F84 辐射防护仪器 标准查询与下载

DIN IEC 61453:2008 核仪器.放射性核素分析用闪烁γ射线探测器系统.校准和功能检验

Nuclear Instrumentation - Scintillation gamma ray detector systems for the assay of radionuclides - Calibration and functional checks (IEC 61453:2007)

DIN EN 62022:2008 由车辆运输的可再利用或不可再利用材料中γ辐射的控制和检测用已装好的监测器

Installed monitors for the control and detection of gamma radiations contained in recyclable or non-recyclable materials transported by vehicles (IEC 62022:2004, modified); German version EN 62022:2007

IEEE/ANSI N42.46-2008 货物和车辆安检用X射线和γ射线的成像性能测定的美国国家标准

American National Standard for Determination of the Imaging Performance of X-Ray and Gamma-Ray Systems for Cargo and Vehicle Security Screening

ASTM E1893-08a 为确保退役(退出使用)进行现场辐射评定所采用的便携式辐射测量仪的选择和使用标准指南

The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use. Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities. Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area.1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning. 1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control. 1.3 This standard is applicable to the in situ measurement of radioactive emissions that include: 1.3.1 alpha 1.3.2 beta (electrons) 1.3.3 gamma 1.3.4 characteristic x-rays 1.3.5 The measurement of neutron emissions is not included as part of this standard. 1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors. 1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents. 1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments to Support Unrestricted Release from Further Regulatory Controls

IEEE/ANSI N42.44-2008 关卡秘密X射线成像保安系统性能用美国国家标准

American National Standard for the Performance of Checkpoint Cabinet X-Ray Imaging Security Systems

IEEE/ANSI N42.48-2008 国家安全用光谱个人辐射探测器(SPRDs)性能要求的美国国家标准

American National Standard Performance Requirements for Spectroscopic Personal Radiation Detectors (SPRDs) for Homeland Security

DIN EN 60405:2007 核仪器.放射性测量仪表的结构要求和分类

Nuclear instrumentation - Constructional requirements and classification of radiometric gauges (IEC 60405:2003, modified); German version EN 60405:2007

DIN IEC 60671:2007 核电站.对安全性重要的仪器和控制系统.监督测试

Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing (IEC 60671:2007)

DIN IEC 60412:2007 核检测仪器装置.闪烁探测器.术语(鉴定).闪烁器的标准尺寸

Nuclear instrumentation - Scintillation detectors - Nomenclature (identification) - Standard dimensions of scintillators (IEC 60412:2007)

BS IEC 62342:2007 核电站.对安全性重要的仪器装置和控制系统.老化管理

1.1 Management of physical ageing This International Standard provides strategies, technical requirements, and recommendations for the management of ageing of nuclear power plant (NPP) instrumentation and control (I&C) systems and associated equipment. The standard also includes informative annexes on test methods, procedures, and technologies that may be used to verify proper operation of I&C equipment and aim to prevent ageing degradation from having any adverse impact on the plant safety, efficiency, or reliability. The standard applies to all types of NPPs and relates primarily to safety. 1.2 Management of technology ageing (obsolescence) The scope of this standard has been intentionally focused on the management of physical ageing of I&C systems where this may be considered as having a direct consequence on the safety of the NPP. It does not cover technology ageing aspects (i.e., obsolescence) in any detail. It should be noted, however, that, in practice, the overall scheme for the management of ageing will have to cover obsolescence. Indeed, obsolescence has been recognized as the dominant issue in the life cycle of many I&C technologies (from design through to operational maintenance, replacement, and updating). 1.3 Safety goal of this standard This standard identifies minimum requirements aimed at ensuring that any potential impacts on NPP safety due to I&C ageing can be identified and that suitable actions are undertaken to demonstrate that the safety of the plant will not be impaired.

Nuclear power plants - Instrumentation and control systems important to safety - Management of ageing

BS EN 60405:2007 核监测仪表.放射性测量仪表的装配要求和分类

This International Standard applies to the manufacture and installation of electrical measuring systems and instruments utilizing radioactive sources (radiometric gauges, hereinafter called gauges). It does not apply to portable gauges which, because of their construction and purposes for use, are intended to be operated as mobile equipment and it does not apply to gauges operated with X-ray tubes, but it can be analogously applicable to these gauges. The purpose of this standard is to specify constructional requirements for the design of instruments and the radiation protection to be provided in the case of radiometric gauges. In this conte x t , special attention may be attached to the stability of the source housing in the event of fire

Nuclear instrumentation - Constructional requirements and classification of radiometric gauges

ANSI/IEEE 497:2002/Cor1:2007 核电站用事故监测仪的标准判据.技术勘误1:2005年用户反馈意见合集

ANSI/IEEE 497-2003 provides an approach to designing accident monitoring systems for nuclear power plants. The corrigendum incorporates user feedback in order to improve the usefulness of the standard.

Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations - Corrigendum 1: Incorporation of User Feedback through 2005

IEC 62302:2007 辐射防护仪器.放射性惰性气体的取样和监测用设备

This International Standard is applicable to equipment used for sampling and continuous measurement of radioactive noble gases in the workplace，in gaseous effluents discharged into the environment as well as in the environment itself．Monitoring by definition is the process of continuous and real-time measurement．The processes of sampling or taking samples for retrospective laboratory analysis are included in this standard． The object of this standard is to establish mandatory general requirements and to present examples of acceptable methods and equipment for sampling and monitoring radioactive noble gases．Current standard IEC 60761-3 which is complemented by this standard，is applicable to installing portable and transportable equipment for sampling and monitoring radioactive noble gases，ONLY IN GASEOUS EFFLUENTS，while this standard expands coverage to include monitoring all possible locations where radioactive noble gases could present a radiological hazard．The equipment is designed to be operational during normal operation conditions as well as under emergency conditions,both during and following an accident．Depending on the nature of the emergency conditions it may be necessary to install specially designed equipment for normal operational conditions and other equipment for emergency conditions． This standard is applicable to radioactive noble gas samplers and monitors intended to provide the following functions： —·The measurement of the volumetric activity of radioactive noble gases and their variation with time in the workplace，in gaseous effluents at the discharge point and in the environment． 一The measurements performed during normal operational conditions as well as under emergency conditions during and after an accidental release． 一The actuation of an alarm when a predetermined volumetric activity，or concentration，or a predetermined total of released radioactivity is exceeded． —-The determination of the total gaseous activity discharged over a given time and/or to provide information on the composition of a mixture of different gases released —The sampling and retrospective analysis of air or gas containing noble gas． Radon，with isotopes 219Rn，220Rn，and 222Rn，is a naturally occurring radioactive noble gas whose measurements are NOT considered in this standard．The presence of radon and its progeny may sig n ificantly interfere with the proper measurement of the noble gases of concern in this standard． This standard specifies the general characteristics，general testing procedures，mechanical， electrical and electronic，radiological，safety and environmental characteristics，and the proper identification and certification of the equipment．If this equipment is part of a centralized system for continuous radiation monitoring in a nuclear facility，there may be additional requirements from other standards related to those systems．

Radiation protection instrumentation - Equipment for sampling and monitoring radioactive noble gases

BS EN 61098:2007 辐射防护仪器.固定式个人表面污染监测装置

This International Standard applies to contamination warning assemblies and monitors used for the monitoring of radioactive contamination on the surface of personnel whether they be clothed or not~. The standard is applicable only to that type of equipment where the user takes no action other than to present himself and/or his hands and feet to the detectors. It is not applicable to equipment where the user or someone else moves detectors over the area to be monitored or the user passes quickly through the monitor. It is also not applicable to any peripheral equipment which may be associated with a particular type of equipment such as small article monitors. This standard is applicable to the monitoring of the whole body (including the head), hands and feet but parts of this standard may be used for equipment designed for the monitoring of radioactive contamination on the hands and/or feet only. This standard is applicable to: – installed personnel monitoring equipment (all Clauses applicable); – equipment for monitoring the hands (see the following Clauses and Subclauses: 2, 3, 4, 5, 6, 7.1.2, 7.2, 7.3.2, 7.4.1.2 b), 7.4.2, 7.4.3.1, 7.4.3.2, 7.4.3.3 b), 7.5, 7.6, 7.7, 8, 9, 10, 11 and 12); – equipment for monitoring the feet (see the following Clauses and Subclauses: 2, 3, 4, 5, 6, 7.1.3, 7.2, 7.3.3, 7.4.1.2 c), 7.4.2, 7.4.3.1, 7.4.3.2, 7.4.3.3 c), 7.5, 7.6, 7.7, 8, 9, 10, 11, 12 and 13); – equipment for monitoring the hands and feet (see the following Clauses and Subclauses 2, 3, 4, 5, 6, 7.1.2, 7.1.3, 7.2, 7.3.2, 7.3.3, 7.4.1.2 b), 7.4.1.2 c), 7.4.2, 7.4.3.1, 7.4.3.2, 7.4.3.3 b), 7.4.3.3 c), 7.5, 7.6, 7.7, 8, 9, 10, 11 and 12).

Radiation protection instrumentation - Installed personnel surface contamination monitoring assemblies

BS EN 62022:2007 由车辆运输的可循环利用或不可循环利用材料中γ辐射的控制和检测用已安装的监测器

This International Standard is applicable to installed monitors for the control and detection of radioactivity of gamma emitters contained in recyclable or non-recyclable material waste to be transported by vehicles. This standard is designed to provide the purchaser with an indication of the performance of the equipment in detecting radioactive sources left in the material being monitored, and not to measure quantity. This standard does not apply to hand-held equipment. It is not applicable to the monitoring of materials on conveyors, in grabs or being moved by electromagnets. This standard is not intended for the monitoring of radioactive waste or detection of fissile materials. The object of this standard is to define an installed monitor for the control and detection of radioactivity of gamma emitters contained in recyclable or non-recyclable materials transported by vehicle, the conceptual requirements, general characteristics, mechanical characteristics, environmental conditions, minimal requirements, test procedures and documentation. The selection of the location of the instrumentation on the site needs to be optimised to achieve the best performance of measurement, but this is beyond the scope of this standard. The gamma radiation detected by these monitors may be emitted by one or several discrete radioactive sources included in the loading, or by the presence of radioactive material in the vehicle being monitored. These monitors are to be used outdoors. The radiations detected are gamma emissions of energy at least from 50 keV to 1 500 keV. It is advantageous if the equipment can give the approximate location of a radioactive source but this is not a mandatory requirement of this standard. Conformance with the requirements of this standard is no guarantee that a radioactive source will always be discovered. The shielding of the high-density materials will mean radioactive substances buried deep in the material could be missed.

