F84 辐射防护仪器 标准查询与下载

IEC 60846-2:2007 辐射防护仪表.β,X和γ辐射周围和/或定向剂量当量(率)仪和/或监测仪.第2部分:紧急情况放射线防护目的用的便携式高射程β,光子剂量

This part of the IEC 60846 series applies to pertable or transportable dose equivalent (rate) meters and/or monitors for the measurement of ambient and/or directional dose equivalent (rate)form external beta, X and gamma radiation during emergency situations.It applies directly to dose equivalent (rate)meters intended for the determination of the dose equivalent or dose equivalent rate form external beta and/or X and gamma radiation of energies up to 10 MeV during emergency situations. This part of the IEC 60846 series dose not specify which instruments are required nor does it comsider the munbers or specific locations of such instruments. This part of the IEC 60846 series dose not identify instrumentation for specific types of accicents.It is essential that the rated randes of the instruments and the radiological and non-radiological conditions for which the instruments are designed adequately cover the accident and post-accident conditions as determined by accident analysis and/or specified by appropriate regulatory authorities or qulaified individuals. It is expected that accidents will involve both dose quivalent (rate) and environmental extremes.Specitications for instruments for measuring dise equicalent rates less than the minimum detectable dose rate level specified in this part of the IEC 60846 series are contained in IEC 60846:2002. Where such instruments are also to be uesd for emergency measurements, they shall also meet the requirements of this part of the IEC 60846 series. Although this part of the IEC 60846 series specifies therequirements for instruments primarily for emergency use,such instruments may also be used for on-site measurements at other times. If the instrumnent hes a remote detector and if an additional detector is procided in the measuring assembly to measure dose equivalent rate at the location of the operator, the requirements shall apply to both of the detectors.

Radiation protection instrumentation - Ambient and/or directional dose equivalent (rate) meters and/or monitors for beta, X and gamma radiation - Part 2: High range beta and photon dose and dose rate portable instruments for emergency radiation protection

IEC 62387-1:2007 辐射防护测量仪.环境和个人监测用无源集成放射量测定系统.第1部分:一般特性和性能要求

This part of IEC 62387 applies to all kinds of passive dosimetry systems that are used for measuring the personal dose equivalents Hp(10) or Hp(0,07) or the ambient dose equivalent H*(10). It applies to dosimetry systems that measure external photon or beta radiation in the dose range between 0,01 mSv and 10 Sv and in the energy ranges given in the following Table. All the energy values are mean energies with respect to the prevailing dose quantity. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled. NOTE 1 In this standard, “dose” means personal or ambient dose equivalent, unless otherwise stated. NOTE 2 For Hp(10) and H*(10) no beta radiation is considered. Reasons: 1) Hp(10) and H*(10) are a conservative estimate for the effective dose which is not a suitable quantity for beta radiation. 2) No conversion coefficients are available in ICRU 56, ICRU 57 or ISO 6980. This standard is intended to be applied to dosimetry systems that are capable of evaluating doses in the required quantity and unit (Sv) from readout signals in any quantity and unit. The only correction that may be applied to the evaluated dose (indicated value) is the one resulting from natural background radiation using extra dosemeters. NOTE The correction due to natural background may be made before or after the dose calculation. In this standard, requirements are stated for minimal ranges of influence quantities, for example 80 keV to 1,25 MeV for photon energy (see Tables 3 to 5). A dosimetry system shall at least fulfil the requirements stated for these minimal ranges. However, the manufacturer may state larger ranges for the different influence quantities, for example 60 keV to 7 MeV. These larger ranges are called rated ranges. In such cases, the dosimetry systems must fulfil the requirements stated for these rated ranges. Thus, dosimetry systems can be classified by stating a set of ranges (for dose, energy, temperature etc.) within which the requirements stated in this standard are met (Capabilities of the system, see Clause 7). In addition, usage categories are given in Annex D with respect to different measuring capabilities.

