F84 辐射防护仪器 标准查询与下载

DIN 25457-6:2000 放射性废料和核技术设备部件的释放放射性强度测量方法.第6部分:建筑物橡胶和建筑物

The document is intended to apply to the release of rubble and buildings in the case of changes or decommissioning of nuclear plants. It is also intended to apply to the release of contaminated on activated buildings which are provided either to be pulled down or to be used later in case of harmless reuse beyond an atomic authorisation. The document can also be used in case of mass specific release of loose goods in case of special rlease criteria.

Activity measurement methods for the release of radioactive waste materials and nuclear facility components - Part 6: Building rubble and buildings

BS ISO 12794:2000 核能.辐射防护.肢端和眼用单独热致发光剂量计

To be read in conjunction with IEC 1066:1991

Nuclear energy. Radiation protection. Individual thermoluminescence dosemeters for extremities and eyes

NAVY MIL-I-85832 NOTICE 1-1999 直升机飞行员内部通信化学,生物,辐射防护设备

This notice should be filed in front of MIL-I-85832(AS) dated 6 November 1989.

INTERCOM, HELICOPTER AIRCREWMAN, CHEMICAL, BIOLOGICAL, RADIOLOGICAL PROTECTIVE SET

NF M60-303:1999 核能.核燃料技术－废料.用伽码射线能谱测定法对放射性废料形态的放射性活度测量设施校准的推荐规范

Nuclear energy. Nuclear fuel technology-Waste. Recommendations for the calibrating of an activity measurement facility of radioactive waste forms by gamma spectrometry.

JIS Z 4511:1999 照射量计和剂量当量计的校准方法

Methods of calibration for exposure meters and dose-equivalent meters

IEEE 309-1999 盖革-弥勒计数器试验规程和基础

Test procedures for the Geiger-Mueller counters that are used for the detection of ionizing radiation are presented so that they have the same meaning to both manufacturers and users. Also included is information on bases (i.e., connections) for the counters.

Standard Test Procedures and Basis for Geiger-Mueller Counters ANSI N42.3:1999

ASTM C1112-99 特种核材料的控制和物理安全用辐射监控器的应用

1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrate, and maintain them. Effective operation also requires training in the use of monitors for the security inspectors who attend them. Training is particularly important for hand-held monitoring where the inspector plays an important role in the search by scanning the instrument over pedestrians and packages or throughout a motor vehicle. 1.3 SNM radiation monitors are commercially available in three forms: 1.3.1 Small Hand-Held Monitors- These monitors may be used by an inspector to manually search pedestrians and vehicles that stop for inspection. 1.3.2 Automatic Pedestrian Monitors -These monitors are doorway or portal monitors that search pedestrians in motion as they pass between radiation detectors, or wait-in monitoring booths that make extended measurements to search pedestrians while they stop to obtain exit clearance. 1.3.3 Automatic Vehicle Monitors -These monitors are portals that monitor vehicles as they pass between radiation detectors, or vehicle monitoring stations that make extended measurements to search vehicles while they stop to obtain exit clearance. 1.4 Guidance for applying SNM monitors is available as Atomic Energy Commission/Nuclear Regulatory Commission (AEC/NRC) regulatory guides, AEC/ERDA/DOE performance standards, and more recently as handbooks and applications guides published by national laboratories under DOE sponsorship. This broad information base covering the pertinent physics, engineering practice, and equipment available for monitoring has had no automatic mechanism for periodic review and revision. This ASTM series of guides and standards will consolidate the information in a form that is reexamined and updated on a fixed schedule. 1.5 Up-to-date information on monitoring allows both nuclear facilities and regulatory agencies to be aware of the current range of monitoring alternatives. Up-to-date information also allows manufacturers to be aware of the current goals of facilities and regulators, for example, to obtain particular sensitivities at a low nuisance alarm rate with instrumentation that is dependable and easy to maintain. 1.6 This guide updates and expands the scope of NRC regulatory guides and AEC/ERDA/DOE SNM monitor performance standards using the listed publications as a technical basis. 1.7 The values stated in SI units are to be regarded as the standard. 1.8 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety problems 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 Application of Radiation Monitors to the Control and Physical Security of Special Nuclear Material

IEEE/ANSI N42.14-1999 伽马射线辐射率的放射性核素含量测定用锗光谱仪校准和使用方法

Calibration and use of germanium spectrometers for the measurement of gammma-ray emission rates of radionuclides