Installed monitors for the control and detection of gamma radiations contained in recyclable or non-recyclable materials transported by vehicles

BS IEC 62401:2007 辐射防护仪器装置.放射性材料违禁运输监测用人体辐射报警器(PRD)

This International Standard applies to alarming radiation detection instruments that are pocket-sized, carried on the body and used to detect and indicate the presence and general magnitude of penetrating ionizing radiation, including photons and/or neutrons. Personal Radiation Devices (PRD) alert the user to the presence of a source of radiation that is distinctly above the measure average local background radiation level. They are not intended to provide a measurement of dose equivalent rate.

Radiation protection instrumentation - Alarming personal radiation devices (PRD) for detection of illicit trafficking of radioactive material

DIN EN 61526:2007 辐射防护仪器装置.X、γ、中子和β射线辐射个人剂量当量H_p(10)和H_p(0.07)的测量.直读式个人剂量当量计和监控器(IEC 61526-2005的修正版)

Radiation protection instrumentation - Measurement of personal dose equivalents H_p(10) and H_p(0,07) for X, gamma, neutron and beta radiations - Direct reading personal dose equivalent meters and monitors (IEC 61526:2005, modified); Germa

IEC 62342:2007 核电站.对安全性重要的仪器仪表和控制系统.老化管理

1.1 Management of physical ageing This International Standard provides strategies, technical requirements, and recommendations for the management of ageing of nuclear power plant (NPP) instrumentation and control (I&C) systems and associated equipment. The standard also includes informative annexes on test methods, procedures, and technologies that may be used to verify proper operation of I&C equipment and aim to prevent ageing degradation from having any adverse impact on the plant safety, efficiency, or reliability. The standard applies to all types of NPPs and relates primarily to safety. 1.2 Management of technology ageing (obsolescence) The scope of this standard has been intentionally focused on the management of physical ageing of I&C systems where this may be considered as having a direct consequence on the safety of the NPP. It does not cover technology ageing aspects (i.e., obsolescence) in any detail. It should be noted, however, that, in practice, the overall scheme for the management of ageing will have to cover obsolescence. Indeed, obsolescence has been recognized as the dominant issue in the life cycle of many I&C technologies (from design through to operational maintenance, replacement, and updating). 1.3 Safety goal of this standard This standard identifies minimum requirements aimed at ensuring that any potential impacts on NPP safety due to I&C ageing can be identified and that suitable actions are undertaken to demonstrate that the safety of the plant will not be impaired.

Nuclear power plants - Instrumentation and control systems important to safety - Management of ageing

DIN IEC 60880:2007 核电站.对安全重要的仪器和控制系统.表现A类功能的基于计算机系统的软件问题(IEC 60880-2006)

Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions (IEC 60880:2006)

IEC 61453:2007 核检测仪表.放射性核素分析用闪烁γ射线探测器系统.校准和常规试验

This International Standard specifies methods of calibration and routine tests of scintillation detector systems for the measurement of gamma-ray energies and emission rates of radionuclides and the assay of radioactivity. This International Standard is applicable to scintillation detector systems based on inorganic scintillators for photon measurements. Typical applications include radionuclide identification and assay in various industrial, environmental, and medical applications. The detector system consists of three major components: a scintillating material that produces photons of light when ionizing radiation interacts with it; one or more photomultipliers or photodiodes, optically coupled to the scintillator, which convert the light photons to an amplified electrical pulse or pulses; and associated electronic instrumentation which powers the photomultiplier and processes the output signal. Both energy calibration and efficiency calibration are covered. The following three techniques are considered: a) total spectrum counting (see 3.1) which employs a system that counts all pulses above a low-energy threshold (see 5.1, 5.2 and 5.3); b) single-channel analyzer (SCA) counting (see 3.2) which employs a system with a counting channel established through upper and lower energy boundaries (see 5.1, 5.2, and 5.3); c) multichannel analyzer counting (see 3.3) which employs a system in which multiple counting windows are utilized. This technique allows measurements for which the continuum under the total absorption peak may be subtracted without introducing unacceptable error. In case of overlapping peaks in the spectrum, a multichannel analyzer (MCA) with access to a peak deconvolution program is necessary. This case is not covered by this standard.

Nuclear instrumentation - Scintillation gamma ray detector systems for the assay of radionuclides - Calibration and routine tests