F74 辐射防护监测与评价 标准查询与下载

IEEE N42.44-2008 检查站房间式X射线成像安全系统的性能用美国国家标准

This document establishes standards for the technical performance of cabinet x-ray imaging systems used for screening at security checkpoints and other inspection venues. Included are all x-ray systems designed primarily for the inspection of baggage at airline, railroad, and bus terminals, and in similar facilities. An xray tube used within a shielded part of a building, or x-ray equipment that may temporarily or occasionally incorporate portable shielding, is not considered to be a cabinet x-ray system. Hereinafter, systems covered by the scope of this standard are referred to as the system. This standard applies to x-ray imaging equipment with all of the following characteristics: -Meet the definition of cabinet x-ray systems as given in 21 CFR 1020.40 -Operate at or above 120 kV -Have tunnel nominal dimensions of up to 1.1 m × 1.1 m -Provide a single-view direct-projection image as the primary image -Are used to examine items to detect prohibited and illicit materials at security-checkpoint locations (e.g., airports, seaports, land border crossings, office buildings, court houses, correctional institutions, nuclear power facilities, military facilities, commercial shipping and receiving stations, stations used for manifest verification) For further clarification, systems included in this standard can be those with or without organic/inorganic differentiation, with or without active or passive threat alerts, and those incorporating multi-view and computed-tomography (CT) imaging (if the primary image presented is a single-view projection image), if they have all of the characteristics found in the list above. This standard therefore is not intended for x-ray imaging systems with any of the following characteristics: -Operate at potentials that are less than 120 kV -Are not cabinet systems (e.g., open bomb-squad systems) -Do not present a direct-projection image -Can provide a projection image only through image reconstruction from multiple views -Are based primarily on the use of CT -Are used for medical diagnostic imaging -Are used for non-destructive evaluation (NDE) or non-destructive testing (NDT), industrial quality control (e.g., food inspection), industrial sortation of recyclables or natural resource extraction, systems used for scientific research purposes -Are based only on backscattered or coherently scattered x-rays This standard specifies minimum requirements and test procedures for x-ray imaging performance, radiation-limitation requirements, and electrical, mechanical, and environmental requirements. This standard addresses technical image-quality performance, not threat-detection performance.

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

BS ISO 21243:2008 辐射防护.放射线或核紧急事件中大量人员伤亡评估用实验室实施细胞生成治疗类选法的性能标准.dicentric试验的一般原理和应用

Radiation protection - Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay

KS I ISO 10155:2008 固定源排放.颗粒物质量浓度自动监测.工作特性、试验方法和规范

이 표준은 고정 오염원 가스 흐름 안의 입자상 물질의 질량 농도를 자동 모니터링하는 조건과

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

IEEE N42.46-2008 货物和车辆安全审查用X射线及γ射线系统的测定用美国国家标准

This standard is intended to be used to determine the imaging performance of x-ray and gamma-ray systems utilized to inspect loaded or empty vehicles, including personal and commercial vehicles of any type; marine and air cargo containers of any size; railroad cars; and palletized or unpalletized cargo larger than 1 m × 1 m in cross-section. The standard applies to systems that are the following: -Single or multiple energy, source, or view -Employ primary (i.e., transmission) and/or scatter (e.g., backscatter) radiation detection -Used to detect prohibited and controlled materials and/or to verify manifests -Primarily imaging systems but also may have complementary features such as material discrimination and automatic active or passive threat alerts. This standard does not address how to test these complementary features. Adherence to all applicable mechanical and electrical safety requirements and compatibility with all applicable installation codes, including electro-magnetic compatibility requirements, is extremely important for any type of x-ray or gamma-ray screening system; however, identification of these requirements is not within the scope of this standard.

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

BS ISO 18589-1:2008 环境中辐射性的测量.土壤.一般指南和定义

Measurement of radioactivity in the environment - Soil - General guidelines and definitions

NF M60-761-3:2008 核能.环境中放射性测量.水.第3部分:氡222及其水中短暂子核:除气测量.

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 3 : radon 222 and its short-lived daughters in water : measurements by degassing.

NF M60-790-2:2008 环境中放射能的测量.土壤.第2部分:取样方案的选择、取样和样品预处理用指南

Measurements of radioactivity in the environment - Soil - Part 2 : guidance for the selection of the sampling strategy, sampling and pre-treatment of samples.

NF M60-790-3:2008 环境辐射性的测量.土壤.第3部分:γ辐射放射性核素的测量

Measurements of radioactivity in the environment - Soil - Part 3 : measurements of gamma-emitting radionuclides.

ISO 12789-2:2008 参考辐射区域.模拟工作场所中子区域.第2部分:与基础量相关的校准基本原则

Reference radiation fields - Simulated workplace neutron fields - Part 2: Calibration fundamentals related to the basic quantities

BS ISO 18589-2:2008 环境辐射的测量.土壤.抽样方法的选择,抽样和样品预处理指南

Measurement of radioactivity in the environment - Soil - Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

BS ISO 18589-3:2008 环境辐射性的测量.土壤.γ辐射放射性核素的测量

Measurement of radioactivity in the environment - Soil - Measurement of gamma-emitting radionuclides

ASTM E262-08 用放射性技术测定热中子反应和注量率的标准试验方法

This test method can be extended to use any material that has the necessary nuclear and activation properties that suit the experimenter''s particular situation. No attempt has been made to fully describe the myriad problems of counting techniques, neutron-fluence depression, and thick-foil self-shielding. It is assumed that the experimenter will refer to existing literature on these subjects. This test method does offer a referee technique (the standard gold foil irradiation at National Institute of Standards and Technology (NIST) to aid the experimenter when he is in doubt of his ability to perform the radiometric technique with sufficient accuracy. The standard comparison technique uses a set of foils that are as nearly identical as possible in shape and mass. The foils are fabricated from any material that activates by an (n, γ) reaction, preferably having a cross section approximately inversely proportional to neutron speed in the thermal energy range. Some of the foils are irradiated in a known neutron field (at NIST) or other standards laboratory). The foils are counted in a fixed geometry on a stable radiation-detecting instrument. The neutron induced reaction rate of the foils is computed from the counting data, and the ratio of the known neutron fluence rate to the computed reaction rate is determined. For any given foil, neutron energy spectrum, and counting set-up, this ratio is a constant. Other foils from the identical set can now be exposed to an unknown neutron field. The magnitude of the fluence rate in the unknown field can be obtained by comparing the reaction rates as determined from the counting data from the unknown and reference field, with proper corrections to account for spectral differences between the two fields (see Section 5). One important feature of this technique is that it eliminates the need for knowing the detector efficiency.1.1 The purpose of this test method is to define a general procedure for determining an unknown thermal-neutron fluence rate by neutron activation techniques. It is not practicable to describe completely a technique applicable to the large number of experimental situations that require the measurement of a thermal-neutron fluence rate. Therefore, this method is presented so that the user may adapt to his particular situation the fundamental procedures of the following techniques. 1.1.1 Radiometric counting technique using pure cobalt, pure gold, pure indium, cobalt-aluminum, alloy, gold-aluminum alloy, or indium-aluminum alloy. 1.1.2 Standard comparison technique using pure gold, or gold-aluminum alloy, and 1.1.3 Secondary standard comparison techniques using pure indium, indium-aluminum alloy, pure dysprosium, or dysprosium-aluminum alloy. 1.2 The techniques presented are limited to measurements at room temperatures. However, special problems when making thermal-neutron fluence rate measurements in high-temperature environments are discussed in 9.2. For those circumstances where the use of cadmium as a thermal shield is undesirable because of potential spectrum perturbations or of temperatures above the melting point of cadmium, the method described in Test Method E 481 can be used in some cases. Alternatively, gadolinium filters may be used instead of cadmium. For high temperature applications in which aluminum alloys are unsuitable, other alloys such as cobalt-nickel or cobalt-vanadium have been used. 1.3 This test method may be used to determine the equivalent 2200 m/s fluence rate. The accurate determination of the actual thermal neutron fluence rate requires knowledge of the neutron temperature, and determination of the neutron temperature is not within the scope of the standard. 1.4 The techniques presented are suitable on......

Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques

ASTM E1035-08 核反应堆容器支承结构的中子辐照测定的标准实施规程

Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.2) and national standards groups (see 2.1) have promulgated regulations and standards to ensure safe operation of these vessels. The support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 2, 3, 4, 5). The objective of this practice is to provide guidelines for determining the neutron radiation exposures experienced by individual vessel supports. It is known that high energy photons can also produce displacement damage effects that may be similar to those produced by neutrons. These effects are known to be much less at the belt line of a light water reactor pressure vessel than those induced by neutrons. The same has not been proven for all locations within vessel support structures. Therefore, it may be prudent to apply coupled neutron-photon transport methods and photon induced displacement cross sections to determine whether gamma-induced dpa exceeds the screening level of 3.0 × 10-4, used in this practice for neutron exposures. See 1.2.1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for: 1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities. 1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures. 1.2 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm2 or 3.0 × 10−4 dpa. (See Terminology E 170.) 1.3 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2. 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 Determining NeutronExposures for Nuclear Reactor Vessel Support Structures

ASTM E264-08 通过镍的放射性测量快中子反应速率的试验方法

Refer to Guide E 844 for the selection, irradiation, and quality control of neutron dosimeters. Refer to Practice E 261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors. Pure nickel in the form of foil or wire is readily available, and easily handled. 58Co has a half-life of 70.86 days and emits a gamma ray with an energy of 0.8107593-MeV. Competing activities 65Ni(2.5172 h) and 57Ni(35.60 h) are formed by the reactions 64Ni(n,γ) 65Ni, and 58Ni(n,2n)57Ni, respectively. A second 9.04 h isomer, 58mCo, is formed that decays to 70.86-day 58Co. Loss of 58Co and 58mCo by thermal-neutron burnout will occur in environments , having thermal fluence rates of 3 × 1012 cm−2·s−1 and above. Burnout correction factors, R, are plotted as a function of time for several thermal fluxes in Fig. 1. Tabulated values for a continuous irradiation time are provided in Hogg, et al. Fig. 2 shows a plot of cross section versus energy for the fast-neutron reaction 58Ni(n,p) 58Co. This figure is for illustrative purposes only to indicate the range of response of the 58Ni(n,p) reaction. Refer to Guide E 1018 for descriptions of recommended tabulated dosimetry cross sections. Note 18212;The data is taken from the Evaluated Nuclear Data File, ENDF/B-VI, rather than the later ENDF/B-VII. This is in accordance with E 1018, section 6.1, since the later ENDF/B-VII data files do not include covariance information. For more details see Section H of reference 8. FIG. 2 58Ni(n,p)58Co Cross Section1.1 This test method covers procedures for measuring reaction rates by the activation reaction 58Ni(n,p)58Co. 1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.1 MeV and for irradiation times up to about 200 days in the absence of high thermal neutron fluence rates (for longer irradiations, see Practice E 261). 1.3 With suitable techniques fission-neutron fluence rates densities above 107 cm−2·s−1 can be determined. 1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E 261. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.6 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. Note8212;The burnup corrections were computed using effective burn-up cross sections of 1650 b for 58Co(n,γ) and 1.4E5 b for 58mCo(n,......

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel

ASTM E2601-08 辐射应急响应标准做法

It is essential for response agency personnel to plan, develop, implement, and train on standardized guidelines that encompass policy, strategy, operations, and tactical decisions prior to responding to a radiological incident. Use of this standard is recommended for all levels of the response structure. Documents developed from this standard practice shall be referenced and revised as necessary and reviewed on a two-year cycle (at a minimum). The review shall consider new and updated requirements and guidance, technologies, and other information or equipment that might have a significant impact on the management and outcome of radiological incidents.1.1 This practice provides decision-making considerations for response to incidents that involve radioactive materials. It provides information and guidance for what to include in response planning, and what activities to conduct during a response. The scope of this standard does not explicitly consider response to INDs or nuclear power plant accidents. It does not expressly address emergency response to contamination of food or water supplies. 1.2 This practice applies to those emergency response agencies that have a role in the response to a radiological incident, excluding an IND incident. It should be used in emergency services response such as law enforcement, fire department, and emergency medical response actions. 1.3 This practice assumes that implementation begins with the recognition of a radiological incident and ends when emergency response actions cease or the response is assumed by specialized regional, state, or federal response teams. 1.4 AHJs using this practice will identify hazards, develop a plan, acquire and track equipment, and provide training consistent with the descriptions provided in Section 6. AHJs not able to meet the requirements should refer to the United States (US) Department of Transportation (DOT) Emergency Response Guidebook (ERG) for guidance on how to manage radiological incidents (DOT, current version). This standard provides additional guidance and is not intended to replace the ERG, rather to supplement it (see Annex A1 ). 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 Practice for Radiological Emergency Response

NF M60-808:2007 核能.环境中放射能的测量.水.用α光谱测定法测量水中钋210的放射性

Nuclear energy - Measurement of the radioactivity in the environment - Water - Measurement of polonium 210 activity in water by alpha spectrometry.

NF M60-761-1:2007 核能.环境中放射性测量.水.第1部分:水中氡222及其短期子体产物:它们的起源和测量方法

Nuclear energy - Measurement of radioactivity in the environment - Water - Part 1 : Radon 222 and its short lived daughter products in water : their origins and measurement methods.

SN/T 0570-2007 进口可用作原料的废物放射性污染检验规程

本标准规定了进口可用作原料的废物放射性污染的检验方法和检验结果的判定规则。 本标准适用于进口的废物原料的放射性污染的检验方法和检验结果的判定规则。

Rules of the inspection for radioactive contamination of scrap imported as raw material

ASTM D7362-07 放射锶空中沉积用植物的快速筛检用标准指南

Strontium-90 is a major component of nuclear waste and is also a potential radioisotope for use as a weapon of mass destruction in a radiological dispersal device. It is a beta-emitting radioisotope with moderate half-life (~30 years). Strontium-89 is also a beta emitting radionuclide, but with a half-life of only ~50 days it is not usually present in significant quantities. If ingested the radiostrontium may deposit in the bone of an individual and thus can contribute a significant radiological dose to an affected person. Following an explosion in which radioactive material was present, the potential exists for the material to become airborne. It will quickly attach to atmospheric particles and be deposited on surfaces as the plume passes. This guide provides a rapid procedure by which vegetation can be screened to determine if radiostrontium is present and to provide a conservative estimate of its deposition on vegetation. This guide is intended to be used in a field portable lab, or if needed, can be performed completely in the field; therefore no hazardous chemicals are required to complete the analysis. However, an option for the use of acid in certain steps is documented in this guide. This guide is not intended to be used for screening food products or animal feed following an accident or incident.1.1 This guide provides a rapid procedure by which vegetation samples may be screened for surface contamination of radioactive strontium (89Sr and 90Sr, collectively referred to as radiostrontium) following an airborne radioactive dispersal event. It provides a conservative estimate of radiostrontium deposition that can be used by decision makers for immediate actions prior to obtaining definitive results from a fixed laboratory asset.1.2 Insoluble forms of radiostrontium, such as the strontium (90Sr) titanate (SrTiO3) used in radio-isotope thermal-electric generators (RTGs), will not be measured by this method.1.3 Non-SI units are used in the calculations of this guide for ease of use during the emergency phase of an event. The instrumentation used typically provides count rates in counts per minute (cpm) rather than per second (s-1, the SI unit), thus activity is expressed in dpm (decays per minute) rather than Bq. Additionally, US EPA protective guidelines for surface contamination are expressed in dpm/100 cm2.1.4 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 Rapid Screening of Vegetation for Radioactive Strontium Aerial Deposition

JIS Z 4316:2006 放射性气溶胶监测仪

この規格は，施設の作業環境，周辺環境,施設の排気系などにおいて，ろ過式ダストサンプラなどによって空気中に浮遊する放射性粒子状物質(以下，放射性ダストという。)を採取し，ガイガ?ミュラー計数管，シンチレーション検出器などによってα線，β線又はγ線のいずれガを検出して，その指示値が放射線管理上設定された放射能レべル以上であったとき，放射線防護を目的として，警報を発する放射性ダストモニタ(以下，ダストモニタという。)について規定する。

Radioactive aerosol monitors