Radiation protection instrumentation - Passive integrating dosimetry systems for environmental and personal monitoring - Part 1: General characteristics and performance requirements

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

Corrigendum to IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

Criteria for accident monitoring instrumentation for nuclear power generating stations - Corrigendum 1: Incorporations of user feedback through 2005

DIN IEC 61577-1:2007 辐射防护仪器.氡和氡衰变产物的测量仪器.第1部分:一般原则

Radiation protection instrumentation - Radon and radon decay product measuring instruments - Part 1: General principles (IEC 61577-1:2006)

DIN 6802-3:2007 中子剂量学.第3部分:辐射防护中中子测量方法

Neutron dosimetry - Part 3: Methods for neutron measurement in radiation protection

DIN VDE 0493 Bb.2:2007 辐射防护仪器.测量中不确定性的测定

Radiation protection instrumentation - Determination of uncertainty in measurement (IEC/TR 62461:2006)

IEC 60671:2007 核电站.仪器装置和控制系统的安全性.监督测试

Where functional reliability is required by general safety standards, one aspect of demonstrating this reliability is testing performed on-line during plant operation or during plant shutdown in preparation for return to power operation. This standard lays down principles for testing I&C systems performing category A, B and C functions, per IEC 61226, during normal power operation and shutdown, so as to check the functional availability especially with regard to the detection of faults that could prevent the proper operation of the functions important to safety. It covers the possibility of testing at short intervals or continuous surveillance, as well as periodic testing at longer intervals. It also establishes basic rules for the design and application of the test equipment and its interface with the systems important to safety. Further, the effect of any test equipment failure on the reliability of the I&C systems is considered. Types of surveillance tests may include: – self-tests for I&C equipment; – test of a group of equipment or components to confirm properties that support the safety function (continuity, power availability, etc.); – test based on information redundancy or comparison of control signatures (consistency checking for redundant sensors, CRC-checking, Checksum, etc.); – periodic testing which is related to the correctness of functional behaviour of an I&C system. The dependability targets of any I&C system is reached using an appropriate combination of tests of the form indicated above. The extent of the I&C system to be tested is from the interface of the sensors with the process through to the actuation devices. It is applicable to the installed I&C systems as well as to temporary installations which are part of those I&C systems important to safety (for example, auxiliary equipment for commissioning tests and experiments). This standard also applies to individual electromechanical equipment, such as relays and solenoid actuators. Additional testing and inspections may be performed on I&C equipment for purposes other than the demonstration of functional capability, such as to optimise preventive maintenance, etc. Such tests are beyond the scope of this standard; however, they may be combined with the surveillance testing discussed herein. For any on-line tests the potential interaction and fault dependencies between the part of the system under test and the testing part, have to be carefully studied and their influences have to be fully integrated into the reliability assessment of the functions important to safety (in accordance with IEC 61513). This standard applies to the I&C of new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants. For I&C upgrades, only a subset of the requirements may be applicable; this subset is to be identified at the beginning of any project.

Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing

BS IEC 60515:2007 核电站.对安全性重要仪器.辐射探测器.特性和试验方法.

This International Standard applies to the radiation detectors which are installed external to the core of nuclear reactors and which provide electrical input signals to the reactor’s control and instrumentation system. These detectors are usually gas-filled neutron detectors and this standard applies only to that type although many of its principles could be used for others, for example, gas-filled gamma radiation detectors. This standard therefore describes characteristics and tests methods for gas-filled radiation detectors used for the protection of nuclear reactors. The detectors subject to this standard are: • boron d.c. ionization chambers, • fission d.c. ionization chambers or fission pulse ionization chambers (fission counters), • boron trifluoride proportional pulse counter tubes, • helium-3 proportional pulse counter tubes. This standard may be used for d.c. ionization chambers for gamma radiation but the detectors discussed here are not used for personnel dosimetry. In-core radiation detectors are specifically addressed by IEC 60568 and IEC 61468. NOTE This list is not restrictive and it is hoped that all types of radiation detectors used in reactor installations will benefit from the present standard. The standard for tests also applies to connecting cables and connectors when they form an integral part of the detector.

Nuclear power plants - Instrumentation important to safety - Radiation detectors - Characteristics and test methods

BS 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Hp(10)和Hp(0.07)的测量.直读式个人剂量当量计和监控器

This International Standard applies to personal dose equivalent meters with the following characteristics: a) They are worn on the trunk or the extremities of the body. b) They measure the personal dose equivalents Hp (10) and Hp (0,07) from external X and gamma, neutron and beta radiations, and may measure the personal dose equivalent rates H& p (10) and H& p (0,07) . c) They have a digital indication. d) They may have alarm functions for the personal dose equivalents or personal dose equivalent rates. This standard is therefore applicable to the measurement of the following combinations of dose quantities (including the respective dose rates) and radiation 1) Hp(10) and Hp(0,07) from X and gamma radiations; 2) Hp(10) and Hp(0,07) from X, gamma and beta radiations; 3) Hp(10) from X and gamma radiations; 4) Hp(10) from neutron radiations; 5) Hp(10) from X, gamma and neutron radiations; 6) Hp(0,07) from X, gamma and beta radiations. This standard specifies, for the dosemeters described above, general characteristics, general test procedures, radiation characteristics as well as electrical, mechanical, safety and environmental characteristics. The only requirements specified for associated readout systems are those which affect its accuracy of readout of the personal dose equivalent and alarm settings and those which concern the influence of the reader on the dosemeter. This standard also specifies classes of personal dose equivalent meters in relation to retention of stored information (see 6.1). In addition, usage categories are given in Annex ZA with respect to different measuring capabilities. This standard does not cover special requirements for accidental or emergency dosimetry although the dosemeters may be used for this purpose. The standard does not apply to dosemeters used for measurement of pulsed radiation where the dose rate in the pulse exceeds the specification such as that emanating from linear accelerators or similar equipment.

Radiation protection instrumentation - Measurement of personal dose equivalents Hp(10) and Hp(0,07) for X, gamma, neutron and beta radiations - Direct reading personal dose equivalent meters and monitors

DIN EN 61582:2007 辐射防护测量仪表.体内计数管.轻便运输和已安装设备的分类、一般要求和试验过程

Radiation protection instrumentation - In vivo counters - Classification, general requirements and test procedures for portable, transportable and installed equipment (IEC 61582:2004, modified); German version EN 61582:2006

ASTM E910-07 反应堆容器监测用氦聚集流监视器应用和分析的标准试验方法.E 706(IIIC)

1.1 This test method describes the concept and use of helium accumulation for neutron fluence dosimetry for reactor vessel surveillance. Although this test method is directed toward applications in vessel surveillance, the concepts and techniques are equally applicable to the general field of neutron dosimetry. The various applications of this test method for reactor vessel surveillance are as follows:1.1.1 Helium accumulation fluence monitor (HAFM) capsules,1.1.2 Unencapsulated, or cadmium or gadolinium covered, radiometric monitors (RM) and HAFM wires for helium analysis,1.1.3 Charpy test block samples for helium accumulation, and1.1.4 Reactor vessel (RV) wall samples for helium accumulation.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 Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

IEEE/ANSI N42.41-2007 国家安全用主动监测系统的美国国家标准化最小性能准则

American National Standard Minimum Performance Criteria for Active Interrogation Systems Used for Homeland Security

ANSI N42.37-2006 国家安全目的阻拦和预防用辐射检测仪器的培训要求

The scope of this standard describes requirements for training in the use of personal radiation detectors (ANSI N42.32), portable radiation detection instruments (ANSI N42.33), portable radionuclide identifiers (ANSI N42.34) and portal radiation monitors

Training Requirements for Homeland Security Purposes Using Radiation Detection Instrumentation for Interdiction and Prevention

ANSI N42.43-2006 用于国家安全的可移动和可运输辐射监测器的性能标准

This standard specifies the operational and performance requirements for transportable and/or mobile radiation monitors used in Homeland Security applications. Transportable radiation monitors are designed to be transported to a location and used for a s

Performance Criteria for Mobile and Transportable Radiation Monitors used for Homeland Security

JIS Z 4341:2006 中子环境剂量当量率计

この規絡は，15MeV以下のエネルギーをもつ中性子のIcm線量当量(率)を測定する放射線サーべイメータ(以下，サーペイメータという。)について規定するものであり，サーペイメータには少なくとも次の装置のものを合む。

Neutron ambient dose equivalent (rate) meters

BS IEC 61577-1:2006 辐射防护仪.氡和氡衰变产品测量仪.总则

The IEC 61577 series covers the general features concerning test and calibration of radon and radon decay product measuring instruments. This standard addresses only the instruments and associated methods for measuring isotopes 220 and 222 of radon and their subsequent short-lived decay products in gases. Its object is to help to define type tests which have to be conducted in order to qualify these instruments. NOTE These type tests will be described in the future IEC 61577-2-1, IEC 61577-2-2, IEC 61577-3-1 and IEC 61577-3-2 (see IEC 61577 structure in Annex A). For the suitability of the document, this standard also proposes a classification of the instruments measuring radon or RnDP based on the duration of sampling.