IEEE/ANSI N42.27-1999 固态γ放射源不均匀性测定的美国国家标准

American National Standard for Determination of Uniformity of Solid Gamma-Emitting Flood Sources

ASTM C1112-99(2005) 特种核材料的控制和物理安全用辐射监控器的应用

SNM monitors are an efficient and sensitive means of unobtrusively (without a body search) meeting the requirements of 10 CFR (Code of Federal Regulations) Part 73 or DOE Order 5632.4 (May 1986) that individuals exiting nuclear material access areas (MAAs) be searched for concealed SNM. The monitors sense radiation emitted by SNM, which is an excellent but otherwise imperceptible clue to the presence of the material. Because the monitors operate in a natural radiation environment and must detect small intensity increases as clues, the monitors must be well designed and maintained to operate without unnecessary nuisance alarms. This guide provides information on different types of monitors for searching pedestrians and vehicles. Each monitor has an inherent sensitivity at a particular nuisance alarm rate that must be low enough to maintain the monitorrsquo;credibility. Sensitivity and nuisance alarm rates are both governed by the alarm threshold so it is very important that corresponding values for both be known when measured, estimated, or specified values are discussed. Fitting SNM monitors into a facility physical protection plan must not only consider adequate sensitivity but also a sufficiently low nuisance alarm rate.1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see ) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms.1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrate, and maintain them. Effective operation also requires training in the use of monitors for the security inspectors who attend them. Training is particularly important for hand-held monitoring where the inspector plays an important role in the search by scanning the instrument over pedestrians and packages or throughout a motor vehicle.1.3 SNM radiation monitors are commercially available in three forms:1.3.1 Small Hand-Held MonitorsThese monitors may be used by an inspector to manually search pedestrians and vehicles that stop for inspection.1.3.2 Automatic Pedestrian MonitorsThese monitors are doorway or portal monitors that search pedestrians in motion as they pass between radiation detectors, or wait-in monitoring booths that make extended measurements to search pedestrians while they stop to obtain exit clearance.1.3.3 Automatic Vehicle MonitorsThese monitors are portals that monitor vehicles as they pass between radiation detectors, or vehicle monitoring stations that make extended measurements to search vehicles while they stop to obtain exit clearance.1.4 Guidance for applying SNM monitors is available as Atomic Energy Commission/Nuclear Regulatory Commission (AEC/NRC) regulatory guides, AEC/ERDA/DOE performance standards, and more recently as handbooks and applications guides published by national laboratories under DOE sponsorship. This broad information base covering the pertinent physics, engineering practice, and equipment available for monitoring has had no automatic mechanism for periodic review and revision. This ASTM series of guides and standards will consolidate the information in a form t......

Standard Guide for Application of Radiation Monitors to the Control and Physical Security of Special Nuclear Material

EJ/T 1097-1999 用于核设施辐射及放射性活度连续监测的中央控制系统

Radiation in nuclear facilities - Centralized system for continuous monitoring of radiation and/or levels of radioactivity

NF M60-517-2:1998 表面污染监测仪校准的参考辐射源.第2部分:能量低于0.15MEV的电子和能量低于1.5MEV的光子

Reference sources for the calibration of surface contamination monitors. Part 2 : electrons of energy less than 0,15 MeV and photons of energy less than 1,5 MeV.

NF M60-522:1998 X射线和伽玛射线辐射.直接或非直接读数电容器芯子剂量仪

X and gamma radiation. Indirect- or direct-reading capacitor-type pocket dosemeters.

NF M60-512-1:1998 校准剂量计和剂量率计及测量作为光子能量作用反应用X射线和伽玛射线的参考辐射

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy. Part 1 : radiation characteristics and production methods.

EJ/T 1077-1998 用于辐射防护的空气中氚的测量和监测设备

Radiation protection equipment for the measuring and monitoring for airborne tritium

JIS Z 4324:1997 X、γ 射线区域监测仪

この規格は，原子力施設及び放射線利用施設の建屋内の作業環境における，X線及びγ線の1 cm線量当量率を連続的に監視するためのエリアモニタ(以下，モニタという。)について規定する。ただし，バルス状の放射線に使用するモニタには適用しない。

Area monitors for X and gamma rays

JIS Z 4338:1997 β发射体用员工身体表面受放射性污染监测的安装组件

Installed personnel surface contamination monitoring assemblies for beta emitters

IEC 61275:1997 辐射防护仪表 环境中放射性核素的测量 使用锗探测器的现场光子光谱测定系统

This International Standard is applicable to a portable or transportable photon spectrometry assembly using a germanium (Ge) detector to survey, in situ, generally at 1 m above ground level, areas in the environment for discrete radionuclides. Such equipment is used to make rapid assessments of activity levels and corresponding free air exposure rates from photon emitting radionuclides. Such measurements may be used to develop guidance for subsequent follow-on action, for example including radiological assessments, sampling and monitoring programmes. (This standard does not apply to airborne measurement systems, which are covered by a separate standard. See IEC 61134.) This standard specifies for such an assembly the general characteristics, test methods for the evaluation of radiation characteristics, electrical, mechanical, safety and environmental characteristics specific to the applications described above. Advice is also provided in annexes as to the calibration, appropriate use and interpretation of the system for in situ measurements. An in situ spectrometry system is a combination of instruments or subassemblies designed to measure, in situ, the flux of gamma rays incident on the detector, in order to rapidly survey areas for discrete radionuclides present in the soil or air, either natural or manmade. The purpose of this standard is to specify the performance characteristics of assemblies intended for the determination of surface soil activity. Accordingly, this standard a) specifies the functions and performance characteristics of measuring assemblies, and b) specifies the methods of test to be used to determine compliance with the requirements of this standard.

Radiation protection instrumentation - Measurement of discrete radionuclides in the environment - In situ photon spectrometry system using a germanium detector

JIS Z 4337:1997 β发射体用器件表面受放射性污染监测的安装组件

この規格は，最大エネルギー0.15 MeV以上のβ線を放出する核種による汚染を検出することによって，原子力施設等の管理区域から搬出する物品の表面汚染を測定する据置形β線用物品表面汚染モニタ(以下，モニタとしンう。)について規定する。

Installed articles surface contamination monitoring assemblies for beta emitters

IEEE N323A-1997 辐射防护仪器的试验和校准,便携式调查仪器

This standard establishes specific requirements for portable radiation protection instruments used for detection and measurement of levels of ionizing radiation fields or levels of radioactive surface contamination. For purposes of this standard, portable radiation protection instruments are those battery-powered instruments that are carried to a specific facility or location for use. NOTE--These instruments are normally held during operation. Count rate meters and sealers, when used with an appropriate probe for quantifying activity, can be considered portable radiation protection instruments and treated as a single unit for the purposes of this standard. Specific requirements for calibration of low-range [i.e., near background to 10µSv/h (1 mrem/h)]1 portable survey instruments will be detailed in ANSI N323B (currently under development). Specific requirements for all air monitoring instruments will be detailed in ANSI N323C (currently under development). Specific requirements for installed instruments that measure dose or dose equivalent, or dose rate or dose equivalent rate, and AC powered instruments used only to detect the presence of radioactive material contamination will be detailed in ANSI N323D (currently under development). Radiation protection instrumentation provides direct readout of, or readout proportional to, dose or dose equivalent, dose rate or dose equivalent rate, or activity per unit area (i.e., effective probe area). Included are portable rate and integrating devices for beta, photon, and neutron radiations; and monitors for surface contamination (alpha, beta, and photon). Portable radiation protection instruments intended for use in underwater survey and monitoring are included in this standard. Personnel dosimeters (including electronic pocket dosimeters and hybrid pocket dosimeters/dose equivalent rate meters) and environmental monitoring instruments, other than portable instruments used to measure rad/h or rem/h levels, are outside the scope of this standard. Radon monitoring instruments are not within the scope of this standard. Since special-purpose instrumentation, such as emergency post-accident radiological monitors, may also fall under the scope of one or more related ANSI standards, this standard is intended to supplement rather than replace these standards. For example, ANSI N42.17A-1989 [133] sets forth requirements for instrument performance. In general, radiation protection instrumentation is considered to cover the dose and dose equivalent rate ranges for survey meters of 10µGy/h to 10 Gy/h (1 mrad/h to 1000 red/h) and 10µSv/h to 10 Sv/h (1 mrem/h to 1000 rein/h), and activity-per-unit-area ranges for surface contamination monitors of 2 Bq/100 cm2 to 20 000 Bn/100 cm2 (120 dpm/100 cm2to 1.2 x 106 dpm/100 cm2). Throughout this standard, three verbs have been used to indicate tile degree of rigor intended for each specific criterion. The word shall is used to denote a requirement. The word should is used to denote a recommendation. The word may is used to denote a permissible practice.

Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments