F74 辐射防护监测与评价 标准查询与下载

BS ISO 19238:2004 辐射防护.进行细胞遗传学生物剂量测定的工作实验室的性能标准

ISO 19238:2004 provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories.

Radiation protection - Performance criteria for service laboratories performing biological dosimetry by cytogenetics

NF M60-800:2004 核能.环境放射性的测量.水.根据低盐水中的锶90和钇90当量测量β总的活性指数

Nuclear energy - Measurement of environmental radioactivity - Water - Measurement of global beta activity index in terms of strontium 90 and yttrium 90 equivalent in low salted water.

NF M60-764:2004 核能.环境中放射性的测量.空气.氡222:大气环境中氡的短寿命衰变产物的α位能的综合测量方法

Nuclear energy - Measurement of environmental radioactivity - Air - Radon 222 : methods for integrated measurement of the alpha potential energy of short-life decay products of radon in the atmospheric environment.

NF M60-801:2004 核能.环境放射性的测量.水.根据低盐水中的钚239当量测量α活性指数

Nuclear energy - Measurement of environmental radioactivity - Water - Measurement of alpha activity index in terms of plutonium 239 equivalent in low salted water.

NF M60-765:2004 核能.环境中放射性的测量.空气.氡222:大气环境中氡的短寿命衰变产物的α位能的现场测量方法

Nuclear energy - Measurement of radioactivity in the enviromment - Air - Radon 222 : methods for spot measurement of the alpha potential energy of short-life decay products of radon in the atmospheric environnement.

NF M60-763:2004 核能.环境中放射性的测量.空气.在大气环境中氡222和其短寿命衰变产物:它们的来源和测量方法

Nuclear energy - Measurement of radioactivity in the enviromment - Air - Radon 222 and its short-life decay products in the atmospheric environment : their origins and measuring methods.

NF M60-766:2004 核能.环境中放射性的测量.空气.氡222:在无源采集和延迟分析下进行氡在大气环境中的平均容量活性的综合测量方法

Nuclear energy - Measurement of radioactivity in the enviromment - Air - Radon 222 : methods for integrated measurement of the average volumic activity of radon in the atmospheric environment, with a passive collection and an deferred analysis.

ISO 22188:2004 放射性物质的无意中移动和违禁运输的监控

This International Standard specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable (e.g. handheld) instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e. requirements derived for monitoring of traffic and commodities mainly at bordercrossing facilities. Although the term border is used repeatedly in this International Standard, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. This document does not address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals may be done at the borders of a state. This International Standard is applicable to regulatory authorities seeking guidance on implementation of action plans to combat illicit trafficking, to law enforcement agencies (e.g. border guards) to obtain guidelines on recommended monitoring procedures, and to equipment manufacturers in order to understand minimum requirements derived from operational necessities according to this International Standard.

Monitoring for inadvertent movement and illicit trafficking of radioactive material

NF M60-804-1:2004 核能.用α光谱测定法对水中铀后元素(Pu, Am, Cm, Np)的活性测量.第1部分:一般信息

Nuclear energy - Activity measurement of transuranium elements (Pu, Am, Cm, Np) in water with alpha spectrometry - Part 1 : general informations.

NF M60-804-2:2004 核能.用α光谱测定法对水中铀后元素(Pu, Am, Cm)的活性测量.第2部分:用阴离子阳离子树脂和色层分离萃取法分离放射性核素

Nuclear energy - Activity measurement of transuranium elements (Pu, Am, Cm) in water with alpha spectrometry - Part 2 : radionuclides separation with anionic and cationic resines and chromatographic extraction.

NF M60-804-3:2004 核能.用α光谱测定法对水中铀后元素(Pu, Am, Cm, Np)的活性测量.第3部分:用色层分离萃取法分离放射性核素(小容量)

Nuclear energy - Activity measurement of transuranium elements (Pu, Am, Cm, Np) in water with alpha spectrometry - Part 3 : radionuclides separation with chromatographic extraction (small volumes).

EJ 1153-2004 X、γ外照射个人监测规定

Regulations of individual monitoring for X, γ ray external exposure

ANSI/ISO/ASTM 51310E 1310:2004 辐射变色光波导管计量学系统使用实施规程

Practice for Use of a Radiochromic Optical Waveguide Dosimetry System

ANSI/ISO/ASTM 51540E 1540:2004 辐射变色液体计量学系统使用的实施规程

Practice for Use of a Radiochromic Liquid Dosimetry System

KS A IEC 61005:2003 防辐射便携式中子周围等价剂量率计

1.1.1 이 규격은 16 MeV 이하 에너지의 중성자선에 의한 주위 등가 선량률(1.3.

Portable neutron ambient dose equivalent ratemeters for use in radiation protection

ASTM E261-03 用放射性技术测定中子的积分通量、积分通量率和中子波谱的标准实施规范

Transmutation Processes8212;The effect on materials of bombardment by neutrons depends on the energy of the neutrons; therefore, it is important that the energy distribution of the neutron fluence, as well as the total fluence, be determined.1.1 This practice describes the general procedures for the determination of neutron fluence rate, fluence, and energy spectra from the radioactivity that is induced in a detector specimen. 1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials. 1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E 1005. 1.4 This standard does not purport to address all 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. Note 18212;Detailed methods for individual detectors are given in the following ASTM test methods: E 262, E 263, E 264, E 265, E 266, E 343, E 393, E 418, E 481, E 523, E 526, E 704, E 705, and E 854.

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

JIS Z 4332:2002 检测Χ和γ射线辐射用个人剂量计的一般要求

この規格は，x線及びγ線によって個人が体外から受ける1 cm線量当量及び70μm線量当量を測定するため，体幹部に装着する個人線量計の一般事項について規定する。

General requirements of personal dosemeters for X and gamma radiations

ASTM E1035-02 核反应堆容器支承结构的中子辐照量测定标准实施规程

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. Recently, it has become apparent that the support structures for pressurized water reactor vessels may also be subject to similar neutron radiation effects (1, 2, 3, 4, 5).7 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 x 1017 neutrons/cm 2 or 3.0 x 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 E266-02 通过铝的辐射激活化法测量快中子反应速率的标准试验方法

1.1 This test method covers procedures measuring reaction rates by the activation reaction 7Al(n,alpha)24Na.1.2 This activation reaction is useful for measuring neutrons with energies above approximately 6.5 MeV and for irradiation times up to about 2 days (for longer irradiations, see Practice E 261).1.3 With suitable techniques, fission-neutron fluence rates above 106cm-2183;s-1 can be determined.1.4 Detailed procedures for other fast neutron detectors are referenced in Practice E 261.1.5 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 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

ASTM E2232-02 辐射处理中计算吸收剂量的数学方法的选择和使用的标准指南

1.1 This guide describes different mathematical methods that may be used to calculate absorbed dose and criteria for their selection. Absorbed dose calculations determine the effectiveness of the radiation process, estimate the absorbed-dose distribution in product, or supplement and/or complement dosimetry measurements.1.2 Radiation processing is an evolving field and annotated examples are provided in to illustrate the applications where mathematical methods have been successfully applied. While not limited by the applications cited in these examples, applications specific to neutron transport, radiation therapy and shielding design are not addressed in this document.1.3 This guide covers the calculation of radiation transport of electrons and photons in the energy range of 0.1 to 25 MeV.1.4 The mathematical methods described include Monte Carlo, point kernel, discrete ordinate, semi-empirical and empirical methods.1.5 General purpose software packages are available for the calculation of the transport of charged and/or neutral particles and photons from various types of sources of ionizing radiation. This standard is limited to the use of these software packages or other mathematical methods for the determination of spatial dose distributions for photons emitted following the decay of 137Cs or 60Co, energetic electrons from particle accelerators, or bremsstrahlung generated by electron accelerators.1.6 This guide assists the user in determining if mathematical methods are a useful tool. This guide may assist the user in selecting an appropriate method for calculating absorbed dose.Note 18212;The user is urged to apply these predictive techniques while being aware of the need for experience and also the inherent limitations of both the method and the available software. Information pertaining to availability and updates to codes for modeling radiation transport, courses, workshops and meetings can be found in . For a basic understanding of radiation physics and a brief overview of method selection, refer to .1.7 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 requirements prior to use.

Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications