F80 核仪器与核探测器综合 标准查询与下载

EJ/T 604-2005 NIM标准机箱、插件产品规范

本规范规定了NIM标准机箱(以下简称机箱)及NIM标准插件(以下简称插件)的技术要求、试验方法和检验规则。 本规范适用于NIM标准机箱及插件的设计、生产和质量检验。

Specification for NIM standard bin and module

ASTM E2446-05(2010) 计算机辐射系统分类的标准实施规程

There are several factors affecting the quality of a CR image including the spatial resolution of the IP system, geometrical unsharpness, scatter and contrast sensitivity (signal-to-noise ratio), as well as software. There are several additional factors (for example, scanning parameters), which affect the accurate reading of images on exposed IPs using an optical scanner. This practice is to be used to establish a classification of CR system classes on the basis of a normalized SNR. Due to the difference between the methods, it is required to specify the CR system classes with spatial resolution values. The CR system classes in this document do not refer to any particular manufacturers’ imaging plates. A CR system class results from the use of a particular imaging plate together with the exposure conditions, particularly total exposure, the scanner type and software and the scanning parameters. This classification system provides a means to compare differing CR technologies, as is common practice with film systems, which guides the user to the appropriate configuration, IP and technique for the application at hand. The class selected may not match the imaging performance of a corresponding film class due to the difference in the spatial resolution and scatter sensitivity. Therefore, the practice should always use IQIs for proof of contrast sensitivity and spatial resolution. The quality factors can be determined most accurately by the tests described in this practice. Some of the system tests require special tools, which may not be available in user laboratories. Simpler tests are described for quality assurance in Practice E2445, which are designed for a fast test of the quality of CR systems and long-term stability and are recommended as practical user tests, should the user not have the special tools available as needed for the tests in this practice. Manufacturers of industrial CR systems will use this practice. Users of industrial CR systems may also perform the tests and measurements outlined in this practice, provided that the required test equipment is used and the methodology is strictly followed. Any alternative methods may be applied if equivalence to the methods of this practice is proven to the appropriate Cognizant Engineering Organization. The publication of CR system classes will enable specifying bodies and contracting parties to agree to particular system class, as a first step in arriving at the appropriate settings of a system, or the selection of a system. Confirmation of necessary image quality shall be achieved by using Practice E2033.1.1 This practice describes the evaluation and classification of a computed radiography (CR) system, a particular phosphor imaging plate (IP), system scanner and software, in combination with specified metal screens for industrial radiography. It is intended to ensure that the evaluation of image quality, as far as this is influenced by the scanner/IP system, meets the needs of users. 1.2 The practice defines system tests to be used to classify the systems of different suppliers and make them comparable for users. 1.3 The CR system performance is described by signal and noise parameters. For film systems, the signal is represented by gradient and the noise by granularity. The signal-to-noise ratio is normalized by the basic spatial resolution of the system and is part of classification. The normalization is given by the scanning aperture of 100 µm diameter for the micro-photometer, which is defined in Test Method E1815 for film system ......

Standard Practice for Classification of Computed Radiology Systems

ASTM C1473-05 α光谱测定法放化测定尿中铀同位素的标准试验方法

This test method is used to detect possible exposures to uranium isotopes from occupational operations.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 E2446-05 计算机辐射系统分类的标准实施规程

1.1 This practice describes the evaluation and classification of a computed radiography (CR) system, a particular phosphor imaging plate (IP), system scanner and software, in combination with specified metal screens for industrial radiography. It is intended to ensure that the evaluation of image quality, as far as this is influenced by the scanner/IP system, meets the needs of users.1.2 The practice defines system tests to be used to classify the systems of different suppliers and make them comparable for users.1.3 The CR system performance is described by signal and noise parameters. For film systems, the signal is represented by gradient and the noise by granularity. The signal-to-noise ratio is normalized by the basic spatial resolution of the system and is part of classification. The normalization is given by the scanning aperture of 100 m diameter for the micro-photometer, which is defined in Test Method E 1815 for film system classification. This practice describes how the parameters shall be measured for CR systems.1.4 The values stated in SI 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 to determine the applicability of regulatory limitations prior to use.

Standard Practice for Classification of Computed Radiology Systems

ASTM E2059-05 快中子剂量测定用核研究乳剂的应用和分析的标准规程

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 low energy limit of appli......

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

ASTM E2445-05 计算机辐射系统的合格鉴定和长期稳定性的标准规程

1.1 This practice specifies the fundamental parameters of computed radiography systems to assure satisfactory and repeatable results for nondestructive testing.1.2 This practice describes the evaluation of Computed Radiology (CR) systems for industrial radiography. It is intended to ensure that the evaluation of image quality, as far as this is influenced by the scanner/IP system, meets the needs of users and enables the test of long-term stability. 1.3 Each of the tests described may be performed with individual gages specified. The user shall decide which tests shall be used for system control using individual test objects or the CR test phantom178; (Appendix X1). The computed radiological tests, specified as "user tests" in this practice, may be utilized at appropriate intervals determined by the user, based on the application of the examination operations. The tests shall be appropriate for the materials and range of use of the system. Fading, uniformity, and erasure tests shall also be part of the control system. All other tests for qualification and capability are to be performed and certified by the CR equipment manufacturer.1.4 The values stated in SI units are to be regarded as the standard. Values in inch-pound units are for information purposes.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 Practice for Qualification and Long-Term Stability of Computed Radiology Systems

BS ISO 6980-2:2004 核能.参考β粒子辐射.辐射场的基本数量特性的相关校正基础

This part of ISO 6980 specifies methods for the measurement of the directional absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,066 to 3,54 MeV (maximum energy). Radiation energies outside this range are beyond the scope of this standard. While measurements in a reference geometry (depth of 0,07 mm at perpendicular incidence in a tissue-equivalent slab phantom) with a reference class extrapolation chamber are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. The ambient dose equivalent, H(10) as used for area monitoring of strongly penetrating radiation, is not an appropriate quantity for any beta radiation, even for that penetrating a 10 mm thick layer of ICRU tissue (i.e. Emax > 2 MeV). If adequate protection is provided at 0,07 mm, only rarely will one be concerned with other depths, for example 3 mm. This document is geared towards organizations wishing to establish reference-class dosimetry capabilities for beta particles, and serves as a guide to the performance of dosimetry with the reference class extrapolation chamber for beta-particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.

Nuclear energy - Reference beta-particle radiation - Calibration fundamentals related to basic quantities characterizing the radiation field

ISO/ASTM 51607:2004 丙氨酸-EPR剂量测定系统的使用规程

1．1 本标准规定了使用丙氨酸一EPR剂量测量系统测定光子和电子照射下被照射材料中的吸收剂量 所涉及的剂量计材料的选择、剂量计制备、仪器设备和剂量测量程序。该系统依赖于电子顺磁共振谱仪 对丙氨酸中氨基酸衍生的自由基的测量。该系统被定为参考标准级剂量系统(见GB／T 16640)。 1．2本标准适用于在下述条件下测量吸收剂量的丙氨酸一EPR剂量测量系统： 1．2．1 吸收剂量范围：1 Gy～lOGy。 1．2．2 吸收剂量率：≤lOGy·S(连续辐射场) ≤5×10Gy·s(脉冲辐射场)。 1．2．3 辐射能量范围：0．1 MeV~28 MeVu。 1．2．4辐照温度范围：一60℃～90℃。 1．3 以国际单位制给出的值作为标准值，括号内的量值仅供参考。 1．4本标准不涉及与使用相关的安全问题。本标准的使用者负责建立适用的安全和健康标准，并在使 用前确定其适用的限制范围。

Practice for use of the alanine-EPR dosimetriy system

ISO/ASTM 51940:2004 无生殖力昆虫释放计划的剂量测定指南

1 This guide outlines dosimetric procedures to be fol-lowed for the radiation sterilization of live insects for use in pest management programs. The primary use of irradiated, reproductively sterile insects is in the Sterile Insect Technique, where large numbers of sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of sterile insects is as benign hosts for rearing insect parasitoids. The procedures outlined in this guide will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of this guide. Note 1—Dosimelry is only one component of a total quality control program to ensure that irradiated insects arc adequately sterilized and sufficiently competitive or otherwise suitable for their intended purpose. 2 This guide covers dosimetry in the irradiation of insects for these types of irradiators: self-contained dry-storage Cs or Co irradiators, large-scale gamma irradiators, and electron accelerators. Additional, detailed information on dosimetric procedures to be followed in installation qualification, opera-tional qualification, performance qualification, and routine product processing can be found in ISO/ASTM Practices 51608 (X-ray [bremsstrahlung] facilities), 51649 (electron beam facilities), 51702 (large-scale gamma facilities), and ASTM Practice E2116 (self-contained dry-storage gamma facilities). 3 The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy. 4 This guide refers, throughout the text, specifically to reproductive sterilization of insects. It is equally applicable to radiation sterilization of invertebrates from other taxa (for example, Acarina, Gastropoda) and to irradiation of live insects or other invertebrates for other purposes (for example, induc-ing mutations), provided the absorbed dose is within the range specified in 1.3. 5 This guide also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the insects have been irradiated. 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.

Guide for dosimetry for sterile insects release programs

ISO/ASTM 51702:2004 辐射加工用γ辐射装置中剂量测定的实施规程

1 This practice outlines the installation qualification pro-gram for an irradiator and the dosimetric procedures to be followed during operational qualification, performance quali-fication, and routine processing in facilities that process prod-uct with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to installation qualification, operational qualification, performance qualifica-tion, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory absorbed-dose limits is not within the scope of this practice. Note 1—Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices. Note 2—ISO/ASTM Practices 51649 and 51608 describe dosimetric procedures for electron beam and X-ray (bremsstrahlung) irradiation facilities for radiation processing. 2 For the irradiation of food and the radiation sterilization of health care products, other specific ISO/ASTM or ISO standards exist. For food irradiation, see ISO/ASTM Practice 51204. For the radiation sterilization of health care products, see ISO 11137. In those areas covered by ISO/ASTM Practice 51204 or ISO 11137, those standards take precedence. 3 For guidance in the selection and calibration of dosim-etry systems, and interpretation of measured absorbed dose in the product, see ISO/ASTM Guide 51261 and ASTM Practice E 666. For the use of specific dosimetry systems, see ASTM Practices E 1026 and E 2304, and ISO/ASTM Practices 51205. 51275. 51276, 51310, 51401, 51538, 51540, 51607, 51650, and 51956. For discussion of radiation dosimetry for gamma-rays and X-rays also see ICRU Report 14. 4 Tliis 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 gamma irradiation facility for radiation processing

ANSI/ASTM E1539:2004 辐射灵敏指示器的使用指南

This guide covers the use of radiation-sensitive indicators in radiation processing. These indicators may be labels, papers, or inks which undergo a color change or become colored when exposed to ionizing radiation. The purpose of these indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels. Such materials are not dosimeters and should not be used as a substitute for proper dosimetry. Information about dosimetry systems for ionizing radiation is provided in other ASTM documents (see Guide E1261). 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.

Guide for the Use of Radiation-Sensitive Indicators

ISO/ASTM 51310:2004 放射性铬光波导剂量测定系统使用规程

1 This practice covers the procedures for handling, test-ing, and using a radiochromic optical waveguide dosimetry system to measure absorbed dose in materials irradiated by photons in terms of absorbed dose in water. 2 This practice applies to radiochromic optical waveguide dosimeters that can be used within part or all of the specified ranges as follows: 2.1 The absorbed dose range is from 1 to 10 000 Gy for photons. 2.2 The absorbed dose rate is from 0.001 to 1000 Gy/s. 2.3 The radiation energy range for photons is from 0.1 to 10 MeV. 2.4 The irradiation temperature range is from -78 to -60℃. 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 use of a radiochromic optical waveguide dosimetry system

ISO/ASTM 51275:2004 放射性铬薄膜剂量测定系统使用规程

1 This practice covers the procedures for handling, test-ing, and using a radiochromic film dosimetry system to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose in water. 2 This practice applies to radiochromic film dosimeters that can be used within part or all of the specified ranges as follows: 2.1 The absorbed dose range is 1 Gy to 100 kGy. 2.2 The absorbed dose rate is 1 × 10 to 1 × 10 Gy/s (1-4). 2.3 The radiation energy range for both photons and electrons is 0.1 to 50 MeV. 2.4 The irradiation temperature range is -78 to +60℃. 3 This practice applies to radiochromic films of various formats, including small pieces used to measure a single dose value, strips used for one-dimensional dose-mapping, and sheets used for two-dimensional dose-mapping. Three-dimensional dose-mapping may be achieved by proper place-ment of any of these formats. 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. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this practice.

Practice for use of a radiochromic film dosimetry system

ISO/ASTM 51540:2004 放射性铬液体剂量测定系统使用规程

1 This practice covers the procedures for preparation, handling, testing, and using radiochromic liquid dosimetry systems of radiochromic dye solutions held in sealed or capped containers (for example, ampoules, vials). It also covers the use of spectrophotometric or photometric readout equipment for measuring absorbed dose in materials irradiated by photons and electrons. 2 This practice applies to radiochromic liquid dosimeter solutions that can be used within part or all of the specified ranges as follows: 2.1 The absorbed dose range is from 0.5 to 40 000 Gy for photons and electrons. 2.2 The absorbed dose rate is from 10 to 10 Gy/s. 2.3 The radiation energy range for photons is from 0.01 to 20 MeV. 2.4 The radiation energy range for electrons is from 0.01 to 20 MeV. NOTE 1—Since electrons with energies less than 0.01 MeV may not penetrate the container of the solution, the solutions may be stirred in an open beaker with the electrons entering the solutions directly (1). 2.5 The irradiation temperature range is from -40 to +60℃. 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. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this practice.

Practice for use of a radiochromic liquid dosimetry system

ISO 16797:2004 核能.索格利特式耐化学试验.高放射性废弃物用陶瓷容器的应用

This International Standard describes the Soxhlet-mode parameter test to assess the chemical durability of materials by measuring the initial dissolution rate in pure water. The measurement is performed at the boiling point of water, at which the dissolution rate is considerably higher than at room temperature. In most cases, the alteration phenomena are therefore significantly accelerated. The test described in this International Standard is intended to measure the initial dissolution rate; it is thus applicable only to nonporous materials (or materials with small, closed porosity) for which the primary alteration phenomenon is a surface reaction mechanism (diffusion mechanisms are involved in the dissolution of porous media). The test results can therefore be compared only with findings obtained for nonporous materials if serious errors of interpretation are to be avoided. The resulting "initial dissolution rate in pure boiling water at atmospheric pressure" can be used to compare materials of the same type (e.g. oxides), provided their initial dissolution is governed by the same mechanism (e.g. surface reactions). This parameter test cannot be used to assess the long-term behaviour of a material, which generally requires several tests, modelling and validation, as described, for example, in Standard ENV 12920. This test is applicable to any glass, vitrified material (i.e. material resulting from a vitrification process) or nonporous oxide material with a morphology that allows the preparation of monolithic test coupons of known surface area. It determines the initial dissolution rate of the material in deionized water at the boiling point (approximately 100 ℃) by analysis of the leaching solution and by measurement of the specimen mass loss.

Nuclear energy - Soxhlet-mode chemical durability test - Application to vitrified matrixes for high-level radioactive waste

NF C01-393:2004 电工词汇.第393部分:核用仪器仪表.物理现象和基本概念

Electrotechnical Vocabulary - Part 393 : nuclear instrumentation - Physical phenomena and basic concepts.

ANSI/ASTM E2343:2004 常规剂量测定系统的性能表征标准实施规范

Standard Practice for Performance Characterization of Routine Dosimetery Systems

ANSI/ASTM E1540:2004 放射铬液体溶液剂量测定系统使用的实施规范

This practice covers the preparation, handling, testing, and procedure for using radiochromic liquid dosimetry systems of radiochromic dye solutions held in sealed or capped containers (for example, ampoules, vials) and the spectrophotometric or photometric readout equipment for measuring absorbed dose in materials irradiated by photons and electrons in terms of absorbed dose in water. This practice applies to radiochromic liquid dosimeter solutions that can be used within part or all of the specified ranges as follows: The absorbed dose range is from 0.5 to 40000 Gy for photons and electrons. The absorbed dose rate is from 10 -3 to 1011 Gy/s. The radiation energy range for photons is from 1 to 20 MeV. The radiation energy range for electrons is from 0.01 to 20 MeV. Note 1-Since low-energy electrons, such as 0.01 MeV, may not penetrate the container of the solution, the solutions may be used in a stirred open beaker with the electrons entering the solutions directly (1). The irradiation temperature range is from -40 to +60?C. 1.3 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.

Practice for Use of a Radiochromic Liquid Dosimetry System

ASTM E722-04 确定电子辐射强度试验用等效单能级中子流量的能级中中子能量流量能谱的特征的标准规程

1.1 This practice covers procedures for characterizing a neutron fluence from a source in terms of an equivalent monoenergetic neutron fluence. It is applicable to neutron effects testing, to the development of test specifications, and to the characterization of neutron test environments. The sources may have a broad neutron-energy spectrum, or may be mono-energetic neutron sources with energies up to 20 MeV. The relevant equivalence is in terms of a specified effect on certain physical properties of materials upon which the source spectrum is incident. In order to achieve this, knowledge of the effects of neutrons as a function of energy on the specific property of the material of interest is required. Sharp variations in the effects with neutron energy may limit the usefulness of this practice in the case of mono-energetic sources.1.2 This practice is presented in a manner to be of general application to a variety of materials and sources. Correlation between displacements () caused by different particles (electrons, neutrons, protons, and heavy ions) is beyond the scope of this practice. In radiation-hardness testing of electronic semiconductor devices, specific materials of interest include silicon and gallium arsenide, and the neutron sources generally are test and research reactors and californium-252 irradiators.1.3 The technique involved relies on the following factors: (1) a detailed determination of the energy spectrum of the neutron source, and (2) a knowledge of the degradation (damage) effects of neutrons as a function of energy on specific material properties.1.4 The detailed determination of the neutron energy spectrum referred to in need not be performed afresh for each test exposure, provided the exposure conditions are repeatable. When the spectrum determination is not repeated, a neutron fluence monitor shall be used for each test exposure.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 Practice for Characterizing Neutron Energy Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics

ASTM E722-04e1 确定电子辐射强度试验用等效单能级中子流量的能级中中子能量流量能谱的特征的标准规程

1.1 This practice covers procedures for characterizing a neutron fluence from a source in terms of an equivalent monoenergetic neutron fluence. It is applicable to neutron effects testing, to the development of test specifications, and to the characterization of neutron test environments. The sources may have a broad neutron-energy spectrum, or may be mono-energetic neutron sources with energies up to 20 MeV. The relevant equivalence is in terms of a specified effect on certain physical properties of materials upon which the source spectrum is incident. In order to achieve this, knowledge of the effects of neutrons as a function of energy on the specific property of the material of interest is required. Sharp variations in the effects with neutron energy may limit the usefulness of this practice in the case of mono-energetic sources.1.2 This practice is presented in a manner to be of general application to a variety of materials and sources. Correlation between displacements () caused by different particles (electrons, neutrons, protons, and heavy ions) is beyond the scope of this practice. In radiation-hardness testing of electronic semiconductor devices, specific materials of interest include silicon and gallium arsenide, and the neutron sources generally are test and research reactors and californium-252 irradiators.1.3 The technique involved relies on the following factors: (1) a detailed determination of the energy spectrum of the neutron source, and (2) a knowledge of the degradation (damage) effects of neutrons as a function of energy on specific material properties.1.4 The detailed determination of the neutron energy spectrum referred to in need not be performed afresh for each test exposure, provided the exposure conditions are repeatable. When the spectrum determination is not repeated, a neutron fluence monitor shall be used for each test exposure.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 Practice for Characterizing Neutron Energy Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics