F84 辐射防护仪器 标准查询与下载

DIN EN 60846:2005 辐射防护仪.β、X和γ辐射的环境和(或)定向剂量当量(率)测量仪和(或)监测仪

Radiation protection instrumentation - Ambient and/or directional dose equivalent (rate) meters and/or monitors for beta, X and gamma radiation (IEC 60846:2002, modified); German version EN 60846:2004

DIN EN 61005:2005 辐射防护仪.中子环境剂量当量(率)测量仪

Radiation protection instrumentation - Neutron ambient dose equivalent (rate) meters (IEC 61005:2003, modified); German version EN 61005:2004

KS C IEC 60710:2005 测量和监视空气中氚的辐射防护设备

이 규격은 공기 중 삼중 수소의 측정과 모니터링을 위한 장치에 적용된다. 그러한 장치에는

Radiation protection equipment for the measuring and monitoring of airborne tritium

KS C IEC 60761-2:2005 气态排出流放射性连续监视设备.第2部分:包括铀后气溶胶的放射性气溶胶监视设备的特殊要求

이 규격은 환경으로 방출되는 기체 유출액 속의 에어로졸을 동시, 지연 또는 불연속 순차적(

Equipment for continous monitoring of radioactivity in gaseous effluents－Part 2：Specific requirements for radioactive aerosol monitors including transuranic aerosols

KS C IEC 60761-3:2005 气态排出流放射性连续监视设备.第3部分:惰性气体排出流监视仪的特殊要求

이 규격은 주위 환경으로 방출되는 기체 유출액 속의 방사성 희가스를 동시, 지연 또는 불연

Equipment for continous monitoring of radioactivity in gaseous effluents－Part 3：Specific requirements for radioactive noble gas monitors

NF C19-101:2005 辐射防护仪.中子环境剂量当量率计

Radiation protection instrumentation - Neutron ambient dose equivalent (rate) meters.

NF C19-102:2005 辐射防护仪.β、X和γ辐射的环境和/或定向剂量当量(率)测量仪和(或)监测仪

Radiation protection instrumentation - Ambient and/or directional dose equivalent (rate) meters and/or monitors for beta, X and gamma radiation.

ASTM ISO/ASTM 51539-05(2013) 辐射敏感指示计使用的标准指南

4.1 Indicators may be used to show that products have been exposed to a radiation source. They should be used only to provide a qualitative indication of radiation exposure and may be used to distinguish processed loads that have been irradiated from unirradiated process loads.NOTE 1桾he use of indicators does not eliminate the need for other process-control procedures, such as quantitative dosimetry or the controlled segregation of irradiated from nonirradiated products.NOTE 2桽ee ISO/ASTM Standards 51204, 51431, 51608, 51649, 51702, 51939, and 51940 for information on the use of indicators in the various types of processing facilities and for unique product applications.4.2 The indicator manufacturer is obliged to supply a statement regarding the approximate dose level at which the examiner (20/20 vision), at standard illumination (unfiltered daylight, or artificial light of the spectrum and intensity defined by the proper ASTM standard), is able to determine the visual change in the indicator.1.1 This guide covers procedures for using radiationsensitive indicators (referred to hereafter as indicators) in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation (1-5).21.2 The purpose for using indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels.1.3 Indicators are not dosimeters and shall not be used as a substitute for proper dosimetry. Information about dosimetry systems for radiation processing is provided in other ASTM and ISO/ASTM documents (see ISO/ASTM Guide 51261).1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Use of Radiation-Sensitive Indicators

ASTM ISO/ASTM 51539-05 辐射敏感指示器使用的标准指南

4.1 Indicators may be used to show that products have been exposed to a radiation source. They should be used only to provide a qualitative indication of radiation exposure and may be used to distinguish processed loads that have been irradiated from unirradiated process loads.NOTE 1 - The use of indicators does not eliminate the need for other process-control procedures, such as quantitative dosimetry or the controlled segregation of irradiated from nonirradiated products. NOTE 2 - See ISO/ASTM Standards 51204, 51431, 51608, 51649, 51702, 51939, and 51940 for information on the use of indicators in the various types of processing facilities and for unique product applications. 4.2 The indicator manufacturer is obliged to supply a statement regarding the approximate dose level at which the examiner (20/20 vision), at standard illumination (unfiltered daylight, or artificial light of the spectrum and intensity defined by the proper ASTM standard), is able to determine the visual change in the indicator.1.1 This guide covers procedures for using radiation-sensitive indicators (referred to hereafter as indicators) in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation 1-5).1.2 The purpose for using indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels.1.3 Indicators are not dosimeters and shall not be used as a substitute for proper dosimetry. Information about dosimetry systems for radiation processing is provided in other ASTM and ISO/ASTM documents (see ISO/ASTM Guide 51261).1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Use of Radiation-Sensitive Indicators

BS EN 61005:2004 辐射防护测量仪.中子环境剂量当量(率)计

This International Standard is applicable to all assemblies designed to measure the ambient dose equivalent (rate) due to neutron radiation of energy up to 16 MeV, and which comprise at least: a) a detection assembly, which may, for example, consist of a detector probe for thermalised neutrons and an arrangement of moderating and absorbing media surrounding the detector; b) a measuring assembly with a display for the measuring result, which may be incorporated into a single assembly or connected by means of a flexible cable. NOTE Z If the Equipment consists of separate detector and measurement assemblies the cable between the two shall be that specified by the manufacturer. If the connection is by other means (e.g. radio waves, infrared) or other cables, it is necessary to apply additional requirements with respect to the specific media. The requirements given below pertain to assemblies as defined in the first paragraph. It is acceptable, however, to use assemblies, which do not meet the requirements below when such requirements are not deemed essential for a given purpose. In such cases, the requirements to be applied to the assemblies should be specified by agreement between the manufacturer and the purchaser, but the methods of determination of the characteristics of the assemblies should conform to this standard. No tests are specified in this standard for the performance requirements of the assemblies in pulsed radiation fields, and it is to be considered that an assembly designed to meet this standard may not be suitable for use in such fields. The object of this standard is to specify requirements for the performance characteristics of neutron ambient dose equivalent (rate) meters, and to prescribe the methods of testing in order to determine compliance with this standard. This standard specifies, for the assemblies described in the first paragraph, general characteristics, general test procedures, radiation characteristics, electrical, mechanical, safety and environmental characteristics, and also the identification certificate. Requirements and test procedures are also specified for the alarm performance of the dose equivalent (rate) meters, which are equipped with alarm provisions. NOTE Dose equivalent (rate) meters for neutrons have an energy dependence of ambient dose equivalent response, which may deviate considerably from unity. The response in realistic spectra encountered in workplace fields is such that the deviations in different energy ranges tend to neutralise each other. Consequently, the response in realistic fields is generally much closer to unity. ISO 12789 specifies a list of appropriate neutron sources having broad spectra suitable for the testing of such (rate) meters. Also work places may be specified by agreement between manufacturer and purchaser to be appropriate for testing when the spectral environment is well defined. Unconventional dose equivalent ratemeters, for example consisting of more than one detector probe, have recently become available. For such instruments, evaluation based on mono-energetic neutrons is not relevant. Also for those ratemeters, the above considerations may apply.

Radiation protection instrumentation. Neutron ambient dose equivalent (rate) meters

BS EN 60325:2004 辐射防护仪.α,和α/β(β能量为60 keV)污染测量仪和监测仪

This International Standard is applicable to radiation meters and monitors designed for the direct measurement or the direct detection of surface contamination by alpha and/or beta radiation emitting nuclides and which comprise at least: - a detection assembly (comprising text deleted counter tube, scintillation detector or semiconductor detector, etc), which may be connected either rigidly or by means of a flexible cable or incorporated into a single assembly. - a measurement assembly. Some meters and monitors consist of detection assemblies and measurement assemblies where it is possible to separate the detector assembly and use alternative detection assemblies. Conformity with the standard can either be achieved by: All combinations of the detection assembly and the measurement assembly conforming to the requirements of this standard. or The detection assembly and the measurement assembly separately conforming to the relevant parts of this standard in isolation. NOTE The use of the latter criteria verifies conformance with this standard but does not infer that calibration of a particular combination of instruments is interchangeable with any other combination. The use of the latter criteria could allow a purchaser to use combinations of assemblies from different manufacturers with confidence. The standard is applicable to: - alpha surface contamination meters; - alpha surface contamination monitors; - beta surface contamination meters; - beta surface contamination monitors; - alpha/beta surface contamination meters; - alpha/beta surface contamination monitors. The latter two are equipment capable of determining alpha and beta contamination simultaneously and displaying the measurement of either: - Alpha (beta, alpha/beta) surface contamination meter An assembly including one or more radiation detectors and associated assemblies or basic function units, designed to measure alpha (beta, alpha/beta) surface emission rate associated with the contamination of the surface under examination. - Alpha (beta, alpha/beta) surface contamination monitor. This standard is also applicable to special purpose assemblies and to assemblies specifically designed for a surface of a particular nature. However, some of the requirements may need to be amended or supplemented according to the particular requirements applicable to such assemblies. If an assembly has been designed to carry out combined functions, it must comply with the requirements pertaining to these different functions. If, on the other hand, it has been designed to perform one function, and, in addition, it is also capable of carrying out other functions, then it must comply with the requirements for the first function, and it would be desirable for it to comply with requirements pertaining to the others. This standard is not applicable to radiation monitors or meters designed to measure or detect beta particles with Emax < 60 keV. The object of this standard is to lay down standard requirements and to give examples of acceptable methods, and also to specify general characteristics, general test conditions, radiation characteristics, electrical safety, environmental characteristics, and the requirements of the identification certificate for alpha, beta and alpha-beta contamination meters and monitors.

Radiation protection instrumentation. Alpha, beta and alpha/beta (beta energy 60 keV) contamination meters and monitors

DIN 6818-1:2004 射线防护剂量计.第1部分:一般规则

The standard contains terms and definitions regarding to dosimeters, and additional determining factors and error-sources, that might influence the measurement. Further x-ray qualities and requirements for adjustment and calibration of dosimeters are included.

Radiation protection dosimeters - Part 1: General

IEEE N323A/COR-2004 辐射防护仪器的试验和校准,便携式调查仪器

Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments

JIS Z 4329:2004 便携式放射性表面污染剂量器和监测仪

この規格は，物体表面上のα線放出核種，又は最大エネルギー60 keV以上のβ線を放出するβ線放出核種による汚染密度を測定する放射性表面汚染サーべイメータ又は警報付き放射性表面汚染サーべイメータ(以下サーべイメータという。)について規定する。

Portable radiation surface contamination meters and monitors

IEC 61582:2004 辐射防护测量仪表.体内计数管.便携式、可运输和已安装设备的分类、一般要求和试验过程

Specifies the classification, general design requirements, performance characteristics and test procedures for in vivo counting systems for detecting trace amounts of radionuclides in the bodies of persons working in nuclear power plants, laboratories an

Radiation protection instrumentation - In vivo counters - Classification, general requirements and test procedures for portable, transportable and installed equipment

ASTM ISO/ASTM 51275-04 放射性铬胶片剂量测量系统的标准方法

4.1 The radiochromic film dosimetry system provides a means of determining absorbed dose in materials. Under the influence of ionizing radiation, chemical reactions take place in the radiochromic film creating or enhancing, or both, optical absorption bands. Absorbance is determined within these radiation-induced absorption bands using a spectrophotometer or photometer (See 5.1.2).4.2 In the application of a specific dosimetry system, absorbed dose is determined by use of a calibration curve traceable to national or international standards.4.3 The absorbed dose determined is usually specified in water. Absorbed dose in other materials may be determined by applying conversion factors. This is discussed in ISO/ASTM Guide 51261.NOTE 1 - For comprehensive discussion of various dosimetry methods applicable to the radiation types and energies discussed in this practice, see ICRU Reports 14, 17, 34, and 35.1.1 This practice covers the procedures for handling, testing, 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.1.2 This practice applies to radiochromic film dosimeters that can be used within part or all of the specified ranges as follows:1.2.1 The absorbed dose range is 1 Gy to 100 kGy.1.2.2 The absorbed dose rate is 1 x 10-2 to 1 x 1013 Gy/s (1-4).1.2.3 The radiation energy range for both photons and electrons is 0.1 to 50 MeV.1.2.4 The irradiation temperature range is -78 to +60176;C.1.3 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 placement of any of these formats.1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Use of a Radiochromic Film Dosimetry System

IEEE/ANSI N42.18-2004 连续监测废水放射性用现场仪器的美国国家标准化规范和性能

American National Standard Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents

KS A IEC 60579:2003 放射性气雾剂污染计监控器

1.1 이 규격은 다음에 적용된다.-방사성 에어로졸 오염계-방사성 에어로졸 오염 감

Radioactive aerosol contamination meters and monitors

KS A IEC 60532:2003 辐射防护检测设备.安装型剂量计、警报装置和监控器.能量范围50keV∼7MeV的X和γ线

이 규격은 1.4에서 정의한 설치형 선량률계, 경고 장치 및 감시기에 적용된다.이

Radiation protection instrumentation-Installed dose ratemeters, warning assemblies and monitors-X and gamma radiation of energy between 50 keV and 7 MeV

KS A IEC 61525:2003 辐射防护仪器.X.γ、高能β和中子辐射直读式个人剂量当量和/或剂量当量率监测仪

이 규격의 목적은 강한 투과성 방사선의 개인 선량 당량 또는 개인 선량 당량률 측정에

Radiation protection instrumentation-X, gamma, high energy beta and neutron radiations-Direct reading personal dose equivalent and/or dose equivalent rate monitors