ISO 8529-1:2001 基准中子辐射-第一部分：产品特性和方法

标准编号：ISO 8529-1:2001

中文名称：基准中子辐射-第一部分：产品特性和方法

英文名称：Reference neutron radiations — Part 1: Characteristics and methods of production

发布日期：2001-02

标准范围

ISO 8529的这一部分规定了参考中子辐射，能量范围从热能到20 MeV，用于校准用于辐射防护目的的中子测量装置并确定其响应作为中子能量的函数。给出了中子注量率高达1 109 m？的参考辐射？2美元？1.相应地，在1 MeV的中子能量下，剂量当量率高达100 mSv_h？1.ISO 8529的本部分仅涉及中子基准的产生和表征方法辐射。ISO 8529-2和ISO 8529-2中描述了将这些辐射用于校准的程序ISO 8529-3。规定的参考辐射如下:_来自放射性核素源的中子，包括来自慢化剂源的中子；_与加速器带电粒子发生核反应产生的中子；_来自反应堆的中子。考虑到它们的生产和使用方法，这些参考辐射被划分为ISO 8529的这一部分分为以下两个单独的部分。_第4条规定了宽光谱放射性核素中子源用于中子测量的校准设备。这些源应由从事常规校准的实验室使用中子测量装置，其特殊设计已经过型式试验。_在第5条中，加速器产生的单能中子和反应堆产生的宽或准能中子规定了单能谱，以确定中子测量装置作为函数的响应中子能。因为这些参考辐射是在专业和装备精良的工厂产生的在实验室中，只给出了最小的实验细节。将中子注量转换为辐射防护推荐量，根据规范性附录A中给出的光谱，并使用ICRP出版物74中给出的作为中子能量函数的剂量当量转换系数通量ICRU第57号报告。

This part of ISO 8529 specifies the reference neutron radiations, in the energy range from thermal up to 20 MeV,for calibrating neutron-measuring devices used for radiation protection purposes and for determining their responseas a function of neutron energy. Reference radiations are given for neutron fluence rates of up to 1 _ 109 m?2_s?1,corresponding, at a neutron energy of 1 MeV, to dose-equivalent rates of up to 100 mSv_h?1.This part of ISO 8529 is concerned only with the methods of producing and characterizing the neutron referenceradiations. The procedures for applying these radiations for calibrations are described in ISO 8529-2 andISO 8529-3.The reference radiations specified are the following:_ neutrons from radionuclide sources, including neutrons from sources in a moderator;_ neutrons produced by nuclear reactions with charged particles from accelerators;_ neutrons from reactors.In view of the methods of production and use of them, these reference radiations are divided, for the purposes ofthis part of ISO 8529, into the following two separate sections._ In clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutronmeasuringdevices. These sources should be used by laboratories engaged in the routine calibration ofneutron-measuring devices, the particular design of which has already been type tested._ In clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasimonoenergetic spectra are specified for determining the response of neutron-measuring devices as a functionof neutron energy. Since these reference radiations are produced at specialized and well equippedlaboratories, only the minimum of experimental detail is given.For the conversion of neutron fluence into the quantities recommended for radiation protection purposes,conversion coefficients have been calculated based on the spectra presented in normative annex A and using thefluence-to-dose-equivalent conversion coefficients as a function of neutron energy as given in ICRP Publication 74and ICRU Report 57.

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