Radiation protection instrumentation - Radon and radon decay product measuring instruments - General principles

BS EN 60861:2008 液体流出物和地表水中放射性核素用监测设备

Equipment for monitoring of radionuclides in liquid effluents and surface waters

IEC 60861:2006 排出废液和地表水中放射性核的监测设备

This International Standard defines technical requirements for equipment for monitoring of alpha-, beta- or gamma-emitting radionuclides in liquid effluents and surface waters, provides some general guidance as to the possible detection capability of such equipment and indicates when and where its uses may be practicable. NOTE Alpha monitoring in liquids is a possibility that has been demonstrated using a concentration device and collection of the concentrate in a filter, so this standard may also be applicable to alpha monitoring in liquids. This standard is applicable to equipment for continuous monitoring of the activity: – in liquid effluents which could be released in the environment during normal operations; – in environmental waters. This standard does not apply to equipment specifically for use in accident conditions that may require additional capabilities. This standard is restricted to equipment for continuous monitoring of gross alpha or gross beta of maximum energy higher than 150 keV or gamma activity in liquid effluent streams and environmental waters. It does not deal with sample extraction and laboratory analysis. The object of this standard is to lay down general requirements and give examples of acceptable methods for equipment to monitor continuously the activity of water. This International Standard specifies, for the equipment described in the scope, the general characteristics, general test procedures, radiation, electrical, safety and environmental characteristics, and the identification and certification of the equipment. Performance requirements for the safe operation of electrical equipment are provided in IEC 61010-1. These safety requirements and corresponding tests are applicable if the manufacturer wants to, or is required to, label its equipment with the appropriate safety mark (for example, CE, UL, etc.). This standard is applicable to water monitors intended to fulfil the following functions: – measurement of the volumetric activity or count rate (see 5.1.2) due to radionuclides in the liquid and its variation with time; – actuation of an alarm when a limit value of volumetric activity or count rate in water is exceeded. Annex A gives some guidance for use with radioactive water monitors.

Equipment for monitoring of radionuclides in liquid effluents and surface waters

BS EN 62244:2011 辐射保护仪器.在国际边境地区探测放射性和特殊核材料用的现场组装辐射监测器

Radiation protection instrumentation. Installed radiation monitors for the detection of radioactive and special nuclear materials at national borders

BS IEC 62244:2006 辐射防护仪.在国家边境地区探测放射性和特种核材料安装的辐射监控器

The scope of this International Standard is to define the performance of installed monitors used for the detection of gamma and neutron radiation emitters contained in objects/ containers or vehicles, general characteristics, mechanical characteristics, environmental requirements, test procedures and documentation. This standard is applicable to installed monitors designed to detect special nuclear and other radioactive materials by their emitted gamma and/or neutron radiation. They are used to monitor vehicles, cargo containers, people, or packages and are typically located at national and international borders, but may be used at any location where there is a need for this type of monitoring. This standard does not apply to hand-held monitors. Information regarding the detection of special nuclear material (SNM) is contained in Annex A. This standard provides the purchaser with information that may be used to determine the performance of the monitor in detecting the presence of radioactive sources. This standard does not provide the data needed to determine the performance of the monitor in measuring the quantity of the radioactive material. In this standard, the term radioactive material includes both special nuclear and radioactive material unless otherwise specifically noted. The radioactive material may be transported by vehicle, carried by person, or concealed in a cargo container or in a package moved by conveyor belt, such as international mail parcels. Conformance with the requirements of this standard does not guarantee that a radioactive source will always be discovered. The selection of the location and the configuration of the monitoring system on each site needs to be optimised to achieve the best performance, however, this is outside the scope of this standard.

Radiation protection instrumentation - Installed radiation monitors for the detection of radioactive and special nuclear materials at national borders