred hereafter as photo-fluorescent dosimeters) that can be used within part or all of the following ranges:1.2.1 Absorbed dose range of 5 10-2 to 3 102 kGy (1-3).1.2.2 Absorbed dose rate range of 0.3 to 2 10 4 Gy/s (2-5)).1.2.3 Radiation energy range for photons of 0.05 to 10 MeV (2).1.2.4 Radiation energy range for electrons of 0.1 to 10 MeV (2).1.2.5 Radiation temperature range of -20 to +60176;C (6,7).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 Use of a Lif Photo-Fluorescent Film Dosimetry System

ASTM E2304-03(2011) 使用Lif照片荧光薄膜计量系统的标准操作规程

A lithium fluoride (LiF)-based photo-fluorescent film dosimetry system provides a means of determining absorbed dose to materials by the photo-stimulated emission of wavelengths longer than that of the stimulation wavelength. The absorbed dose is obtained from the amount of the light emission. Imperfections within the ionic lattice of alkali-halide compounds such as LiF act as traps for electrons and electron holes (positively charged negative-ion vacancies). These imperfections are known as color centers because of the part they play in the compound''s ability to absorb and then release energy in the form of visible-light photons. Like an atom, these color centers have discrete, allowed energy levels, and electrons can be removed from these sites when energy of the appropriate wavelength and intensity is transferred to the material. The resulting fluorescence spectra contain discrete peaks that can cover a range of wavelengths, depending upon the type of alkali-halide (8). An example of fluorescence spectra from a LiF-based dosimeter is provided in Fig. 1. A system of optical filters within a light-detecting instrument (that is, fluorimeter) can be used to block all but a narrow range of wavelengths that are desired for use. Theories on how color centers are formed, how luminescence mechanisms work, and their application in dosimetry are found in Refs (8-13). For characterization studies on specific photo-fluorescent dosimeters see Refs (1-7) and (14-19). In the application of a specific dosimetry system, absorbed dose is determined by use of an experimentally-derived calibration curve. The calibration curve for the photo-fluorescent dosimeter is the functional relationship between ΔEf and D, and is determined by measuring the net fluorescence of sets of dosimeters irradiated to known absorbed doses. These absorbed doses span the range of utilization of the system. Photo-fluorescent dosimetry systems require calibration traceable to national standards. See ISO/ASTM Guide . The absorbed dose is usually specified relative to water. Absorbed dose in other materials may be determined by applying the conversion factors discussed in ISO/ASTM Guide . During calibration and use, possible effects of influence quantities such as temperature, light exposure, post-irradiation stabilization of signal, and absorbed-dose rate need to be taken into account. Photo-fluorescent dosimeters are sensitive to light, especially during irradiation and post-irradiation stabilization (7). Some color centers are sensitive to the UV and blue regions of the spectrum, while other centers are only sensitive to the UV. Therefore, they need to be packaged in appropriate light-tight packaging shortly after manufacture, and during use they need to be packaged or the appropriate filters placed over room lighting. Filtering the light fixtures involved during irradiation may be required for irradiations using low-energy X-rays or electrons where unpackaged dosimeters are used. The signal from photo-fluorescent dosimeters either increases or decreases with time following irradiation, depending on the color center utilized (19). This stabilization process, which can last from hours to days depending on storage temperature (and dose for some color centers) can be accelerated and stabilized by heat treating the dosimeters after irradiation and before readout (see 9.2).

Standard Practice for Use of a LiF Photo-Fluorescent Film Dosimetry System

ASTM E2303-03 辐射处理设施中吸收剂量标记的标准指南

Radiation processing is carried out under fixed path conditions where (a) a process load is automatically moved through the radiation field by mechanical means or (b) a process load is irradiated statically by manually placing product at predetermined positions before the process is started. In both cases the process is controlled in such a manner that the process load position(s) and orientation(s) are reproducible within specified limits. Some radiation processing facilities that utilize a fixed conveyor path for routine processing may also characterize a region within the radiation field for static radiation processing, sometimes referred to as “Off Carrier” processing. Radiation processing may require a minimum absorbed dose (to achieve a desired effect or to fulfill a legal requirement), and a maximum dose that can be tolerated (while the product, material or substance still meets functional specifications or to fulfill a legal requirement). Dose mapping is used to characterize the radiation process and assess the reproducibility of absorbed-dose results, which may be used as part of operational qualification and performance qualification. Dose mapping is used to determine the spatial distribution of absorbed doses and the zone(s) of maximum and minimum absorbed doses throughout a process load, which may consist of an actual or simulated product. Dose mapping is used to establish the relationship between the dose at a reference position and the dose within the minimum and maximum dose zones established for a process load. Dose mapping is used to verify mathematical dose calculation methods. See Guide E 2232. Dose mapping is used to determine the process shutdown and startup transit dose effect on the distribution of absorbed dose and the magnitude of the minimum and maximum doses. Dose mapping is used to assess the impact on the distribution of absorbed dose and the magnitude of the minimum and maximum doses resulting from the transition from one process load to another where changes, for example, in density or product loading pattern may occur.1.1 This document provides guidance in determining absorbed-dose distributions in products, materials or substances irradiated in gamma, X-ray (bremsstrahlung) and electron beam facilities.Note 18212;For irradiation of food and the radiation sterilization of health care products, other specific ISO and ISO/ASTM standards containing dose mapping requirements exist. For food irradiation, see ISO/ASTM 51204, Practice for Dosimetry in Gamma Irradiation Facilities for Food Processing and ISO/ASTM 51431, Practice for Dosimetry in Electron and Bremsstrahlung Irradiation Facilities for Food Processing. For the radiation sterilization of health care products, see ISO 11137: 1995, Sterilization of Health Care Products Requirements for Validation and Routine Control Radiation Sterilization. In those areas covered by ISO 11137, that standard takes precedence. ISO/ASTM Practice 51608, ISO/ASTM Practice 51649, and ISO/ASTM Practice 51702 also contain dose mapping requirements.1.2 Methods of analyzing the dose map data are described. Examples are provided of statistical methods that may be used to analyze dose map data.1.3 Dose mapping for bulk flow processing and fluid streams is not discussed.1.4 Dosimetry is only one component of a total quality program for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the resp......

Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities

BS IEC 61577-2:2000 辐射防护测量仪器.氡和氡降解产物的测量仪.氡测量仪的特殊要求

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 - Specific requirements for radon measuring instruments

ISO/ASTM 52116:2002 自带的干式存储γ射线辐照器的剂量测定实施规范

1 This practice outlines dosimetric procedures to be fol-lowed with self-contained dry-storage gamma-ray irradiators. If followed, these procedures will help to ensure that calibra-tion and testing will be carried out with acceptable precision and accuracy and that the samples processed with ionizing radiation from gamma rays in a self-contained dry-storage irradiator receive absorbed doses within a predetermined range. 2 This practice covers dosimetry in the use of dry-storage gamma-ray irradiators, namely self-contained dry-storage Cs or Co irradiators (shielded freestanding irra-diators). It does not cover underwater pool sources, panoramic gamma-ray sources such as those raised mechanically or pneumatically to irradiate isotropically into a room or through a collimator, nor does it cover self-contained bremsstrahlung x-ray units. 3 The absorbed dose range for the use of the dry-storage self-contained gamma-ray irradiators covered by this practice is typically 1 to 10 Gy, depending on the application. The absorbed-dose rate range typically is from 10 to 10 Gy/min. 4 This practice describes general procedures applicable to all self-contained dry-storage gamma-ray irradiators. For pro-cedures specific to dosimetry in blood irradiation, see ISO/ ASTM Practice 51939. For procedures specific to dosimetry in radiation research on food and agricultural products, see ISO/ASTM Practice 51900. For procedures specific to radia-tion hardness testing, see ASTM Practice E 1249. For proce-dures specific to the dosimetry in the irradiation of insects for sterile release programs, see ISO/ASTM Guide 51940. In those cases covered by ISO/ASTM Practices 51939, 51900, 51940, or ASTM E 1249, those standards take precedence. In addition, this practice does not cover absorbed-dose rate calibrations of radiation protection instrumentation. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry for a self-contained dry-storage gamma-ray irradiator

DIN IEC 62088:2002 核仪表设备.闪烁检测器用光电二极管.试验程序 (IEC 62088:2001)

Nuclear instrumentation - Photodiodes for scintillation detectors - Test procedures (IEC 62088:2001)

DIN EN 13649:2002 固定源辐射.专用气体有机化合物质量浓度的测定.活性炭和溶剂解吸法; 德文版本 EN 13649:2001

This European Standard specifies procedures for the sampling, preparation and analysis of samples of gaseous or vapour phase organic components such as those arising from solvent using processes and can be used as a reference method. NOTE: See Council Directive 13/99/EEC. The results obtained using this Standard are expressed as the mass concentration (mg/m3) of the individual gaseous organic components. This Standard is suitable for use in the range of about 0,5 mg/m3 to 2000 mg/m3. The method utilizes adsorption and is suitable when the desorption efficiency is greater than 80%.

Stationary source emissions - Determination of the mass concentration of individual gaseous organic compounds - Activated carbon and solvent desorption method; German version EN 13649:2001

ISO/ASTM 51539:2002 辐射灵敏指示计使用指南

Guide for use of radiation-sensitive indicators

ISO/ASTM 51956:2002 辐射加工用热致发光剂量测定(TLD)系统使用规程

Practice for use of thermoluminescence-dosimetry (TLD) systems for radiation processing

ISO/ASTM 51940:2002 不育计划的昆虫辐照剂量测定指南

Guide for dosimetry for irradiation of insects for sterile release programs

ISO/ASTM 51818:2002 辐射加工的电子束设备中剂量测定的实施规程

1 This practice covers dosimetric procedures to be fol-lowed to determine the performance of low energy (300 keV or less) single-gap electron beam radiation processing facilities. Other practices and procedures related to facility characteriza-tion, product qualification, and routine processing are also discussed. 2 The electron energy range covered in this practice is from 80 keV to 300 keV. Such electron beams can be generated by single-gap self-contained thermal filament or plasma source accelerators. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry in an electron beam facility for radiation processing at energies between 80 KeV and 300 KeV

ISO/ASTM 51707:2002 辐射加工的剂量测定中不确定度的估算指南

Guide for estimating uncertainties in dosimetry for radiation processing

ISO/ASTM 51702:2002 辐射加工用γ辐照装置中剂量测定的实施规程

Practice for dosimetry in a gamma irradiation facility for radiation processing