F80 核仪器与核探测器综合 标准查询与下载

ISO/ASTM 51650:2002 醋酸纤维素剂量测定系统使用规程

Practice for use of cellulose acetate dosimetry systems

ISO/ASTM 51649:2002 在300 keV 和25 MeV 能量之间辐射加工用电子束设备中剂量测定的实施规程

Practice for dosimetry in an electron beam facility for radiation processing at energies between 300 keV and 25 MeV

ISO/ASTM 51631:2002 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

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

ISO/ASTM 51608:2002 辐射加工用X射线(韧致辐射)设备中放射剂量测定实施规程

Practice for dosimetry in X-ray (bremsstrahlung) facility for radiation processing

ISO/ASTM 51607:2002 丙氨酸-EPR剂量测定系统实施规程

Practice for use of the alanine-EPR dosimetry system

ISO/ASTM 51540:2002 放射性铬液体剂量测定系统使用规程

Practice for use of a radiochromic liquid dosimetry system

ISO/ASTM 51538:2002 酒精-氯苯剂量测定系统使用规程

1 This practice covers the preparation, handling, testing, and procedure for using the ethanol-chlorobenzene dosimetry system to measure absorbed dose in materials irradiated by photons and electrons in terms of absorbed dose in water. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ECB system. It is classified as a reference-standard dosimeter and is also used as a routine dosimetry system (see ISO/ASTM Guide 51261). 2 This practice describes the titration analysis as a stan-dard readout procedure for the ECB dosimeter. Other appli-cable readout methods (spectrophotometric, oscillometric) are described in Annex Al and Annex A2. 3 This practice applies only to gamma rays, X rays, and high-energy electrons. 4 This practice applies provided the following are satis-fied: 4.1 The absorbed dose range shall be from 10 Gy to 2 MGy (1). 4.2 The absorbed dose rate does not exceed 10 Gy s(2). 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 equal to or greater than 4 MeV (3) (see ICRU Reports 34 and 35). Note 1—The lower limits of electromagnetic radiation energy given are appropriate for a cylindrical dosimeter ampoule of 12-mm diameter. Corrections for dose gradients across an ampoule of that diameter or less are not required. The ECB system may be used at energies of incident electrons lower than 4 MeV by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35). The ECB system may also be used at X-ray energies as low as 120 kVp (4). In this range of photon energies the effect caused by the wall is considerable. 4.4 The irradiation temperature of the dosimeter should be within the range from -40℃ to 80℃. Note 2—The temperature dependence of dosimeter response is known only in this range. For use outside this range, the dosimetry system should be calibrated for the required range of irradiation temperatures. 4.5 The effects of size and shape of the irradiation vessel on the response of the dosimeter can adequately be taken into account by performing the appropriate calculations using cavity theory (5). 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. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this practice.

Practice for use of the ethanol-chlorobenzene dosimetry system

ISO/ASTM 51401:2002 重铬酸盐剂量测定系统使用规程

Practice for use of a dichromate dosimetry system

ISO/ASTM 51400:2002 高剂量照射剂量测定校准实验室特征和性能的实施规程

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

ISO/ASTM 51310:2002 放射性铬光波导剂量测定系统使用规程

Practice for use of a radiochromic optical waveguide dosimetry system

ISO/ASTM 51275:2002 放射性铬薄膜剂量测定系统使用规程

Practice for use of a radiochromic film dosimetry system

ISO/ASTM 51261:2002 辐射处理用剂量测定系统的选择和校准指南

1 This guide covers the basis for selecting and calibrating dosimetry systems used to measure absorbed dose in gamma-ray or X-ray fields and in electron beams used for radiation processing. It discusses the types of dosimetry systems that may be employed during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products. This guide also discusses interpretation of absorbed dose and briefly outlines measurements of the uncertainties associated with the dosimetry. The details of the calibration of the analytical instrumentation are addressed in individual dosimetry system standard practices. 2 The absorbed-dose range covered is up to 1 MGy (100 Mrad). Source energies covered are from 0.1 to 50 MeV photons and electrons. 3 This guide should be used along with standard practices and guides for specific dosimetry systems and applications covered in other standards. 4 Dosimetry for radiation processing with neutrons or heavy charged particles is not covered in this guide. 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.

Guide for selection and calibration of dosimetry systems for radiation processing

ISO/ASTM 51205:2002 硫酸铈和硫酸高铈剂量测定系统的使用规程

1 This practice covers the preparation, testing, and proce-dure for using the ceric-cerous sulfate 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 system will be referred to as the ceric-cerous system. It is classified as a reference standard dosimetry system (see ISO/ASTM Guide 51261). Ceric-cerous dosimeters are also used as transfer-stan-dard dosimeters or routine dosimeters. 2 This practice describes both the spectrophotometric and the potentiometric readout procedures for the ceric-cerous systems. 3 This practice applies only to γ rays, X rays, and high energy electrons. 4 This practice applies provided the following are satis-fied: 4.1 The absorbed-dose range shall be between 5 × 10 and 5 × 10 Gy (1). 4.2 The absorbed-dose rate shall be less than 10 Gy/s (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 are appropriate for a cylindrical dosimeter ampoule of 12-mm diameter. Corrections for dose gradients across an ampoule of that diameter or less are not required for photons, but may be required for electron beams (2). The ceric-cerous 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 between 0 and 62℃ (3). Note 2—The temperature coefficient of dosimeter response is known only in this range. For use outside this range, the dosimetry system should be calibrated for the required range of irradiation temperatures. 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. note: 2 The boldface numbers in parenthese refer to the bibliography at the end of this standard.

Practice for use of a ceric-cerous sulfate dosimetry system

ISO 10155:1995/cor 1:2002 固定源辐射.自动监测粒子的质量浓度.性能特性、实验方法和规范、技术勘误1

This is Technical Corrigendum 1 to ISO 10155-1995 (Stationary source emissions — Automated monitoring of mass concentrations of particles — Performance characteristics, test methods and specifications )

Stationary source emissions - Automated monitoring of mass concentrations of particles - Performance characteristics, test methods and specifications; Technical Corrigendum 1

ASTM E720-02 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

ISO 14152:2001 中子辐射保护屏蔽 设计原则和选择适用材料的考虑

This International Standard presents the general methodology governing the design of neutron radiation protection shielding and the choice of neutron radiation protection shielding materials. This International Standard is applicable to facilities and operations where neutron sources are located and used, and where workers are occupationally exposed. These operations and facilities vary considerably in design and purpose. These facilities and operations include, but are not limited to: — nuclear power plants; — research reactors; — particle accelerators and neutron generators; — fusion research facilities; — transportation packaging for radioactive materials operations; — medical treatment and research facilities and applications; — industrial applications such as use of devices for measuring and detecting moisture and density level; — space applications; — calibration facilities; — radiographic installations; — nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste storage, etc.). The criteria for the design of neutron shielding and the choice of shielding materials contained in this International Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.

Neutron radiation protection shielding - Design principles and considerations for the choice of appropriate materials

BS ISO 8529-2:2000 标准中子辐射.与表征辐射场基本量有关的辐射保护仪表的校准原则

This part of ISO 8529 takes as its starting point the neutron sources described in ISO 8529-1. It specifies the procedures to be used for realizing the calibration conditions of radiation protection devices in neutron fields produced by these calibration sources, with particular emphasis on the corrections for extraneous effects (e.g., the neutrons scattered from the walls of the calibration room). In this part of ISO 8529, particular emphasis is placed on calibrations using radionuclide sources (clauses 4 to 6) due to their widespread application, with less details given on the use of accelerator and reactor sources (8.2 and 8.3). This part of ISO 8529 then leads to ISO 8529-3 which gives conversion coefficients and the general rules and procedures for calibration.

Reference neutron radiations - Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field

ASME SEC XI D3 MA APP I-2001 附录I.测漏仪的校正

Boiler and Pressure Vessels.Appendix I Calibration of Leak Detectors

Appendix I Calibration of Leak Detectors

IEC 61584:2001 辐射防护仪器 空气比释动能方向与空气比释动能率的测量

1 This International Standard is applicable to installed, portable or transportable assemblies intended to measure - the direction of an X or gamma radiation source in terms of azimuth and elevation angles, as shown in the schema of figure 1; - the X or gamma air kerma rate at the equipment location; - the attenuation coefficient in a given medium and the related effective energy of the X or gamma beam incident to the equipment location. The energy range of X or gamma radiation is at least between 50 keV and 1,5 MeV. 2 The assemblies considered in this standard comprise at least - a detection sub-assembly which could include several detectors; - a measuring sub-assembly including a display device, which may be connected together or incorporated into a single assembly or interfaced. This sub-assembly could contain a microprocessor equipped with an algorithm to process the measured data. 3 This standard is applicable to measuring assemblies designed for special applications: e.g. high air kerma rate measurements and direction of the plume following a nuclear accident or, when mounted on a vehicle, to guide it towards the X or gamma sources and to bring it closer to the intervention place. 4 National regulation or practice may require the measurement of other quantities than air kerma rate (e.g. ambient dose equivalent rate, other dose rate or exposure rate). This standard may be applied to performance characteristics of equipment to measure any such quantity. For example, the numerical values given for the radiation characteristics apply to any case but the conventionally true values would be expressed in the appropriate quantity. 5 This publication specifies general characteristics, general test procedures, electrical, safety and environmental characteristics and the identification certificate for assemblies defined in this clause. 6 This standard does not apply to thermoluminescence dosimetry systems or other passive integrating devices. 7 This standard does not provide specifications for measurements of beta radiation and neutrons. 8 This standard is not applicable to the operating characteristics of indicating or recording equipments as such (e.g. indicating meters, recorders, alarms etc.). The characteristics of such equipment should be in conformity with the general requirements appropriate to them.

Radiation protection instrumentation - Installed, portable or transportable assemblies - Measurement of air kerma direction and air kerma rate

IEC 61563:2001 辐射防护仪器 测量粮食中γ-辐射放射性核素的比活度用的设备

This International Standard applies to portable instruments used for measuring the specific or volumic activity of gamma-emitting radionuclides in food/foodstuffs intended for operation under field conditions, particularly in case of a post-accidental situation. It does not apply to low background laboratory instrumentation requiring highly skilled personnel. The instruments designed for measurement of gamma 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 the gamma emitting surface contamination and other radiation measurements as well, but these applications are 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 estimate specific gamma activity for a wide variety of samples according to this standard.

Radiation protection instrumentation - Equipment for measuring specific activity of gamma-emitting radionuclides in foodstuffs